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Sample records for brunswick steam electric

  1. Brunswick steam electric plant probabilistic fire analysis

    International Nuclear Information System (INIS)

    A probabilistic safety analysis of fires was performed for the Brunswick Plant as part of the overall BSEP probabilistic risk assessment (PRA) program. The prime feature of the model is that plant-specific historical data were used to calculate the frequency of fire ignition for each zone. Fire growth and suppression parameters leading to fires of sufficient size to cause damage to redundant trains of equipment were also developed. The Brunswick Plant fire model was developed in such a way as to easily identify dominant fire zones, ignition sources, combustible sources, cable damage locations, and random equipment failures. After NRC reviews, it is expected that this probabilistic fire analysis model will continue to be used as a basis for fire risk reduction activities, for continued improvements to the fire protection program and procedures, and possibly for supporting licensing positions. 9 refs

  2. 75 FR 16871 - Carolina Power & Light Company, Brunswick Steam Electric Plant, Units 1 and 2; Exemption

    Science.gov (United States)

    2010-04-02

    ... significant effect on the quality of the human environment (75 FR 8753, February 25, 2010). This exemption is... License Nos. DPR-71 and DPR-62, which authorize operation of the Brunswick Steam Electric Plant (BSEP... requirements that BSEP now seeks an exemption from the March 31, 2010, implementation date. All other...

  3. 76 FR 53970 - Carolina Power & Light; Brunswick Steam Electric Plant, Units 1 and 2; Independent Spent Fuel...

    Science.gov (United States)

    2011-08-30

    ... accordance with the NRC E-Filing rule (72 FR 49139, August 28, 2007). The E-Filing process requires... Licenses Nos. DPR-71 and DPR-62 for the Brunswick Steam Electric Plant (BSEP), Units 1 and 2, including the BSEP Independent Spent Fuel Storage Installation, currently held by Carolina Power & Light Company,...

  4. 75 FR 8753 - Carolina Power & Light Company, Brunswick Steam Electric Plant, Units 1 and 2; Environmental...

    Science.gov (United States)

    2010-02-25

    ... part 73 as discussed in a Federal Register notice dated March 27, 2009 (74 FR 13967). There will be no... Requirements, 74 FR 13926, 13967 (March 27, 2009)). The licensee currently maintains a security system... Electric Plant, Units 1 and 2 (BSEP), located in Brunswick County, North Carolina. In accordance with...

  5. Technical evaluation report on the monitoring of electric power to the reactor-protection system for the Brunswick Steam Electric Plant, Units 1 and 2

    International Nuclear Information System (INIS)

    This report documents the technical evaluation of the monitoring of electric power to the reactor protection system (RPS) at the Brunswick Steam Electric Plant, Units 1 and 2. The evaluation is to determine if the proposed design modification will protect the RPS from abnormal voltage and frequency conditions which could be supplied from the power supplies and will meet certain requirements set forth by the Nuclear Regulatory Commission. The proposed design modifications with time delays verified by GE, will protect the RPS from sustained abnormal voltage and frequency conditions from the supplying sources

  6. Start-up support for New Brunswick Electric's Point Lepreau nuclear steam generators

    International Nuclear Information System (INIS)

    The start-up of the 600 MW Point Lepreau reactor provided the opportunity for direct involvement in the important low and medium power start-up phase which was of particular interest because this was a first-of-a-kind reactor type incorporating a new steam generator design. Support included test assistance and test results interpretation for the thermal hydraulic performance of the steam generators and in particular, investigation of water level response to operating pressure, power and feed flow. This work resulted in both a greatly improved understanding of transient characteristics and in a number of beneficial refinements in the control methods

  7. Brunswick Steam Electric Plant, Units 1 and 2. Annual operating report for 1976

    International Nuclear Information System (INIS)

    Net electrical energy generated by Unit 1 was 30,399 MWH with the generator on line 334.5 hrs. Unit 2 generated 2,481,014 MWH with the generator on line 4,915.53 hrs. Information is presented concerning operations, shutdowns and power reductions, maintenance, power generation, modifications, changes to operational procedures, radiation exposures, and leak rate testing

  8. A competitive electricity future for New Brunswick

    Energy Technology Data Exchange (ETDEWEB)

    Adams, T.

    1998-05-26

    The direction of New Brunswick`s power system was examined by a task Force on electricity, having as its objective the encouragement of discussion of important public policy matters regarding New Brunswick`s energy industry. This study was a submission to the Task Force by Energy Probe, to help expand public understanding of some underlying technical and economic issues, and to encourage positive solutions to New Brunswick Power`s problems based on privatization, competition, a reduced rate of environmental injury and enhanced regulation. The study also expresses Energy Probe`s concern regarding the integrity of the public process surrounding discussions of electricity policy in New Brunswick. The concern is based on NB Power`s now resolved defamation suit against the Atlantic Institute for Market Studies, Energy Probe, and the author of this submission. The study suggests that the main problems with New Brunswick`s electricity future are NB Power`s financial liabilities and its nuclear problems, including nuclear waste disposal, decommissioning costs, production problems, safety problems and rising costs. The study recommends that the provincial government cease to provide any further loan guarantees for NB Power, treat existing obligations as preferred liabilities, and promote as much competition as possible in the energy sector between fuels and between producers and marketers of energy products. It also recommends that given the results of the technical and economic study of Point Lepreau, the province of New Brunswick should begin the process of preparing for a non-nuclear future.

  9. New Brunswick electricity market rules : summary

    International Nuclear Information System (INIS)

    The electricity market rules for New Brunswick were reviewed with particular reference to two broad classifications. The first classification is based on the roles and responsibilities of the system operator (SO) in facilitating the Bilateral Contract market, as well as the role of market participants in participating in the Bilateral Contract market. The second classification is based on the roles and responsibilities of each of the SO, market participants and transmitters in maintaining the reliability of the integrated electricity system and ensuring a secure supply of electricity for consumers in New Brunswick. The market rules consist of 10 chapters entitled: (1) introduction to the market rules and administrative rules of general application, (2) market participation and the use of the SO-controlled grid, (3) market administration, (4) technical and connection requirements, testing and commissioning, (5) system reliability, (6) operational requirements, (7) settlement, (8) connection of new or modified facilities, (9) transmission system planning, investment and operation, and (10) definitions and interpretation

  10. Advisory panel on the proposed New Brunswick - Quebec electricity transaction

    International Nuclear Information System (INIS)

    NB Power was faced with major financial and technical challenges in generation that would lead to significant rate increases over several years to come. In 2009, the governments of New Brunswick and Quebec proposed an agreement whereby Hydro-Quebec would acquire most of the assets of NB Power and provide a guaranteed electricity supply at a set price to the province. The proposal involved the sale of NB Power's hydro generation facilities, 2 diesel peaking plants and the Point Lepreau nuclear generating facility. It also included a guaranteed bulk electricity supply of 14 Terawatt-hours per year by Hydro-Quebec at a blended rate of 7.35 cents per kilowatt-hour. The new Brunswick government would retain ownership of the fossil-fuelled power plants, the NB Power transmission assets and the NB Power distribution assets and customer sales. A 6-person independent panel was asked to examine the proposal. This report addresses the proposed agreement as presented to the Panel up to January 26, 2010. The panel conducted an independent and objective examination of the financial implications; long-term effects on electricity rates; New Brunswick's control of energy policies; environmental impacts; short-and long-term risks and avoided risks; and benefits and costs to the provincial economy. The Panel drew its conclusions and recommendations on the basis of available information. The Panel concluded that the benefits to New Brunswick contribute to real and positive value to New Brunswick over business as usual. tabs., figs.

  11. 78 FR 64207 - Application To Export Electric Energy; New Brunswick Energy Marketing Corporation (f/k/a New...

    Science.gov (United States)

    2013-10-28

    ... Generation Corporation, to transmit electric energy from the United States to Canada as a power marketer for... a power marketer in New Brunswick Province, Canada. The principal business of NBEMC, as directed...

  12. 76 FR 54261 - Carolina Power & Light; H.B. Robinson Steam Electric Plant, Unit No. 2; HBRSEP Independent Spent...

    Science.gov (United States)

    2011-08-31

    ... accordance with the NRC E-Filing rule (72 FR 49139, August 28, 2007). The E-Filing process requires... pursuant to 10 CFR 72.50 for Robinson ISFSI, along with Brunswick Steam and Electric Plant (BSEP), Units 1 and 2, BSEP Independent Spent Fuel Storage Installation, Shearon Harris Nuclear Power Plant, Unit...

  13. Brunswick Steam Electric Plant, Unit 2. Annual operating report, 1975

    International Nuclear Information System (INIS)

    Initial criticality occurred in March and start-up testing continued for most of the year. Information is presented concerning operations, shutdowns, maintenance, design changes, personnel radiation exposures, thermal transients, safety/relief valve malfunctions, condenser tube leaks, and recirculation pump seal failures

  14. Severe accident insights from the Brunswick IPE

    Energy Technology Data Exchange (ETDEWEB)

    Miller, G.L. (Carolina Power and Light Company, Raleigh, NC (United States))

    1993-01-01

    Insights gained from the development of the level-2 analysis for a Brunswick individual plant examination (IPE) have led to severe accident insights that take advantage of the unique design of the containment structure. The Brunswick steam electric plant (BSEP) consists of two General Electric BWR-4 boiling water reactors (BWRS) with Mark I containments. The containments are unique among BWR Mark I's because the construction of the drywell and torus is reinforced concrete with steel liners. The typical Mark I is a steel shell construction. Both units are rated at 2436 MW(thermal) and [approximately]760 MW(electric). The Brunswick IPE, representing both units, was submitted to the US Nuclear Regulatory Commission in August 1992 (Ref. 1). The estimated mean core damage frequency (CDF) for the level-1 IPE is 2.7 x 10[sup [minus]5]/yr. Station blackout accident sequences contribute 66% to the overall CDF. Transient initiated sequences that involve loss of decay heat removal contribute 30% to the overall CDF. Accident sequences involving anticipated transients without scram (3%), transients with loss of high-pressure injection (I%), loss-of-coolant accidents (LOCAs) (< 1 %), and interfacing LOCAs (< 1 %) constituted the remainder of the accident sequences, which were above the analytical truncation level of 1 X 10 [sup [minus]8]/yr.

  15. Cogeneration of steam and electric power

    International Nuclear Information System (INIS)

    This study is concerned with the production of ethanol from sugar cane itself and not from molasses, which, when blended with gasoline, reduces the import bill for gasoline. The bagasse obtained after juice extraction is used as a fuel for the process. Under this scheme, some extra steam economy can be made because alcohol production does not need as much steam as sugar production. The surplus bagasse can be used to generate additional electric power to be fed into the utility grid. This can be termed as the ethanol/cogeneration solution to the tough growing energy problem. A scheme for the processing of sugar cane in to ethanol, electrical energy and other by-product is also given in this article. (orig./A.B.)

  16. Steam-Electric Power-Plant-Cooling Handbook

    Energy Technology Data Exchange (ETDEWEB)

    Sonnichsen, J.C.; Carlson, H.A.; Charles, P.D.; Jacobson, L.D.; Tadlock, L.A.

    1982-02-01

    The Steam-Electric Power Plant Cooling Handbook provides summary data on steam-electric power plant capacity, generation and number of plants for each cooling means, by Electric Regions, Water Resource Regions and National Electric Reliability Council Areas. Water consumption by once-through cooling, cooling ponds and wet evaporative towers is discussed and a methodology for computation of water consumption is provided for a typical steam-electric plant which uses a wet evaporative tower or cooling pond for cooling.

  17. 76 FR 28481 - Carolina Power & Light Company; Brunswick Steam Electric Plant, Units 1 and 2; Environmental...

    Science.gov (United States)

    2011-05-17

    ... to public health and safety; (2) performing health physics or chemistry duties required as a member... Reading Room on the Internet at the NRC Web site: http://www.nrc.gov/reading-rm/adams.html . Persons...

  18. Brunswick Steam Electric Plant, Units 1 and 2. Annual operating report No. 3

    International Nuclear Information System (INIS)

    After a month-by-month summary of operations and maintenance activities, data are presented concerning modifications, procedure changes, and man-rem radiation doses. Appendices include information on the main generator outage, leak rate testing, refueling outage, recirculation pump modifications, and instrument drift

  19. Electric-arc steam plasma generator

    Science.gov (United States)

    Anshakov, A. S.; Urbakh, E. K.; Radko, S. I.; Urbakh, A. E.; Faleev, V. A.

    2015-01-01

    Investigation results on the arc plasmatorch for water-steam heating are presented. The construction arrangement of steam plasma generator with copper electrodes of the stepped geometry was firstly implemented. The energy characteristics of plasmatorch and erosion of electrodes reflect the features of their behavior at arc glow in the plasma-forming environment of steam. The results of numerical study of the thermal state of the composite copper-steel electrodes had a significant influence on optimization of anode water-cooling aimed at improvement of its operation life.

  20. LPGC, Levelized Steam Electric Power Generator Cost

    International Nuclear Information System (INIS)

    1 - Description of program or function: LPGC is a set of nine microcomputer programs for estimating power generation costs for large steam-electric power plants. These programs permit rapid evaluation using various sets of economic and technical ground rules. The levelized power generation costs calculated may be used to compare the relative economics of nuclear and coal-fired plants based on life-cycle costs. Cost calculations include capital investment cost, operation and maintenance cost, fuel cycle cost, decommissioning cost, and total levelized power generation cost. These programs can be used for quick analyses of power generation costs using alternative economic parameters, such as interest rate, escalation rate, inflation rate, plant lead times, capacity factor, fuel prices, etc. The two major types of electric generating plants considered are pressurized-water reactor (PWR) and pulverized coal-fired plants. Data are also provided for the Large Scale Prototype Breeder (LSPB) type liquid metal reactor. Costs for plant having either one or two units may be obtained. 2 - Method of solution: LPGC consists of nine individual menu-driven programs controlled by a driver program, MAINPWR. The individual programs are PLANTCAP, for calculating capital investment costs; NUCLOM, for determining operation and maintenance (O and M) costs for nuclear plants; COALOM, for computing O and M costs for coal-fired plants; NFUEL, for calculating levelized fuel costs for nuclear plants; COALCOST, for determining levelized fuel costs for coal-fired plants; FCRATE, for computing the fixed charge rate on the capital investment; LEVEL, for calculating levelized power generation costs; CAPITAL, for determining capitalized cost from overnight cost; and MASSGEN, for generating, deleting, or changing fuel cycle mass balance data for use with NFUEL. LPGC has three modes of operation. In the first, each individual code can be executed independently to determine one aspect of the total

  1. Cycle Configurations for a PBMR Steam and Electricity Production Plant

    International Nuclear Information System (INIS)

    The Pebble Bed Modular Reactor (PBMR) is an advanced helium-cooled, graphite moderated High Temperature Gas-cooled Reactor (HTGR) that is capable of multiple missions. The petrochemical industry requires the use of high temperature steam and electricity for their processes. Currently coal or natural gas is utilised for the generation of high temperature steam and electricity, which under-utilises natural resources and in the process emits CO2 into the atmosphere. This paper provides an overview of the PBMR product development path and discusses how steam production forms part of the future possibilities of the PBMR technology. Suitable cycle configurations for both process steam and electricity generation as required by petrochemical plants are discussed. (authors)

  2. Improvements in steam cycle electric power generating plants

    International Nuclear Information System (INIS)

    The invention relates to a steam cycle electric energy generating plants of the type comprising a fossil or nuclear fuel boiler for generating steam and a turbo alternator group, the turbine of which is fed by the boiler steam. The improvement is characterized in that use is made of a second energy generating group in which a fluid (e.g. ammoniac) undergoes a condensation cycle the heat source of said cycle being obtained through a direct or indirect heat exchange with a portion of the boiler generated steam whereby it is possible without overloading the turbo-alternator group, to accomodate any increase of the boiler power resulting from the use of another fuel while maintaining a maximum energy output. This can be applied to electric power stations

  3. Environmental codes of practice for steam electric power generation

    International Nuclear Information System (INIS)

    The Design Phase Code is one of a series of documents being developed for the steam electric power generation industry. This industry includes fossil-fuelled stations (gas, oil and coal-fired boilers), and nuclear-powered stations (CANDU heavy water reactors). In this document, environmental concerns associated with water-related and solid waste activities of steam electric plants are discussed. Design recommendations are presented that will minimize the detrimental environmental effects of once-through cooling water systems, of wastewaters discharged to surface waters and groundwaters, and of solid waste disposal sites. Recommendations are also presented for the design of water-related monitoring systems and programs. Cost estimates associated with the implementation of these recommendations are included. These technical guides for new or modified steam electric stations are the result to consultation with a federal-provincial-industry task force

  4. 1990 production costs operating steam-electric plants

    International Nuclear Information System (INIS)

    In 1990 U.S. electric utilities generated more than 2.8 billion net megawatt hours (MWhr) of electricity from all sources--a slight increase of 0.8% from the 1989 total of 2.78 billion MWhr, but substantially less than the 1989 increase of 2.8% over 1988. Steam-electric plants, which produce electricity by burning fossil fuels or by nuclear fission, typically generate 90% of all U.S. electricity. Utilization of the nation's fossil-fueled steam-electric power plants during 1990 was down about 2% from 1989, primarily because nuclear plant generation increased 9%. (Hydroelectric plant output was up 6% from 1989.) Nuclear power's 1990 contribution to total electric utility generation was up about 1% from 1989 to 20.5%. This paper includes specific 1990 production cost data for 798 steam-electric plants, of which 428 are fueled with coal or lignite, 284 are gas- and/or oil-fired, 73 are nuclear, 6 are geothermal, 4 are wood-fired, and 3 burn refuse or refuse-derived fuel (RDF)

  5. Extending steam generator life at maximum electrical power output

    International Nuclear Information System (INIS)

    This paper reports the results of a study performed to support the steam generator (SG) strategic planning activities of the Northeast Utilities' Connecticut Yankee (CY) nuclear power plant. The goal of the strategic plan is to enable Cy to operate to the end of its licensed life with the current steam generators in a safe, reliable, and economical manner. one element of the strategic plan involved evaluating Tave reductions for the purpose of reducing tube corrosion rates. The evaluation showed that while reducing Tave would provide corrosion relief, it would also result in unacceptable electrical power output losses. Encotech's Steam Turbine Diagnostic Program provided the plant performance estimates required to perform this evaluation. It was used to quantify electrical power output as a function of Tave turbine control valve (TCV) configuration, SC plugging level, and core thermal power level. In addition, this work lead to the reconfiguration of the turbine control valves, resulting in increased power output

  6. Evaluation of material integrity on electricity generator water steam cycles component (Main Steam Pipe)

    International Nuclear Information System (INIS)

    The evaluation of material integrity on electricity generator component has been done. That component was main steam pipe of Unit II Suralaya Coal Fired Power Plant. evaluation was done by replication technique. The damage was found are two porosity's, from two point samples of six points sample population. Based on cavity evaluation in steels, which proposed by Neubauer and Wedel that porosity's still at class A damage. For class A damage, its means no remedial action would be required until next major scheduled maintenance outage. That porosity's was grouped on isolated cavities and not need ti repair that main steam pipe component less than three year after replication test

  7. Aluminum-Enhanced Underwater Electrical Discharges for Steam Explosion Triggering

    International Nuclear Information System (INIS)

    For a number of years, we have been initiating steam explosions of single drops of molten materials with pressure and flow (bubble growth) transients generated by discharging a capacitor bank through gold bridgewires placed underwater. Recent experimental and theoretical advances in the field of steam explosions, however, have made it important to substantially increase these relatively mild transients in water without using high explosives, if possible. To do this with the same capacitor bank, we have discharged similar energies through tiny strips of aluminum foil submerged in water. By replacing the gold wires with the aluminum strips, we were able to add the energy of the aluminum-water combustion to that normally deposited electrically by the bridgewire explosion in water. The chemical enhancement of the explosive characteristics of the discharges was substantial: when the same electrical energies were discharged through the aluminum strips, peak pressures increased as much as 12-fold and maximum bubble volumes as much as 5-fold above those generated with the gold wires. For given weights of aluminum, the magnitudes of both parameters appeared to exceed those produced by the underwater explosion of equivalent weights of high explosives

  8. 77 FR 75674 - Susquehanna Steam Electric Station, Units 1 and 2, PPL Susquehanna, LLC, Exemption

    Science.gov (United States)

    2012-12-21

    ... COMMISSION Susquehanna Steam Electric Station, Units 1 and 2, PPL Susquehanna, LLC, Exemption 1.0 Background... and NPF-22, which authorizes operation of the Susquehanna Steam Electric Station (SSES), Units 1 and 2... unplanned Unit 1 outage necessary due to fatigue cracking experienced on the Unit 1 turbine blades...

  9. Nuclear power in New Brunswick

    International Nuclear Information System (INIS)

    New Brunswick's first nuclear power station was started in 1974, and construction of the major structures began in May 1975. The station is a 600 MW CANDU plant designed for salt water cooling and arranged to serve as the first of a two-unit station. It was the first nuclear plant in Canada to be subjected to the federal government requirements for environmental assessment, and the first in which design, construction and commissioning were carried out under a full quality assurance program to the CSA Z299 standard. The discovery of damage to the steam generators necessitated an extensive rebuild of these components and had a major impact on the construction schedule. Commissioning of the plant got under way in 1979, although construction continued during 1981. Point Lepreau is among the leaders in cost and schedule performance for all reactors being completed worldwide in 1982. Lessons learned during the construction of this reactor suggest that a unit of this type could be built in considerably less time and at a lower cost if a unified approach to engineering and procurement could be achieved

  10. Numerical simulation on coupling performance of steam flow field and electric field in capacitance sensor measuring steam wetness

    International Nuclear Information System (INIS)

    Based on the theory of dielectric polarization and hydrodynamics, using the FLUENT UDF code, the coupling performances of the steam flow field and the electric field in the capacitance sensor were numerically simulated. The standard k-ε model, wall function and SIMPLE way were used. The results show that the voltage decreases gradually from positive plate to negative plate, and the change is even; water molecule is polarized, the polarized charge appears near the plates, and there is no polarized charge in the center of sensor when the dry saturation steam flows through the capacitance sensor; the radial velocity is different from with and without electric field in the capacitance sensor, and the difference is max near the outmost plate; the electric field near the plate is smaller when there is no flow field. The results of numerical simulation match with the results of experiment. The numerical simulation model is feasibility. (authors)

  11. Asbestos exposure in a steam-electric generating plant

    Energy Technology Data Exchange (ETDEWEB)

    Scansetti, G.; Pira, E.; Botta, G.C.; Turbiglio, M.; Piolatto, G. (Turin Univ. (Italy). Inst. of Occupational Health)

    1993-12-01

    A study on asbestos risk in an old multi-fuel-fired steam-electric power station was carried out. In spite of the presence of large amounts of asbestos-containing materials (20 km of asbestos insulated pipes), the mean airborne concentration of asbestos was as low as 1.55 fibres 1.[sup -1](SD 2.05) under normal operating conditions. Much higher concentrations may obviously occur during maintenance or renovation operations. Man-made mineral fibres (MMMF) were detected only occasionally in some samples. Three non-consecutive sputum samples were collected for all the 521 workers included in the study: 3.1% had asbestos bodies (AB), but in no case were there more than four AB per gramme sputum. Small opacities, in most cases irregular of mixed type, were presented in 15 out of 470 radiograms of acceptable quality (3.2%). No AB were found in these cases. Pleural changes were less common: two out of five bilateral cases had AB in the sputum. It is concluded that repeated AB counts in the sputum turned out to be more useful than the search of pleural abnormalities by traditional postero-anterior (PA) view in detecting the signs of low asbestos exposure. (Author)

  12. New Brunswick Market Design Committee : final report

    International Nuclear Information System (INIS)

    This report presents a plan for implementing New Brunswick's electricity restructuring. It includes two resolutions and 95 recommendations to help achieve the main policy objectives of the White Paper, the New Brunswick Energy Policy. The most significant policy goal outlined in the White Paper is the restructuring of the electricity sector, with initial competition being only at the wholesale and large industrial retail level. The Board of Commissioners of Public Utilities will regulate many aspects of the new electricity market. In addition, green pricing options will be made available. The Market Design Committee recommends that the government set up a bilateral contract market for wholesale and large industrial customers to contract with alternate providers for electrical power. Power generators would have the freedom to sell by contract to customers both within and outside the province. The report describes the requirements for establishing a bilateral contract market and how it functions. The Committee also recommends designating a Heritage Pool of electricity available from the existing generation assets in the province. Other recommendations include the creation of programs that will help meet environmental protection goals. The programs include net metering, support of embedded generation, renewable portfolio standards, energy efficiency programs, green pricing, broad-based carbon dioxide emissions trading, emission performance standards, and the promotion of cogeneration. 37 refs., 2 figs

  13. Electrical Characteristics measurement of eddy current testing instrument for steam generator in NPP

    International Nuclear Information System (INIS)

    A steam generator in nuclear power plant is a heat exchager which is used to convert water into steam from heat produced in a nuclear reactor core, and the steam produced in steam generator is delivered to the turbine to generate electricity. Because of damage to steam generator tubing may impair its ability to adequately perform required safety functions in terms of both structural integrity and leakage integrity, eddy current testing is periodically performed to evaluate the integrity of tubes in steam generator. This assessment is normally performed during a reactor refueling outage. Currently, the eddy current testing for steam generator of nuclear power plant in Korea is performed in accordance with KEPIC and ASME Code requirements, the eddy current testing system is consists of remote data acquisition unit and data analysis program to evaluate the acquired data. The KEPIC and ASME Code require that the electrical properties of remote data acquisition unit, such as total harmonic distortion, input and output impedance, amplifier linearity and stability, phase linearity, bandwidth and demodulation filter response, analog-to-digital conversion, and channel crosstalk shall be measured in accordance with the KEPIC and ASME Code requirements. In this paper, the measurement requirements of electrical properties for eddy current testing instrument described in KEPIC and ASME Code are presented, and the measurement results of newly developed eddy current testing instrument by KHNP(Korea Hydro and Nuclear Power Co., LTD) are presented.

  14. Strategic elements of steam cycle chemistry control practices at TXU's Comanche Peak steam electric station

    International Nuclear Information System (INIS)

    Early industry experience defined the critical importance of Chemistry Control Practices to maintaining long-term performance of PWR steam generators. These lessons provided the impetus for a number of innovations and alternate practices at Comanche Peak. For example, advanced amine investigations and implementation of results provided record low iron transport and deposition. The benefits of the surface-active properties of dimethyl-amine exceeded initial expectations. Operation of pre-coat polishers and steam generator blowdown demineralizers in the amine cycle enabled optimization of amine concentrations and stable pH control. The strategy for coordinated control of oxygen and hydrazine dosing complemented the advanced amine program for protective oxide stabilization. Additionally, a proactive chemical cleaning was performed on Unit 1 to prevent degradations from general fouling of steam generator tube-tube support plate (TSP) and top-of-tubesheet (TTS) crevices. This paper shares the results of these innovations and practices. Also, the bases, theory, and philosophy supporting the strategic elements of program will be presented. (authors)

  15. Composite electric generator equipped with steam generator for heating reactor coolant

    International Nuclear Information System (INIS)

    The present invention concerns a composite electric generator having coolants, as a heating source, of a PWR type reactor or a thermonuclear reactor. An electric generator driving gas turbine is disposed, and a superheater using a high temperature exhaust gas of the gas turbine as a heating source is disposed, and main steams are superheated by the superheater to elevate the temperature at the inlet of the turbine. This can increase the electric generation capacity as well as increase the electric generation efficiency. In addition, since the humidity in the vicinity of the exit of the steam turbine is reduced, occurrence of loss and erosion can be suppressed. When cooling water of the thermonuclear reactor is used, the electric power generated by the electric generator driven by the gas turbine can be used upon start of the thermonuclear reactor, and it is not necessary to dispose a large scaled special power source in the vicinity, which is efficient. (N.H.)

  16. Recruiting, Training, Retaining, and Promoting the Workforce of the Future at Comanche Peak Steam Electric Station

    International Nuclear Information System (INIS)

    TXU Electric expects to encounter a relatively high turnover in the workforce in the coming years. To prepare for this challenge and to maintain a high level of performance, a number of approaches are being implemented. These approaches involve recruiting experienced personnel, recruiting and developing local nonexperienced personnel, and developing current employees. Through these approaches, TXU Electric expects to maintain a high-quality workforce for the continued support of Comanche Peak Steam Electric Station

  17. Technical and economic studies of small reactors for supply of electricity and steam

    International Nuclear Information System (INIS)

    Several years ago conventional opinion held that nuclear power plants must be very large to be competitive with fossil fuels. This situation has changed markedly in most countries within recent years, as oil and gas supplies have become more scarce and costly. Studies have been carried out for several nuclear steam supply systems in the small and intermediate size range. Detail studies are reported of the Consolidated Nuclear Steam Generator (CNSG), a 365 MW(th) pressurized water reactor being developed by Babcock and Wilcox, as applied to industrial energy needs. Both conventional and barge-mounted nuclear steam supply systems are considered. Conceptual studies have been started of pressurized and boiling water reactors in the range of 1000 MW(th), which are envisioned for utility operation for supply of electric power and steam. Design studies of a 500 MW(th) high temperature reactor are also reported. The small reactors are expected to have higher unit costs than the large commercial plants, but to have compensating advantages in higher plant availability, shorter construction schedule, and greater siting flexibility. Studies are also reported of power cycle parameters and cost allocations for extraction of steam from steam turbine plants. This steam could be used for industrial energy, district heating, or desalination

  18. Procedure for estimating nonfuel operation and maintenance costs for large steam-electric power plants

    International Nuclear Information System (INIS)

    Revised guidelines are presented for estimating annual nonfuel operation and maintenance costs for large steam-electric power plants, specifically light-water-reactor plants and coal-fired plants. Previous guidelines were published in October 1975 in ERDA 76-37, a Procedure for Estimating Nonfuel Operating and Maintenance Costs for Large Steam-Electric Power Plants. Estimates for coal-fired plants include the option of limestone slurry scrubbing for flue gas desulfurization. A computer program, OMCOST, is also presented which covers all plant options

  19. Integrated gasification and Cu-Cl cycle for trigeneration of hydrogen, steam and electricity

    Energy Technology Data Exchange (ETDEWEB)

    Aghahosseini, S.; Dincer, I.; Naterer, G.F. [University of Ontario, Oshawa, ON (Canada). Institute of Technology

    2011-02-15

    This paper develops and analyzes an integrated process model of an Integrated Gasification Combined Cycle (IGCC) and a thermochemical copper-chlorine (Cu-Cl) cycle for trigeneration of hydrogen, steam and electricity. The process model is developed with Aspen HYSYS software. By using oxygen instead of air for the gasification process, where oxygen is provided by the integrated Cu-Cl cycle, it is found that the hydrogen content of produced syngas increases by about 20%, due to improvement of the gasification combustion efficiency and reduction of syngas NOx emissions. Moreover, about 60% of external heat required for the integrated Cu-Cl cycle can be provided by the IGCC plant, with minor modifications of the steam cycle, and a slight decrease of IGCC overall efficiency. Integration of gasification and thermochemical hydrogen production can provide significant improvements in the overall hydrogen, steam and electricity output, when compared against the processes each operating separately and independently of each other.

  20. Synergetic mechanism of methanol–steam reforming reaction in a catalytic reactor with electric discharges

    International Nuclear Information System (INIS)

    Highlights: • Methanol–steam reforming was performed on Cu catalysts under an electric discharge. • Discharge had a synergetic effect on the catalytic reaction for methanol conversion. • Discharge lowered the temperature for catalyst activation or light off. • Discharge controlled the yield and selectivity of species in a reforming process. • Adsorption triggered by a discharge was a possible mechanism for a synergetic effect. - Abstract: Methanol–steam reforming was performed on Cu/ZnO/Al2O3 catalysts under an electric discharge. The discharge occurred between the electrodes where the catalysts were packed. The electric discharge was characterized by the discharge voltage and electric power to generate the discharge. The existence of a discharge had a synergetic effect on the catalytic reaction for methanol conversion. The electric discharge provided modified reaction paths resulting in a lower temperature for catalyst activation or light off. The discharge partially controlled the yield and selectivity of species in a reforming process. The aspect of control was examined in view of the reaction kinetics. The possible mechanisms for the synergetic effect between the catalytic reaction and electric discharge on methanol–steam reforming were addressed. A discrete reaction path, particularly adsorption triggered by an electric discharge, was suggested to be the most likely mechanism for the synergetic effect. These results are expected to provide a guide for understanding the plasma–catalyst hybrid reaction

  1. 78 FR 34431 - Effluent Limitations Guidelines and Standards for the Steam Electric Power Generating Point...

    Science.gov (United States)

    2013-06-07

    ... steam electric point source category on October 8, 1974 (39 FR 36186, as amended at 40 FR 7095, February... the development of BCT limitations in July 9, 1986 (51 FR 24974). Section 304(a)(4) designates the... grease as an additional conventional pollutant on July 30, 1979 (44 FR 44501; 40 CFR 401.16). 3....

  2. GRAPHICAL REPRESENTATIONS OF 1991 STEAM-ELECTRIC POWER PLANT OPERATION AND AIR EMISSIONS DATA

    Science.gov (United States)

    The report provides graphical representations of data derived from the U.S. Department of Energy's (DOE's) Energy Information Administration, s Form EIA-767 (Steam Electric Plant Operation and Design Report). or more than 10 years, EIA has collected monthly boiler level data from...

  3. Analysis of process steam demand reduction and electricity generation in sugar and ethanol production from sugarcane

    International Nuclear Information System (INIS)

    The sugarcane industry represents one of the most important economic activities in Brazil, producing sugar and ethanol for the internal and external markets. Moreover, thermal and electric energy is produced for self-consumption, using sugarcane bagasse as fuel in cogeneration plants. Almost all the sugarcane plants in Brazil are self-sufficient in terms of energy supply and in the last few years some of them have been selling their surplus electricity for the grid. The reduction of process steam requirements and the use of more efficient cogeneration systems are new alternatives to increase the surplus electricity generation. The purpose of this paper is to analyze the steam demand reduction on sugar and ethanol process and alternatives for cogeneration systems in sugarcane plants, aiming at the surplus electricity generation increase

  4. Automation of steam generator services at public service electric ampersand gas

    International Nuclear Information System (INIS)

    Public Service Electric ampersand 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 ampersand 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

  5. Mechanical problems in turbomachines, steam and gas turbines. Large steam turbine manufacturing requirements to fulfill customer needs for electric power

    International Nuclear Information System (INIS)

    The needs of the customers in large steam turbines for electric power are examined. The choices and decisions made by the utility about the equipments are dealt with after considering the evolution of power demand on the French network. These decisions and choices mainly result from a technical and economic optimization of production equipments: choice of field-proven solutions, trend to lower steam characteristics, trend to higher output of the units (i.e. size effect), spreading out standardization of machines and components (policy of technical as well as technological levels, i.e. mass production effect). Standardization of external characteristics of units of same level of output and even standardization of some main components. The requirements turbine manufacturers have to meet may fall in two categories: on one side: gaining experience and know-how, capability of making high quality experiments, out put capacity, will to hold a high efficiency level; on the other side: meeting the technical requirements related to the contracts. Among these requirements, one can differentiate those dealing with the service expected from the turbine and that resulting in the responsibility limits of the manufacturer and those tending to gain interchangeability, to improve availability of the equipment, to increase safety, and to make operation and maintenance easier

  6. CDIO – The steam engine powering the electric grid

    DEFF Research Database (Denmark)

    Træholt, Chresten; Holbøll, Joachim; Thomsen, Ole Cornelius;

    2011-01-01

    In building the new DTU B.Eng programme [1] one of the pilots on the 4’th semester is the Design-build project course in Electric Energy Systems. In this course, which is the last Designbuild course many of the CDIO Syllabus bullets [2] are addressed starting with problem identification and formu......-ons such as a solar panel or a cable connection to other similar systems and the acquisition of basic skills within electric power engineering....

  7. Draft environmental statement related to steam generator repair at H.B. Robinson Steam Electric Plant Unit No. 2, (Docket No. 50-261)

    International Nuclear Information System (INIS)

    The staff has considered the environmental impacts and economic costs of the proposed steam generator repair at the H.B. Robinson Steam Electric Plant Unit No. 2 along with reasonable alternatives to the proposed action. The staff has concluded that the proposed repair will not significantly affect the quality of the human environment and that there are no preferable alternatives to the proposed action. Furthermore, any impacts from the repair program are outweighted by its benefits

  8. Three Dimensional Visualization for the Steam Injection into Water Pool using Electrical Resistance Tomography

    International Nuclear Information System (INIS)

    The direct injection of steam into a water pool is a method of heat transfer used in many process industries. The amount of research in this area however is limited to the nuclear industry, with applications relating to reactor cooling systems. Electrical resistance tomography (ERT), a low cost, non-invasive and which has high temporal resolution characteristics, can be used as a visualization tool for the resistivity distribution for the steam injection into water pool such as IRWST. In this paper, three dimensional resistivity distribution of the process is obtained through ERT using iterative Gauss-Newton method. Numerical experiments are performed by assuming different resistive objects in the water pool. Numerical results show that ERT is successful in estimating the resistivity distribution for the injection of steam in the water pool

  9. System and method for coproduction of activated carbon and steam/electricity

    Science.gov (United States)

    Srinivasachar, Srivats; Benson, Steven; Crocker, Charlene; Mackenzie, Jill

    2011-07-19

    A system and method for producing activated carbon comprising carbonizing a solid carbonaceous material in a carbonization zone of an activated carbon production apparatus (ACPA) to yield a carbonized product and carbonization product gases, the carbonization zone comprising carbonaceous material inlet, char outlet and carbonization gas outlet; activating the carbonized product via activation with steam in an activation zone of the ACPA to yield activated carbon and activation product gases, the activation zone comprising activated carbon outlet, activation gas outlet, and activation steam inlet; and utilizing process gas comprising at least a portion of the carbonization product gases or a combustion product thereof; at least a portion of the activation product gases or a combustion product thereof; or a combination thereof in a solid fuel boiler system that burns a solid fuel boiler feed with air to produce boiler-produced steam and flue gas, the boiler upstream of an air heater within a steam/electricity generation plant, said boiler comprising a combustion zone, a boiler-produced steam outlet and at least one flue gas outlet.

  10. Reasons for decision in the matter of New Brunswick Power Transmission Corporation

    International Nuclear Information System (INIS)

    The New Brunswick Power Transmission Corporation applied to the National Energy Board (NEB) in May 2001 to construct an international power line (IPL) from the Point Lepreau terminal in New Brunswick to Woodland, Maine. The objective was to improve reliability, efficiency and market access of the regional electricity system. A comprehensive study report detailing the environmental effects of the project indicated that the project was not likely to create negative environmental effects. The application was approved in May 2003 and a certificate EC-III-25 was issued in August 2003 approving the construction, operation and route of the international power line. However, due to changes taking place in New Brunswick's electric power industry, an amending order for certificate EC-III-25 was issued in October 2004 assigning the certificate from New Brunswick Power Corporation to New Brunswick Power Transmission Corporation (NB Power). The IPL consists of a 1 km wide and 95.5 km long corridor for a 345 kV transmission line from the Point Lepreau Peninsula, through Saint John and Charlotte counties New Brunswick to Woodland, Maine on the international border between Canada and the United States. This document included detailed route hearing issues, detailed route selection criteria, detailed route selection process, landowner objections, and a description of an alternate route. The views of the applicant, interveners and the NEB were expressed. In its final decision, the NEB found the detailed route proposed by NB Power to be the best possible route for the power line. 1 tab., 3 figs

  11. Draft environmental impact statement for construction and operation of the proposed Bangor Hydro-Electric Company`s second 345-kV transmission tie line to New Brunswick

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-10-01

    This Draft Environmental Impact Statement (DEIS) was prepared by the US Department of Energy (US DOE). The proposed action is the issuance of Presidential Permit PP-89 by DOE to Bangor Hydro-Electric Company to construct and operate a new international transmission line interconnection to New Brunswick, Canada that would consist of an 83.8 mile (US portion), 345-kilovolt (kV) alternating current transmission line from the US-Canadian border at Baileyville, Maine to an existing substation at Orrington, Maine. The principal environmental impacts of the construction and operation of the transmission line would be incremental in nature and would include the conversion of forested uplands (mostly commercial timberlands) and wetlands to right-of-way (small trees, shrubs, and herbaceous vegetation). The proposed line would also result in localized minor to moderate visual impacts and would contribute a minor incremental increase in the exposure of some individuals to electromagnetic fields. This DEIS documents the purpose and need for the proposed action, describes the proposed action and alternatives considered and provides a comparison of the proposed and alternatives routes, and provides detailed information on analyses of the environmental consequences of the proposed action and alternatives, as well as mitigative measures to minimize impacts.

  12. Fatigue damage of steam turbine shaft at asynchronous connections of turbine generator to electrical network

    Science.gov (United States)

    Bovsunovsky, A. P.

    2015-07-01

    The investigations of cracks growth in the fractured turbine rotors point out at theirs fatigue nature. The main reason of turbine shafts fatigue damage is theirs periodical startups which are typical for steam turbines. Each startup of a turbine is accompanied by the connection of turbine generator to electrical network. During the connection because of the phase shift between the vector of electromotive force of turbine generator and the vector of supply-line voltage the short-term but powerful reactive shaft torque arises. This torque causes torsional vibrations and fatigue damage of turbine shafts of different intensity. Based on the 3D finite element model of turbine shaft of the steam turbine K-200-130 and the mechanical properties of rotor steel there was estimated the fatigue damage of the shaft at its torsional vibrations arising as a result of connection of turbine generator to electric network.

  13. Technical Specifications, Comanche Peak Steam Electric Station, Unit 1 (Docket No. 50-445)

    International Nuclear Information System (INIS)

    The Technical Specifications for Comanche Peak Steam Electric Station, Unit 1 were prepared by the US Nuclear Regulatory Commission. They set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility, as set forth in Section 50.36 of Title 10 of the Code of Federal Regulations Part 50, for the protection of the health and safety of the public

  14. The effects of steam injection on the electrical conductivity of an unconsolidated sand saturated with a salt solution

    International Nuclear Information System (INIS)

    The spatial and temporal variation of electrical conductivity in saturated sands during steam injection has been measured and modeled. Experiments consisted of introducing steam into one end of a tube filled with sand saturated with a slightly saline solution. A steam condensation front formed, separating the mixed-phase steam zone from the liquid zone. Measurements of electrical conductivity were made at 10 locations along the tube using a four-electrode technique. Results show that conductivity starts at a constant value, decreases before the steam front arrives and then, immediately prior to the steam front arrival, goes through a maximum before dropping by a factor of about 25. These variations can be explained by first, a dilution of the interstitial solution causing the initial drop in conductivity; second, an increase in temperature of the solution immediately prior to the arrival of the steam front causing the conductivity maximum; and finally, the large drop in conductivity due to the combined effects of a decrease in saturation and dilution of the residual liquid in the two-phase zone. Mathematical solutions of a set of differential equations that take into consideration all of these effects are presented. These solutions reproduce the significant features of the conductivity data. This study suggests that the measurement of changes in the subsurface conductivity field during steam injection operations may indicate the location of ionic concentration, temperature, and steam saturation fields. 28 refs., 7 figs., 1 tab

  15. Safety evaluation report related to steam generator repair at H.B. Robinson Steam Electric Plant, Unit No. 2. Docket No. 50-261

    International Nuclear Information System (INIS)

    A Safety Evaluation Report was prepared for the H.B. Robinson Steam Electric Plant Unit No. 2 by the Office of Nuclear Reactor Regulation. This report considers the safety aspects of the proposed steam generator repair at H.B. Robinson Steam Electric Plant Unit No. 2. The report focuses on the occupational radiation exposure associated with the proposed repair program. It concludes that there is reasonable assurance that the health and safety on the public will not be endangered by the conduct of the proposed action, such activities will be conducted in compliance with the Commission's regulations, and the issuance of this amendment will not be inimical to the common defense and security or the health and safety of the public

  16. Nuclear power in New Brunswick

    International Nuclear Information System (INIS)

    New Brunswick Power is a medium-utility with gross production for the past fiscal year for domestic and external sales of about 16.5 billion kilowatt hours. Of this figure 33.5% was supplied through nuclear generation. The financial risks involved with the production of the Point Lepreau nuclear generating station were discussed. Further, questions of assurances given for schedule and cost, licencing, and long-term plant performance of the Point Lepreau no. 2 unit were addressed. These were discussed with particular emphasis on the competition for the New England market

  17. Application of steam injection and electrical heating for enhanced in situ soil and ground water treatment

    International Nuclear Information System (INIS)

    The acceleration of recovery rates of second phase liquid contaminants from the subsurface during gas or water pumping operations is realized by an increase in soil temperature. Of the various methods of delivery of thermal energy to soils and ground water, steam injection appears to be the most economical and versatile technique for soils with sufficient permeability. The use of steam injection to recovery volatile semivolatile, and nonvolatile contaminants from the sub-surface also allows the exploitation of various thermodynamic and hydrodynamic mechanisms. These mechanisms include vaporization of liquids with boiling points below that of water, enhanced evaporation rates of semivolatile components, physical displacement of low viscosity liquids, dilution and displacement of aqueous contaminants, and removal of residual contaminants from low permeability zones by depressurization and vacuum drying. Electrical heating provides a means of preferentially heating the low permeability zones. A recently completed field-scale demonstration of the patented combined steam injection and electrical heating enhanced extraction technology (Dynamic Underground Stripping) to remove gasoline at a site at Lawrence Livermore National Laboratory confirms the effectiveness of this technique and its applicability to contaminants found above and below the water table

  18. Regulator of a plant for joint production of electrical energy and steam

    Energy Technology Data Exchange (ETDEWEB)

    Granelli, G.P. (Pavia Univ. (IT). Ist. di Elettrotecnica); Montagna, M.; Salomone, R.; Sarti, E.; Silvestri, A.

    1986-03-01

    The paper shows the new design of a regulation system for joint production of electrical power and steam for technological use. The regulation concerns both with steam pressure and electrical frequency, as the plant (although connectable with the Italian network) runs normally stand-alone. The design was developed on a linearized model for small variations around a normal operating state and, as for the nonlinear characteristics of turbine valves, around a maximum gain condition. The controller now in use carries out the decoupling between pressure and frequency regulation unsatisfactorily: in particular, the latter one causes unacceptable frequency steady state error both for electrical and thermal load changes. The new design aims to avoid such effects: this is done by adding an integrating term to the frequency regulator, and resetting the propotional gain of the actual amplifiers, as to decouple the pressure and frequency feedbach loops. Parameters are set up, too, for pole assignment of the decoupled subsystems. The improvement of control response has been tested by computer simulation, even in conditions different from the design's.

  19. A comparison of two thermal recovery methods for heavy oil reservoirs : steam flood and electric resistive heating

    Energy Technology Data Exchange (ETDEWEB)

    Barillas, J.L. [Federal Univ. of Rio Grande do Norte, Natal (Brazil). Dept. of Petroleum Engineering; Oliveira, H.J.; Rodrigues, M.A. [Federal Univ. of Rio Grande do Norte, Natal (Brazil). Post Graduation Program in Petroleum Engineering Science; Mata, W. [Federal Univ. of Rio Grande do Norte, Natal (Brazil). Dept. of Electrical Engineering; Dutra, T.V. [Federal Univ. of Rio Grande do Norte, Natal (Brazil). Dept. of Chemical Engineering

    2009-07-01

    This paper discussed electromagnetic resistive heating (ERH) processes for reducing oil viscosity in heavy oil reservoirs. The method applied electrical currents through the formation in order to increase temperature by Joule effect. The process was modelled using the characteristics of a heavy oil reservoir in Brazil in order to compare results obtained with steam injection processes. Net cumulative oil rates were used to compare the 2 technologies. The results of the study showed that EHR can be used to obtain high cumulative oil rates, while steam flooding increases oil rates after a period of several years due to oil bank displacements. The profitability of both technologies depends on energy, steam, and oil prices. It was concluded that electrical resistive heating results in lower water production rates when compared with steam flood processes. 5 refs., 9 tabs., 11 figs.

  20. Natural gas for New Brunswick: First report

    International Nuclear Information System (INIS)

    The development of the gas field off Sable Island and the imminent construction of a gas pipeline which will deliver natural gas to New Brunswick has prompted a thorough examination of energy-related issues in the province. This report presents the findings of the provincial energy committee which examined the implications of the arrival of natural gas to the province. The committee held a series of public hearings and consultations, and also received written submissions. After a historical perspective on natural gas as an energy source in the province and a review of the gas industry participants and their interests, the report discusses such issues as gas pipeline economics, local distribution company operations, infrastructure development, the regulatory framework, energy market competition, regional price equity, development of in-province gas sources, pipeline access, pipeline laterals and expansions, establishment of gas distribution franchises, municipal involvement in gas development, the impact of gas industry development on electric utility restructuring, and the environmental benefits of natural gas. Finally, recommendations are made regarding how natural gas should be regulated and distributed

  1. Toxicity of sediments and pore water from Brunswick Estuary, GA

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — A chlor-alkali plant in Brunswick, Ga, discharged >2 kg mercury/day into a tributary of the Turtle River-Brunswick Estuary from 1966 to 1971. Mercury...

  2. Elevated-constant pH control assessment at TXU's Comanche peak steam electric station

    International Nuclear Information System (INIS)

    Industry experience with axial offset anomaly (AOA) has raised the importance of crud management strategies. Elevated-constant pH control is recognized as one potential solution. Additionally, minimizing radiation fields remains a high industry goal which is supported by this strategy. An investigation of industry experience and experimental data has supported a strategy of constant at-temperature pH of 7.4, requiring as much as 6-ppm lithium at the beginning-of-cycle (BOC). This approach, in a modern high temperature plant with high boron requirements, necessitated a careful assessment of potential risk for increased susceptibility to corrosion for both fuel cladding and RCS structural materials. This paper presents results of the assessment for Comanche peak steam electric station (CPSES) and plans for a demonstration of this practice. (author)

  3. Effects of electric current upon catalytic steam reforming of biomass gasification tar model compounds to syngas

    International Nuclear Information System (INIS)

    Highlights: • ECR technique was proposed to convert biomass gasification tar model compounds. • Electric current enhanced the reforming efficiency remarkably. • The highest toluene conversion reached 99.9%. • Ni–CeO2/γ-Al2O3 exhibited good stability during the ECR performance. - Abstract: Electrochemical catalytic reforming (ECR) technique, known as electric current enhanced catalytic reforming technique, was proposed to convert the biomass gasification tar into syngas. In this study, Ni–CeO2/γ-Al2O3 catalyst was prepared, and toluene was employed as the major feedstock for ECR experiments using a fixed-bed lab-scale setup where thermal electrons could be generated and provided to the catalyst. Several factors, including the electric current intensity, reaction temperature and steam/carbon (S/C) ratio, were investigated to reveal their effects on the conversion of toluene as well as the composition of the gas products. Moreover, toluene, two other tar model compounds (benzene and 1-methylnaphthalene) and real tar (tar-containing wastewater) were subjected to the long period catalytic stability tests. All the used catalysts were analyzed to determine their carbon contents. The results indicated that the presence of electric current enhanced the catalytic performance remarkably. The toluene conversion reached 99.9% under the electric current of 4 A, catalytic temperature of 800 °C and S/C ratio of 3. Stable conversion performances of benzene, 1-methylnaphthalene and tar-containing wastewater were also observed in the ECR process. H2 and CO were the major gas products, while CO2 and CH4 were the minor ones. Due to the promising capability, the ECR technique deserves further investigation and application for efficient tar conversion

  4. Evaluation of a sulfur oxide chemical heat storage process for a steam solar electric plant

    Energy Technology Data Exchange (ETDEWEB)

    Dayan, J.; Lynn, S.; Foss, A.

    1979-07-01

    The purpose of this study was to develop and evaluate technically feasible process configurations for the use of the sulfur oxide system, 2 SO/sub 3/ reversible 2 SO/sub 2/ + O/sub 2/, in energy storage. The storage system is coupled with a conventional steam-cycle power plant. Heat for both the power plant and the storage system is supplied during sunlit hours by a field of heliostats focussed on a central solar receiver. When sunlight is not available, the storage system supplies the heat to operate the power plant. A technically feasible, relatively efficient configuration is proposed for incorporating this type of energy storage system into a solar power plant. Complete material and energy balances are presented for a base case that represents a middle range of expected operating conditions. Equipment sizes and costs were estimated for the base case to obtain an approximate value for the cost of the electricity that would be produced from such an installation. In addition, the sensitivity of the efficiency of the system to variations in design and operating conditions was determined for the most important parameters and design details. In the base case the solar tower receives heat at a net rate of 230 MW(t) for a period of eight hours. Daytime electricity is about 30 MW(e). Nighttime generation is at a rate of about 15 MW(e) for a period of sixteen hours. The overall efficiency of converting heat into electricity is about 26%. The total capital cost for the base case is estimated at about $68 million, of which about 67% is for the tower and heliostats, 11% is for the daytime power plant, and 22% is for the storage system. The average cost of the electricity produced for the base case is estimated to be about 11 cents/kW(e)-hr.

  5. Cutaneous blastomycosis in New Brunswick: case report

    OpenAIRE

    Ross, John J.; Keeling, Douglas N.

    2000-01-01

    Blastomycosis is a fungal infection of immunocompetent hosts. We present a case of cutaneous blastomycosis acquired in New Brunswick, which provides evidence that this disease is endemic in Atlantic Canada. This case also demonstrates that the diagnosis of blastomycosis may be elusive. Perseverance, a high index of clinical suspicion and close cooperation with the microbiology laboratory may be required to diagnose this uncommon condition.

  6. Assessment of the once-through cooling alternative for central steam-electric generating stations

    International Nuclear Information System (INIS)

    The efficacy of the disposal of waste heat from steam-electric power generation by means of once-through cooling systems was examined in the context of the physical aspects of water quality standards and guidelines for thermal discharges. Typical thermal standards for each of the four classes of water bodies (rivers, lakes, estuaries, and coastal waters) were identified. The mixing and dilution characteristics of various discharge modes ranging from simple, shoreline surface discharges to long, submerged multiport diffusers were examined in terms of the results of prototype measurements, analytical model predictions, and physical model studies. General guidelines were produced that indicate, for a given plant capacity, a given type of receiving water body, and a given discharge mode, the likelihood that once-through cooling can be effected within the restrictions of typical thermal standards. In general, it was found that shoreline surface discharges would not be adequate for large power plants (greater than or equal to 500 MW) at estuarine and marine coastal sites, would be marginally adequate at lake sites, and would be acceptable only at river sites with large currents and river discharges. Submerged multiport diffusers were found to provide the greatest likelihood of meeting thermal standards in all receiving water environments

  7. RETRAN analysis of Susquehanna Steam Electric Station Unit 2 moisture separator drain tank level transient response

    International Nuclear Information System (INIS)

    Susquehanna Steam Electric Station Unit 2 (SSES-2) experienced three main turbine trips on high moisture separator drain tank level during initial startup testing in 1984. The SSES-2, a 3293-MW (thermal) boiling water reactor-4 with Mark II containment, uses two parallel nonreheating moisture separators between the high- and low-pressure turbine stages. Two of the main turbine trips and subsequent scrams occurred due to the high level in the ''B'' moisture separator drain tank during combined intermediate valve testing. The third trip was also initiated on the same signal, but during a recirculation pump runback event. A task group was created to determine the cause of the level excursions and to make recommendations to reduce the severity of these transients. The RETRAN-02 computer code was used to evaluate the dynamic response of both the A and B moisture separator drain systems to determine the cause of the events, including why the level excursions only occurred in the B system. RETRAN was also used to evaluate the systems' dynamic response to several proposed corrective plant modifications. Based on the recommendations of the task group, modifications were made to SSES-2 during the precommercial operation outage. Startup testing following the outage proved the success of the modifications

  8. Performance of a direct steam generation solar thermal power plant for electricity production as a function of the solar multiple

    OpenAIRE

    Montes Pita, María José; Abánades Velasco, Alberto; Martínez-Val Peñalosa, Jose Maria

    2009-01-01

    This paper describes the influence of the solar multiple on the annual performance of parabolic trough solar thermal power plants with direct steam generation (DSG). The reference system selected is a 50 M We DSG power plant, with thermal storage and auxiliary natural gas-fired boiler. It is considered that both systems are necessary for an optimum coupling to the electricity grid. Although thermal storage is an opening issue for DSG technology, it gives an additional degree of freedom for pl...

  9. Second nuclear reactor, Point Lepreau, New Brunswick

    International Nuclear Information System (INIS)

    This is a report of the findings, conclusions and recommendations of the Environmental Assessment Panel appointed by the Ministers of Environment of New Brunswick and Canada to review the proposal to build a seond nuclear unit at Point Lepreau, New Brunswick. The Panel's mandate was to assess the environmental and related social impacts of the proposal. The Panel concludes that the project can proceed without significant adverse effects provided certain recommendations are followed. In order to understand the impacts of Lepreau II, it was necessary to review, to the extent possible, the actual effects of Lepreau I before estimating the incremental effects of Lepreau II. In so doing, the Panel made a number of recommendations that should be implemented now. The information gathered and experience gained can be applied to Lepreau II to ensure that potential impacts are reduced to a minimum and existing concerns associated with Lepreau I can be corrected

  10. Volume reduction of filter media at Susquehanna steam and electric station

    International Nuclear Information System (INIS)

    This paper describes the joint efforts between Pennsylvania Power ampersand Light (PPQL) and Scientific Ecology Group, Inc. (SEG) to reduce the volume of waste shipped to the burial site by the Susquehanna Steam and Electric Station (SSES) and the resulting savings realized as a result. The filter media used at SSES for its radwaste filters is composed of a mix of anion and cation powered resins, powered carbon, diatomaceous earth and a fibrous overlay. Due to the nature of this waste stream, dewatering was difficult using systems previously available in the industry. Thus, processing was accomplished by decanting (to concentrate the waste) and solidification. In the continuing effort to dewater wastes of this nature, SEG developed a new fabric filter dewatering system (RDU). To investigate its potential use in large containers, this dewatering system was installed in drum-size high integrity containers and used to test its dewatering capabilities on actual SSES waste. Promising results from these tests warranted a full-scale test. This proved successful and implementation of this processing scheme was immediate. Cost savings were substantial in transportation, burial and processing costs as well as personnel exposure. Also, additional waste volume reduction was found due to the volume reduction capability of the dewatering system (equivalent volume of new filter media approximately 1.2 times that of dewatered product volume). Additional savings resulted from SSES's continuing effort to minimize radwaste generation. Combined, these have reduced the number of shipments of filter media in 1989 to sixty percent of the number made in 1988 and have reduced costs by approximately fifty percent. 4 figs., 1 tab

  11. Impact of a 1,000-foot thermal mixing zone on the steam electric power industry

    International Nuclear Information System (INIS)

    Thermal discharge requirements for power plants using once-through cooling systems are based on state water quality standards for temperatures that must be met outside of designated mixing zones. This study evaluates the impact of limiting the extent of thermal mixing zones. This study evaluates the impact of limiting the extent of thermal mixing zones to no more than 1,000 feet from the discharge point. Data were collected from 79 steam electric plants. Of the plants currently using once-through cooling systems, 74% could not meet current thermal standards at the edge of a 1,000-foot mixing zone. Of this total, 68% would retrofit cooling towers, and 6% would retrofit diffusers. The estimated nationwide capital cost for retrofitting plants that could not meet current thermal standards at the edge of a 1,000-foot mixing zone is $21.4 billion. Conversion of a plant from once-through cooling to cooling towers or addition of diffusers would result in a lower energy output from that plant. For the affected plants, the total estimated replacement cost would be $370 to $590 million per year. Some power companies would have to construct new generating capacity to meet the increased energy demand. The estimated nationwide cost of this additional capacity would be $1.2 to $4.8 billion. In addition to the direct costs associated with compliance with a 1,000-foot mixing zone limit, other secondary environmental impacts would also occur. Generation of the additional power needed would increase carbon dioxide emissions by an estimated 8.3 million tons per year. In addition, conversion from once-through cooling systems to cooling towers at affected plants would result in increased evaporation of about 2.7 million gallons of water per minute nationwide

  12. Scram reduction at the Brunswick nuclear project

    International Nuclear Information System (INIS)

    Achieving the Nuclear Management and Resources Council goal of no more than 1.5 scrams per plant year by 1990 promises to be a formidable challenge for domestic utilities. However, after experiencing a less-than-desirable scram frequency in its early years of operation, the two-unit Brunswick plant began a scram reduction program that has contributed to early accomplishment of that goal. To accomplish this significant reduction in scram frequency, Brunswick found that three steps are essential: (1) determine root cause(s) of events, learn from past plant experiences, and (3) learn from other plant's experiences. In 1988, the Boiling Water Reactor Owners' Group's Scram Frequency Reduction Committee (SFRC) developed its own data-base software for BWR scrams. The data base is updated following the quarterly operations activity meetings and is distributed to each participating member of the SFRC. Thus, each plant has the ability to perform its own studies using a complete BWR scram data base. Each of the above actions has aided the Brunswick plant in significantly reducing its number of scrams

  13. Small and medium-sized high-temperature reactors for generation of electricity, process steam and district heat

    International Nuclear Information System (INIS)

    The HTR reactor line of BBC/HRB has been designed to cover the requirements in the market of nuclear power energy of the time being and in the future. Cornerstones of the group's future HTR line are the HTR 500 (550 MWe) and the HTR 100 (100 MWe) for the generation of electricity and process steam, with the possibility of heat extraction for district heating. The HTR 500 design characteristics, reasons for choice of a 500 MW design, economics of the HTR 500, the HTR 100 design characteristics, process heat application, and small heating reactors are discussed in the paper

  14. Study of the European market for industrial nuclear power plants for the mixed production of electricity and steam

    International Nuclear Information System (INIS)

    The opportunity of developing the mixed production of electricity and steam from nuclear power plants in the nine countries of the European Community is studied. Both public distribution and autonomous production are envisaged. An attempt is made to estimate the potentiel market for district heating and for chemical, agricultural and alimentary, textile, paper, car manufacture and wood industries. The reactors considered are LWR reactors of at least 1000MWth. Suggestions are given to overcome the difficulties and constraints that stand in the way of a nuclear solution

  15. The 15 kW sub e (nominal) solar thermal electric power conversion concept definition study: Steam Rankine turbine system

    Science.gov (United States)

    Bland, T. J.

    1979-01-01

    A study to define the performance and cost characteristics of a solar powered, steam Rankine turbine system located at the focal point of a solar concentrator is presented. A two stage re-entry turbine with reheat between stages, which has an efficiency of 27% at a turbine inlet temperature of 732 C was used. System efficiency was defined as 60 Hertz electrical output divided by absorbed thermal input in the working fluid. Mass production costs were found to be approximately 364 dollars/KW.

  16. 76 FR 62298 - Special Local Regulations; Line of Sail Marine Parade, East River and Brunswick River, Brunswick, GA

    Science.gov (United States)

    2011-10-07

    ..., East River and Brunswick River, Brunswick, GA AGENCY: Coast Guard, DHS. ACTION: Temporary final rule... special local regulations consist of a series of moving buffer zones around participant vessels as they... within any of the buffer zones unless authorized by the Captain of the Port Savannah or a...

  17. An autonomous nuclear power plant with integrated nuclear steam supply system designed for electric power and heat supply in remote areas with difficult access

    International Nuclear Information System (INIS)

    The paper contains basic conceptual principles used to develop the technical assignment for an autonomous nuclear power plant with integrated nuclear steam supply system (NSSS) designed to provide heat and electricity for areas which are remote with difficult access. The paper also describes technical procedures and equipment, NPP thermal hydraulic flow chart, steam generator design, safety aspects as well as operational and maintenance procedures. (author)

  18. Impact on the steam electric power industry of deleting Section 316(a) of the Clean Water Act: Capital costs

    International Nuclear Information System (INIS)

    Many power plants discharge large volumes of cooling water. In some cases, the temperature of the discharge exceeds state thermal requirements. Section 316(a) of the Clean Water Act (CWA) allows a thermal discharger to demonstrate that less stringent thermal effluent limitations would still protect aquatic life. About 32% of total US steam electric generating capacity operates under Section 316(a) variances. In 1991, the US Senate proposed legislation that would delete Section 316(a) from the CWA. This study, presented in two companion reports, examines how this legislation would affect the steam electric power industry. This report describes alternatives available to nuclear and coal-fired plants currently operating under variances. Data from 38 plants representing 14 companies are used to estimate the national cost of implementing such alternatives. Although there are other alternatives, most affected plants would be retrofitted with cooling towers. Assuming that all plants currently operating under variances would install cooling towers, the national capital cost estimate for these retrofits ranges from $22.7 billion to $24.4 billion (in 1992 dollars). The second report quantitatively and qualitatively evaluates the energy and environmental impacts of deleting the variance. Little justification has been found for removing the Section 316(a) variance from the CWA

  19. Impact of drought on U.S. steam electric power plant cooling water intakes and related water resource management issues.

    Energy Technology Data Exchange (ETDEWEB)

    Kimmell, T. A.; Veil, J. A.; Environmental Science Division

    2009-04-03

    This report was funded by the U.S. Department of Energy's (DOE's) National Energy Technology Laboratory (NETL) Existing Plants Research Program, which has an energy-water research effort that focuses on water use at power plants. This study complements their overall research effort by evaluating water availability at power plants under drought conditions. While there are a number of competing demands on water uses, particularly during drought conditions, this report focuses solely on impacts to the U.S. steam electric power plant fleet. Included are both fossil-fuel and nuclear power plants. One plant examined also uses biomass as a fuel. The purpose of this project is to estimate the impact on generation capacity of a drop in water level at U.S. steam electric power plants due to climatic or other conditions. While, as indicated above, the temperature of the water can impact decisions to halt or curtail power plant operations, this report specifically examines impacts as a result of a drop in water levels below power plant submerged cooling water intakes. Impacts due to the combined effects of excessive temperatures of the returned cooling water and elevated temperatures of receiving waters (due to high ambient temperatures associated with drought) may be examined in a subsequent study. For this study, the sources of cooling water used by the U.S. steam electric power plant fleet were examined. This effort entailed development of a database of power plants and cooling water intake locations and depths for those plants that use surface water as a source of cooling water. Development of the database and its general characteristics are described in Chapter 2 of this report. Examination of the database gives an indication of how low water levels can drop before cooling water intakes cease to function. Water level drops are evaluated against a number of different power plant characteristics, such as the nature of the water source (river vs. lake or reservoir

  20. New Coleoptera records from New Brunswick, Canada: Tenebrionidae and Zopheridae

    Directory of Open Access Journals (Sweden)

    Reginald Webster

    2012-04-01

    Full Text Available Thirteen species of Tenebrionidae are newly reported for New Brunswick, Canada. Paratenetus punctatus Spinola, Pseudocistela brevis (Say, Mycetochara foveata (LeConte, and Xylopinus aenescens LeConte are recorded for the first time from the Maritime provinces. Platydema excavatum (Say is removed from the faunal list of New Brunswick, and the presence of Platydema americanum Laporte and Brullé for the province is confirmed. This brings the total number of species of Tenebrionidae known from New Brunswick to 42. Two species of Zopheridae, Bitoma crenata Fabricius and Synchita fuliginosa Melsheimer, are newly recorded for New Brunswick, bringing the number of species known from the province to four. Bitoma crenata is new to the Maritime provinces. Collection and habitat data are presented for these species.

  1. Improving maintenance at CP and L's Brunswick

    International Nuclear Information System (INIS)

    Improvements in Carolina Power and Light Company's Brunswick nuclear station included the reorganization of the maintenance unit into separate line groups and centralized staff providing technical and administrative support. The results have been improved plant performance and unit reliability, with recognition from the nuclear Regulatory Commission. The maintenance Improvement Program (MIP) began in early 1980 with a focus on maintenance errors and grass-roots input. The program sought to establish a maintenance mission, optimize human resources, compare performance with the industry as a whole, establish and maintain an employee-oriented work environment, and establish effective management programs to sustain the organization. The author describes the MIP, personnel training, computer and other tools, reporting, and other aspects. 2 figures

  2. New Brunswick Power business and operations update

    International Nuclear Information System (INIS)

    The final paper will present the operating performance and address the high level issues pertaining to NB Power as a corporation. In particular, the impact of the legislation for the restructuring of NB Power and it's impact on the operation of the proposed NB Power Nuclear Corporation will be discussed along with the status of external investment solicitation in the station and the Point Lepreau refurbishment project. A review of the operational performance of Point Lepreau last fiscal year will be presented along with the key focus areas and performance objectives for the current fiscal year (refer to the Appendix). Lastly, the key items that are considered necessary to have a healthy viable nuclear industry in New Brunswick will be discussed. (author)

  3. New Brunswick Laboratory progress report, October 1992--September 1993

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The mission of the New Brunswick Laboratory of the US Department of Energy (DOE) is to provide and maintain a nuclear material measurements and standards laboratory as a technical response to DOE`s statutory responsibility to assure the safeguarding of nuclear materials. This report summarizes the mission-fulfilling activities of the New Brunswick Laboratory for the period of October 1992 through September 1993.

  4. New Coleoptera records from New Brunswick, Canada: Histeridae

    Directory of Open Access Journals (Sweden)

    Reginald Webster

    2012-04-01

    Full Text Available Eighteen species of Histeridae are newly reported from New Brunswick, Canada. This brings the total number of species known from New Brunswick to 42. Seven of these species, Acritus exguus (Erichson, Euspilotus rossi (Wenzel, Hypocaccus fitchi (Marseul, Dendrophilus kiteleyi Bousquet and Laplante, Platysoma cylindricum (Paykull, Atholus sedecimstriatus (Say, and Margarinotus harrisii (Kirby are recorded from the Maritime provinces for the first time. Collection and bionomic data are presented for these species.

  5. Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Unit 2 (Docket No. 50-446)

    International Nuclear Information System (INIS)

    Supplement 26 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Unit 2, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement reports the status of certain issues that had not been resolved when the Safety Evaluation Report and Supplements 1, 2, 3, 4, 6, 12, 21, 22, 23, 24, and 25 to that report were published. This supplement deals primarily with Unit 2 issues; however, it also references evaluations for several licensing issues that relate to Unit 1, which have been resolved since Supplement 25 was issued

  6. Improved HYLIFE-II heat transport system and steam power plant: Impact on performance and cost of electricity

    International Nuclear Information System (INIS)

    The HYLIFE-II conceptual design has evolved and improved continually over the past four years to its present form. This paper describes the latest FY92 versions, Reference Case H1 (nominally 1 GWe net output) and the Enhanced Case HE (nominally 2 GWe net output), which take advantage of improvements in the tritium management system to eliminate the intermediate loop and the intermediate heat exchangers (IHX's). The improvements in the heat transport system and the steam power plant are described and the resulting cost reductions are evaluated. The new estimated cost of electricity (in 1990 dollars) is 6.6 cents/kWh for Reference Case H1 and 4.7 cents/kWh for the Enhanced Case

  7. Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Unit 2 (Docket No. 50-446)

    International Nuclear Information System (INIS)

    This document supplement 25 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Unit 2 (NUREG-0797), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement reports the status of certain issues that had not been resolved when the Safety Evaluation Report and Supplements 1, 2, 3, 4, 6, 12, 21, 22, 23, and 24 to that report were published. This supplement deals primarily with Unit 2 issues; however, it also references evaluations for several Unit 1 licensing items resolved since Supplement 24 was issued

  8. The methods and tools for system analysis of surface heat exchangers of steam-gas turbine and oil-electrical energy installations

    OpenAIRE

    ГАНЖА, А. Н.; Марченко, Н. А.

    2010-01-01

    The methods and tools for system analysis of heat-exchange equipments of steam-gas turbine and oil-electrical energy installations are developed. The methodic and dependences can use for solution of optimization tasks. The apparatus effectiveness depending on surface composition and generalized parameters that reflects of heat-transfer rates, relation of heat carrier expense, operational and technological factors are investigated.

  9. Technical specifications: Susquehanna Steam Electric Station, Unit No. 2 (Docket No. 50-388). Appendix A to License No. NPF-22

    International Nuclear Information System (INIS)

    Susquehanna Steam Electric Station, Unit 2 Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

  10. Effectiveness of The Development And Expansion of The Steam Power Station Condensate To Centers Thermoelectric Dedicated To The Production of Electric Power And Water Desalination

    Directory of Open Access Journals (Sweden)

    Gamal Yaseen Salman

    2014-04-01

    Full Text Available This research includes a mathematical form to study the effectiveness of development of basic design form condensation steam powers to dual pressure thermoelectric centers allocated for production of electric power and distillation water with the aspect of thermal effectiveness scale and preserving the lowest level of pollution for the surrounding media, in this study the scale of saving is used in the amount of fuel saved in the electric network due to the joint process of production for electric power and distillation water in suggested design compared to a separate production process for electric power and distillation water via a replacement station and distillation unit from the type of reverse osmosis. Hence the effect of design the multiple effect evaporation distillation unit and the gas turbine unit were studied, and so basic thermodynamic characteristics for this unit on the scale of effectiveness for development of basic design of steam st ation. Study findings provided the following:

  11. [New Brunswick Power] Fifteen year load forecast, 1990-2005

    International Nuclear Information System (INIS)

    A fifteen-year forecast of the electric requirements of the in-province customers of New Brunswick Power Commission is prepared each year based on a cause and effect analysis of past loads, combined with data gathered through customer surveys and an assessment of economic, demographic, technological and other factors which affect the utilization of electrical energy. In addition to the forecast requirements of each sales classification and total energy supply by month, a forecast of the monthly peak hour demand is also presented. The forecast results are used in overall short and long term planning, particularly the financial and facilities planning. Since variations from the forecast can significantly affect the future financial and facilities requirements, a forecast range is included which indicates the sensitivity of the forecast to various input parameters and their resulting impact on the final results. Total power demand is forecast to increase from 13,183 GWh to 19,703 GWh or 2.8%/y over the 15-year period; in the same period, the maximum peak demand is forecast to increase from 2637 MW to 3818 MW. These results are generally the same as in the previous year's forecast. Nevertheless, the latest forecast shows a trend toward lower energy consumption, a phenomenon which responds to the short term economic situation. By end-use sector, power demand is forecast to grow from 4316 GWh to 6240 GWh in the residential sector, from 2169 GWh to 3454 GWh in the general sector, and from 5247 GWh to 8319 GWh in the industrial sector. 15 figs., 18 tabs

  12. 78 FR 41907 - Effluent Limitations Guidelines and Standards for the Steam Electric Power Generating Point...

    Science.gov (United States)

    2013-07-12

    ..., rather than August 6, 2013. List of Subjects in 40 CFR Part 423 Environmental protection, Electric power generation, Power plants, Waste treatment and disposal, Water pollution control. Dated: July 3, 2013. Ellen... days. DATES: Comments. The public-comment period for the proposed rule published June 7, 2013, (78...

  13. Environmental approvals in New Brunswick : economic considerations

    Energy Technology Data Exchange (ETDEWEB)

    Marrack, C.; Maitland, R. [Suez Renewable Energy North America, Houston, TX (United States)

    2008-07-01

    This presentation provided a timeline of economic considerations related to New Brunswick's regulatory approval process for wind power developments. The economics of wind power projects require careful consideration during the initial planning phases, as it is not yet known if projects are viable. Spending in the early stages of a project should therefore be limited to items that focus on components of the environmental impact assessment (EIA) process that include establishing a relationship with First Nations groups in the area, and conducting seasonal bird studies. Economic considerations change when project viability is confirmed, and developers can then progress to conducting traditional knowledge studies and further seasonal bird studies. Baseline information studies should be reviewed, and biophysical surveys should involve the identification of any wetlands, sensitive areas, and rare plants. Archaeology studies are also required by the provincial government, as well as bat studies to determine if the site has a resident population of bats. Public and stakeholder consultations and open houses should then be held with an adequate time-frame for the submission of questions and concerns and the development of mitigation strategies. Project viability should be confirmed before power purchase agreements (PPAs) are signed. After PPAs are signed, the largest economic consideration is the schedule-related risk associated with legal and financial problems. It was concluded that noise impact, visual impact, and socioeconomic assessments and studies can be conducted after the PPA is secured. tabs., figs.

  14. On-line mechanical tube cleaning for steam electric power plants. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-18

    In July 1991, Superior I.D. Tube Cleaners, Inc. (SIDTEC{trademark}) received a grant through the Department of Energy and the Energy Related Invention Program to conduct a long term demonstration of a proprietary technology for on-line mechanical condenser tube cleaning in thermal Power plants on open or once-through cooling water systems where the warmed condenser cooling water is discharged through a canal. The purpose of the demonstration was to confirm and establish the use of this mechanical method as an alternative to the application of chemical biocides in condenser cooling water for the control of biofouling, the growth of micro-organisms which can reduce a unit`s operating efficiency. The SIDTEC on-line mechanical tube cleaner, the Rocket{trademark}, is used to physically remove accumulated deposits on the water side of the main steam condenser, and the non-intrusive tube cleaner recovery system, the Skimmer{trademark}, is used to recover and recirculate tube cleaners. The periodic circulation of tube cleaners can maintain optimum condenser cleanliness and improve unit heat rate. Thermal power plants which discharge condenser cooling water through a canal now have a viable alternative to the chemical treatment of condenser cooling water, whether the principal foulant is biofouling, chemical scaling, silting, or a combination of the three. At prices competitive with scale inhibitors, and a fraction of competing mechanical systems, this technology is provided as a service requiring no capital investment; minimal retrofit modifications to plant structures or equipment; can be installed and maintained without a unit shutdown; does not add any restrictions in the cooling water system; and is environmentally benign.

  15. Energy Conversion Alternatives Study (ECAS), Westinghouse phase 1. Volume 5: Combined gas-steam turbine cycles. [energy conversion efficiency in electric power plants

    Science.gov (United States)

    Amos, D. J.; Foster-Pegg, R. W.; Lee, R. M.

    1976-01-01

    The energy conversion efficiency of gas-steam turbine cycles was investigated for selected combined cycle power plants. Results indicate that it is possible for combined cycle gas-steam turbine power plants to have efficiencies several point higher than conventional steam plants. Induction of low pressure steam into the steam turbine is shown to improve the plant efficiency. Post firing of the boiler of a high temperature combined cycle plant is found to increase net power but to worsen efficiency. A gas turbine pressure ratio of 12 to 1 was found to be close to optimum at all gas turbine inlet temperatures that were studied. The coal using combined cycle plant with an integrated low-Btu gasifier was calculated to have a plant efficiency of 43.6%, a capitalization of $497/kW, and a cost of electricity of 6.75 mills/MJ (24.3 mills/kwh). This combined cycle plant should be considered for base load power generation.

  16. New Brunswick Site annual environmental report for calendar year 1991, New Brunswick, New Jersey

    International Nuclear Information System (INIS)

    This document describes the environmental monitoring program at the New Brunswick Site (NBS) and surrounding area, implementation of the program, and monitoring results for 1991. The site, near New Brunswick,, New Jersey, is a 5.6-acre vacant, fenced, and grass-covered area. Environmental monitoring of NBS began in 1981 when the site was part of the US Department of Energy's (DOE) Surplus Facilities Management Program. In 1990 responsibility for NBS was transferred to the Formerly Utilized Sites Remedial Action Program (FUSP.4P). FUSRAP is a DOE program to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the,early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The environmental monitoring program at NBS includes sampling networks for radon and thoron in air; external gamma radiation exposure; and radium-226, radium-228, thorium-228, thorium-230, thorium-232, americium-241, cesium-137, plutonium-239, and total uranium in surface water, sediment, and groundwater. Several nonradiological parameters are also measured in groundwater, surface water, and sediments. Monitoring results are compared with applicable Environmental Protection Agency standards, DOE derived concentration guides, dose limits, and other requirements in DOE orders. Environmental standards are established to protect public health and the environment

  17. 1300MVA steam-turbine generators for Kansai Electric Power's Oi Nuclear Power Station

    International Nuclear Information System (INIS)

    Mitsubishi Electric has completed two 1300 MVA generators, equipped with 5500kW brushless exciters, that will be the No. 1 and No. 2 generators of the Oi plant. They are among the largest anywhere, and incorporate such technological innovations as water cooling of the stator coil and asymmetrical arrangement of the rotor slots. The article discusses generator specifications and construction, the brushless exciter, and the results of factory tests. (auth.)

  18. Geology of uranium and associated elements in New Brunswick

    International Nuclear Information System (INIS)

    Eighty-two uranium occurrences have been identified in New Brunswick. Most of the data describing these occurrences is contained within assessment reports by claim holders to the provincial Department of Natural Resources and Energy. Additional information is contained within publications of the Geological Survey of Canada and in university theses. Seven metallogenic uraniferous domains are identified in New Brunswick: the Gaspe Synclinorium, Aroostook-Matapedia Anticlinorium, Chaleur Bay Synclinorium, Miramichi Anticlinorium, Fredericton Trough, Avalonian Platform and the Carboniferous Basin. Of these seven domains, the Miramichi Anticlinorium, Fredericton Trough and the Carboniferous Basin appear to be the most promising. The uranium occurrences in New Brunswick are preferentially associated with the Devono-Carboniferous rocks and appear to be related to deformational, magmatic and hydrothermal processes associated with the Acadian Orogeny. (numerous refs)

  19. New Coleoptera records from New Brunswick, Canada: Lycidae

    Directory of Open Access Journals (Sweden)

    Reginald Webster

    2012-04-01

    Full Text Available Eight species of Lycidae are newly recorded from New Brunswick, Canada, bringing the total number of species known from the province to 16. The first documented records from New Brunswick are provided for Greenarius thoracicus (Randall Erotides scuptilis (Say, and Calopteron terminale (Say reported by Majka et al. (2011. Eropterus arculus Green, Lopheros crenatus (Germar, and Calochromus perfacetus (Say are reported for the first time in the Maritime provinces. Collection data, habitat data, and distribution maps are presented for all these species.

  20. New Coleoptera records from New Brunswick, Canada: Silvanidae and Laemophloeidae

    Directory of Open Access Journals (Sweden)

    Reginald Webster

    2012-04-01

    Full Text Available One species of Silvanidae, Silvanus muticus Sharp, is newly recorded from New Brunswick, Canada and the Maritime provinces; Ahasverus longulus (Blatchley is re-instated to the faunal list of the province, and we report the first recent provincial records of Dendrophagus cygnaei Mannerheim. Five species of Laemophloeidae (Charaphloeus convexulus (LeConte, Charaphloeus undescribed species (near adustus, Leptophloeus angustulus (LeConte, Placonotus zimmermanni (LeConte, and an undescribed Leptophloeus species are added to the faunal list of New Brunswick. Collection data, bionomic data, and distribution maps are presented for all these species.

  1. Final Environmental Statement related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446)

    International Nuclear Information System (INIS)

    In September 1981, the staff of the Nuclear Regulatory Commission (NRC) issued its Final Environmental Statement (NUREG-0775) related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446), located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. The NRC has prepared this supplement to NUREG-0775 to present its evaluation of the alternative of operating Comanche Peak with the installation of further severe-accident-mitigation design features. The NRC has discovered no substantial changes in the proposed action as previously evaluated in the Final Environmental Statement that are relevant to environmental concerns and bearing on the licensing of Comanche Peak Steam Electric Station, Units 1 and 2. 6 refs., 3 tabs

  2. New Brunswick Power Corporation annual report, 1992/93

    International Nuclear Information System (INIS)

    In 1992/93, New Brunswick Power distributed and sold 16,058.6 GWh of electricity, of which ca 7.5 TWh was produced in thermal plants, 5.2 TWh nuclear, and 2.5 TWh hydroelectric. Exports of power to other provinces and the USA totalled 3,142 GWh, down 46.8% from 1991/92. Factors in the decrease included general economic conditions and surplus capacity in New England. Total revenue for 1992/93 was $903.1 million, down 2.2% from the previous year. In-province revenues rose 5% to $35.2 million, with the largest increases in the residential, general services, and wholesale sectors. The first 443-MW coal-fired unit at the Belledune power plant, initially scheduled for completion in September 1993, was delayed due to a fire in the unit transformer. The station is now being commissioned prior to coming into service. A new 345-kV transmission line was constructed from Salisbury to Bathurst, completing a 345-kV ring around the province. The utility's microwave communications network was upgraded to serve the new transmission line. At the Dalhousie generating station, work is in progress to convert the boilers from burning oil and coal to Orimulsion trademark. Both Dalhousie and Belledune will be fitted with advanced flue gas desulfurization systems. A new 138/69 kV terminal was completed and new substations will be added directly to the 138 kV-system to hold load on the 69-kV system to its existing capabilities. Additional activities of the utility are described in the areas of energy management and conservation, safety, training, labor issues, and the environment. Financial statements are included. 6 figs., 9 tabs

  3. Safety evaluation report related to the operation of Waterford Steam Electric Station, Unit No. 3 (Docket No. 50-382). Supplement No. 7

    International Nuclear Information System (INIS)

    Supplement 7 to the Safety Evaluation Report for Louisiana Power and Light's application for a license to operate Waterford Steam Electric Station, Unit 3 (Docket No. 50-382), located in St. Charles Parish, Louisiana, has been jointly prepared by the Office of Nuclear Reactor Regulation and the Region IV Office of the US Nuclear Regulatory Commission. This supplement provides the results to date of the staff's evaluation of approximately 350 allegations and concerns of poor construction practices at the Waterford 3 facility

  4. Steam-electric plant air and water quality control data. Summary report for the year ended December 31, 1975, based on FPC Form No. 67

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-01-01

    Data relating to nationwide impacts of steam-electric power plants on the environment are discussed with regard to growth of the industry; fuel quality; air pollution control; water pollution control; and cost of cooling facilities. Tables are presented to show the following: air quality data aggregated by state and geographic region and by air quality control region; water quality data aggregated by state and geographic region and by water resource region; and individual plant data. (HLW)

  5. Feed pump drives - comparing the efficiency of steam turbine and electrical drives

    International Nuclear Information System (INIS)

    With about 2 to 4% of the plant power, the feedwater pumps are among the main consumers of auxiliary power in fossil-fired and nuclear power stations. Advanced drive components, changes in the mode of operation, the operational cost and the load programmes make a study of profitableness necessary. The factors and criteria of evaluation relevant to this study of profitableness are dealt with. Practicable pump and drive combinations for a conventional power station, a nuclear power station with PWR reactor and one with HTR reactor are investigated. The cost difference to a basic variant with 100% turbopump is given. The power limits for the use of electrical drives are stated. (orig./AK)

  6. Final environmental statement related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2: (Docket Nos. 50-445 and 50-446)

    International Nuclear Information System (INIS)

    The proposed action is the issuance of operating licenses to the Texas Utilities Generating Company for the startup and operation of Units 1 and 2 of the Comanche Peak Steam Electric Station located on Squaw Creek Reservoir in Somervell County, Texas, about 7 km north-northeast of Glen Rose, Texas, and about 65 km southwest of Fort Worth in north-central Texas. The information in this environmental statement represents the second assessment of the environmental impact associated with the Comanche Peak Steam Electric Station pursuant to the guidelines of the National Environmental Policy Act of 1969 (NEPA) and 10 CFR Part 51 of the Commission's Regulations. After receiving an application to construct this station, the staff carried out a review of impact that would occur during its construction and operation. This evaluation was issued as a Final Environmental Statement -- Construction Phase. After this environmental review, a safety review, an evaluation by the Advisory Committee on Reactor Safeguards, and public hearings in Glen Rose, Texas, the US Atomic Energy Commission (now US Nuclear Regulatory Commission) issued construction permits for the construction of Units 1 and 2 of the Comanche Peak Steam Electric Station. 16 figs., 34 tabs

  7. Safety evaluation report related to the operation of Susquehanna Steam Electric Station, Units 1 and 2 (Docket Nos. 50-387 and 50-388). Suppl.6

    International Nuclear Information System (INIS)

    In April 1981, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0776) regarding the application of the Pennsylvania Power and Light Company (the applicant and/or licensee) and the Allegheny Electric Cooperative, Inc. (co-applicant) for licenses to operate the Susquehanna Steam Electric Station, Units 1 and 2, located on a site in Luzerne County, Pennsylvania. This supplement to NUREG-0776 addresses the remaining issues that required resolution before licensing operation of Unit 2 and closes them out

  8. The progress of retail marketing in New Brunswick

    International Nuclear Information System (INIS)

    Enbridge Atlantic Energy Services began commercial operation in New Brunswick in September 2001. Its objective was to provide all customer sectors with competitively priced and quality natural gas services. It was noted that while much progress has been made in the province regarding the pace of natural gas growth, there are many challenges to resolve before homeowners, businesses and the economy of New Brunswick obtain the same benefits as their neighbouring provinces. Prior to September 2001, much of the focus on gas retailing was on vertically integrated suppliers. This design was probably a contributor to the slower than anticipated growth of natural gas in the province. Another option, a fully deregulated model, may be a good end objective, but it may not be suitable for New Brunswick because it is only in the early stages of a growing market. An effective option would be to allow local distribution companies with the flexibility of implementing a system of gas supply for customers. This is the option that Nova Scotia has recently adopted. It allows the competitive natural gas marketers to participate in the industry growth by offering customers different incentives. Some of the key areas that still need constructive changes in New Brunswick are: (1) increased government support of natural gas as an emerging fuel choice, (2) relaxing some of the regulatory pressure on the industry, (3) improved consistency in applying codes and standards for equipment installations, and (4) creating a flexible environment for companies to add skilled technicians to their businesses

  9. Assessment of MTI Water Temperature Retrievals with Ground Truth from the Comanche Peak Steam Electric Station Cooling Lake

    International Nuclear Information System (INIS)

    Surface water temperatures calculated from Multispectral Thermal Imager (MTI) brightness temperatures and the robust retrieval algorithm, developed by the Los Alamos National Laboratory (LANL), are compared with ground truth measurements at the Squaw Creek reservoir at the Comanche Peak Steam Electric Station near Granbury Texas. Temperatures calculated for thirty-four images covering the period May 2000 to March 2002 are compared with water temperatures measured at 10 instrumented buoy locations supplied by the Savannah River Technology Center. The data set was used to examine the effect of image quality on temperature retrieval as well as to document any bias between the sensor chip arrays (SCA's). A portion of the data set was used to evaluate the influence of proximity to shoreline on the water temperature retrievals. This study found errors in daytime water temperature retrievals of 1.8 C for SCA 2 and 4.0 C for SCA 1. The errors in nighttime water temperature retrievals were 3.8 C for SCA 1. Water temperature retrievals for nighttime appear to be related to image quality with the largest positive bias for the highest quality images and the largest negative bias for the lowest quality images. The daytime data show no apparent relationship between water temperature retrieval error and image quality. The average temperature retrieval error near open water buoys was less than corresponding values for the near-shore buoys. After subtraction of the estimated error in the ground truth data, the water temperature retrieval error was 1.2 C for the open-water buoys compared to 1.8 C for the near-shore buoys. The open-water error is comparable to that found at Nauru

  10. Digital implementation, simulation and tests in MATLAB of the models of Steam line, the turbines, the pressure regulator of a BWR type nucleo electric power plant

    International Nuclear Information System (INIS)

    In this phase of the project they were carried out exhaustive tests to the models of the steam lines, turbines and pressure regulator of a BWR type nucleo electric central for to verify that their tendencies and behaviors are it more real possible. For it, it was necessary to also analyze the transfer functions of the different components along the steam line until the power generator. Such models define alone the dominant poles of the system, what is not limitation to reproduce a wide range of anticipated transitoriness of a power station operation. In the same manner, it was integrated and proved the integrated model form with the models of feeding water of the SUN-RAH, simulating the nuclear reactor starting from predetermined entrances of the prospective values of the vessel. Also it was coupled with the graphic interface developed with the libraries DirectX implementing a specific monitoring panel for this system. (Author)

  11. Biomass-to-electricity: analysis and optimization of the complete pathway steam explosion--enzymatic hydrolysis--anaerobic digestion with ICE vs SOFC as biogas users.

    Science.gov (United States)

    Santarelli, M; Barra, S; Sagnelli, F; Zitella, P

    2012-11-01

    The paper deals with the energy analysis and optimization of a complete biomass-to-electricity energy pathway, starting from raw biomass towards the production of renewable electricity. The first step (biomass-to-biogas) is based on a real pilot plant located in Environment Park S.p.A. (Torino, Italy) with three main steps ((1) impregnation; (2) steam explosion; (3) enzymatic hydrolysis), completed by a two-step anaerobic fermentation. In the second step (biogas-to-electricity), the paper considers two technologies: internal combustion engines and a stack of solid oxide fuel cells. First, the complete pathway has been modeled and validated through experimental data. After, the model has been used for an analysis and optimization of the complete thermo-chemical and biological process, with the objective function of maximization of the energy balance at minimum consumption. The comparison between ICE and SOFC shows the better performance of the integrated plants based on SOFC. PMID:22940353

  12. Modelling and simulation of the steam line, the high and low pressure turbines and the pressure regulator for the SUN-RAH nucleo electric university simulator

    International Nuclear Information System (INIS)

    In the following article the development of a simulator that allows to represent the dynamics of the following systems: steam line, nozzle, vapor separator, reheater, high pressure turbine, low pressure turbine, power generator and the pressure regulator of a nucleo electric power station. We start from the supposition that this plant will be modeled from a nuclear reactor type BWR (Boiling Water Reactor), using models of reduced order that represent the more important dynamic variables of the physical processes that happen along the steam line until the one generator. To be able to carry out the simulation in real time the Mat lab mathematical modeling software is used, as well as the specific simulation tool Simulink. It is necessary to point out that the platform on which the one is executed the simulator is the Windows operating system, to allow the intuitive use that only this operating system offers. The above-mentioned obeys to that the objective of the simulator it is to help the user to understand some of the dynamic phenomena that are present in the systems of a nuclear plant, and to provide a tool of analysis and measurement of variables to predict the desirable behavior of the same ones. The model of a pressure controller for the steam lines, the high pressure turbine and the low pressure turbine is also presented that it will be the one in charge of regulating the demand of the system according to the characteristics and critic restrictions of safety and control, assigned according to those wanted parameters of performance of this system inside the nucleo electric plant. This simulator is totally well defined and it is part of the University student nucleo electric simulator with Boiling Water Reactor (SUN-RAH), an integral project and of greater capacity. (Author)

  13. Safety-evaluation report related to the operation of Waterford Steam Electric Station, Unit No. 3. Docket No. 50-382

    International Nuclear Information System (INIS)

    Supplement 5 to the Safety Evaluation Report for the application filed by Louisiana Power and Light Company for a license to operate the Waterford Steam Electric Station, Unit 3 (Docket No. 50-382), located in St. Charles Parish, Louisiana has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation Report by providing the staff's evaluation of information submitted by the applicant since the Safety Evaluation Report and its four previous Supplements were issued

  14. EPA flow reference method testing and analysis: Data report -- Texas Utilities, DeCordova Steam Electric Station. Volume 1: Test description and appendix A (data distribution package)

    International Nuclear Information System (INIS)

    This report describes the test site, equipment, and procedures and presents the data obtained during field testing at Texas Utilities DeCordova Steam Electric Station, June 3-8, 1997. This was the first of three field tests that the US Environmental Protection Agency (EPA) conducted in 1997 as part of a major study to evaluate potential improvements to Method 2, EPA's test Method for measuring flue gas volumetric flow in stacks. The report also includes a Data Distribution Package, the official, complete repository of the results obtained at this test site

  15. EPA flow reference method testing and analysis: Data report -- Texas Utilities, Lake Hubbard Steam Electric Station. Volume 1: Test description and appendix A (data distribution package)

    International Nuclear Information System (INIS)

    This report describes the test site, equipment, and procedures and presents the data obtained during field testing at Texas Utilities Lake Hubbard Steam Electric Station, July 8-12, 1997. This was the second of three field tests that the US Environmental Protection Agency (EPA) conducted in 1997 as part of a major study to evaluate potential improvements to Method 2, EPA's test method for measuring flue gas volumetric flow in stacks. The report also includes a Data Distribution Package, the official, complete repository of the results obtained at this test site

  16. The ANF [Advanced Nuclear Fuels Corporation]-RELAP small-break LOCA [loss-of-coolant accident] analysis for the Comanche Peak steam electric station

    International Nuclear Information System (INIS)

    The system response code RELAP/MOD2 Idaho National Engineering Laboratory cycle 36.02, with modifications developed by Advanced Nuclear Fuels Corporation (ANF), was used to perform small-break loss-of-coolant accident (SBLOCA) calculations for the Comanche Peak steam electric station (CPSES) unit 1. The ability of the ANF-RELAP code to calculate the SBLOCA system response for the four-loop pressurized water reactor is presented by discussing the overall system response, the system mass distribution, and the core response

  17. Safety Evaluation Report related to the operation of Waterford Steam Electric Station, Unit No. 3 (Docket No. 50-382). Supplement No. 8

    International Nuclear Information System (INIS)

    Supplement 8 to the Safety Evaluation Report for the application filed by Louisiana Power and Light Company for a license to operate the Waterford Steam Electric Station, Unit 3 (Docket No. 50-382), located in St. Charles Parish, Louisiana, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation Report by providing the staff's evaluation of information submitted by the applicant since the Safety Evaluation Report and its seven previous supplements were issued

  18. Safety Evaluation Report related to the operation of Waterford Steam Electric Station, Unit No. 3 (Docket No. 50-382). Supplement 9

    International Nuclear Information System (INIS)

    Supplement 9 to the Safety Evaluation Report for Louisiana Power and Light's application for a license to operate Waterford Steam Electric Station, Unit 3 (Docket No. 50-382), located in St. Charles Parish, Louisiana, has been jointly prepared by the Office of Nuclear Reactor Regulation and the Region IV Office of the US Nuclear Regulatory Commission. This supplement provides the results of the staff's completion of its evaluation of approximately 350 allegations and concerns of poor construction practices at the Waterford 3 facility

  19. Safety evaluation report related to the operation of Waterford Steam Electric Station, Unit No. 3 (Docket No. 50-382). Suppl.6

    International Nuclear Information System (INIS)

    Supplement 6 to the Safety Evaluation Report for the application filed by Louisiana Power and Light Company for a license to operate the Waterford Steam Electric Station, Unit 3 (Docket No. 50-382), located in St. Charles Parish, Louisiana, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation Report by providing the staff's evaluation of information submitted by the applicant since the Safety Evaluation Report and its five previous supplements were issued

  20. New Brunswick Laboratory progress report, October 1994--September 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    The mission of the New Brunswick Laboratory (NBL) of the A. S. Department of Energy (DOE) is to serve as the National Certifying Authority for nuclear reference materials and to provide an independent Federal technical staff and laboratory resource performing nuclear material measurement, safeguards, and non-proliferation functions in support of multiple program sponsors. This annual report describes accomplishments achieved in carrying out NBL`s assigned missions.

  1. New Brunswick Laboratory progress report, October 1994--September 1995

    International Nuclear Information System (INIS)

    The mission of the New Brunswick Laboratory (NBL) of the A. S. Department of Energy (DOE) is to serve as the National Certifying Authority for nuclear reference materials and to provide an independent Federal technical staff and laboratory resource performing nuclear material measurement, safeguards, and non-proliferation functions in support of multiple program sponsors. This annual report describes accomplishments achieved in carrying out NBL's assigned missions

  2. Care of the newborn in perinatal units in New Brunswick

    OpenAIRE

    Stephen, David L.

    1986-01-01

    A survey of 23 perinatal units in New Brunswick hospitals was conducted by means of a mailed questionnaire to determine the type of care provided to newborns. The results showed various degrees of conformity with published guidelines for the care of newborns. Deficiencies were noted in several areas of care: failing to give or improperly giving vitamin K1 prophylaxis (in 7 of the units), flushing the eyes after silver nitrate prophylaxis (in 10), using hexachlorophene to bathe newborns (in 11...

  3. New Coleoptera records from New Brunswick, Canada: Eucnemidae

    Directory of Open Access Journals (Sweden)

    Reginald Webster

    2012-04-01

    Full Text Available We report nine species of Eucnemidae new to the province and additional records for Onichodon canadensis (Brown and Dromaeolus harringtoni Horn. Five species, Xylophilus cylindriformis (Horn, Entomophthalmus rufiolus (LeConte, Stethon pectorosus LeConte, Onichodon orchesides Newman, and Isarthrus rufipes (Melsheimer, are newly recorded for the Maritime provinces. This brings the total number of Eucnemidae recorded from New Brunswick to 15 species. Lindgren funnel traps are an effective tool for sampling the Eucnemidae.

  4. Impact on the steam electric power industry of deleting Section 316(a) of the Clean Water Act: Energy and environmental impacts

    International Nuclear Information System (INIS)

    Many power plants discharge large volumes of cooling water. In some cases, the temperature of the discharge exceeds state thermal requirements. Section 316(a) of the Clean Water Act (CWA) allows a thermal discharger to demonstrate that less stringent thermal effluent limitations would still protect aquatic life. About 32% of the total steam electric generating capacity in the United States operates under Section 316(a) variances. In 1991, the US Senate proposed legislation that would delete Section 316(a) from the CWA. This study, presented in two companion reports, examines how this legislation would affect the steam electric power industry. This report quantitatively and qualitatively evaluates the energy and environmental impacts of deleting the variance. No evidence exists that Section 316(a) variances have caused any widespread environmental problems. Conversion from once-through cooling to cooling towers would result in a loss of plant output of 14.7-23.7 billion kilowatt-hours. The cost to make up the lost energy is estimated at $12.8-$23.7 billion (in 1992 dollars). Conversion to cooling towers would increase emission of pollutants to the atmosphere and water loss through evaporation. The second report describes alternatives available to plants that currently operate under the variance and estimates the national cost of implementing such alternatives. Little justification has been found for removing the 316(a) variance from the CWA

  5. Tracking of Steam Generator Thermal Performance Trends

    International Nuclear Information System (INIS)

    A significant number of pressurized water reactor (PWR) plants have reported decreases in their steam generator steam pressure during the last several years. Because a steam pressure decrease causes a reduction of the electrical power generating capacity directly, a steam generator's thermal performance is one of the important issues for steam generator maintenance. Therefore, the Korea Hydro and Nuclear Power Company has established an on-line acquisition system for plant operational parameters as a part of the Steam Generator Management Program (SGMP). Recently, plant-specific tools for calculating the overall heat transfer coefficient and the global fouling factor were also constructed and applied to some plants

  6. New Coleoptera records from New Brunswick, Canada: Geotrupidae and Scarabaeidae

    Directory of Open Access Journals (Sweden)

    Reginald Webster

    2012-04-01

    Full Text Available Two species of Geotrupidae, Geotrupes splendidus splendidus (Fabricius and Odonteus liebecki (Wallis, are newly reported for New Brunswick, Canada. Twelve species of Scarabaeidae are added to the faunal list of the province, including Aegialia criddlei Brown, Caelius humeralis (Brown, Dialytellus dialytoides (Fall, Diapterna omissa (LeConte, Diapterna pinguis (Haldeman, Planolinoides aenictus (Cooper and Gordon, Stenotothorax badipes (Melsheimer, and Ataenius strigatus (Say, which are also newly recorded for the Maritime provinces. Collection data, habitat data, and distribution maps are presented for each species.

  7. Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2. Docket Nos. 50-445 and 50-446

    International Nuclear Information System (INIS)

    Supplement No. 3 to the Safety Evaluation Report (SER) related to the operation of the Comanche Peak Steam electric Station, Units 1 and 2, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. the facility is located in Somervell County, Texas. Subject to favorable resolution of the items identified in this supplement, the staff concludes that the facility can be operated by the applicatn without endangering the health and safety of the public. This document provides the NRC staff's evaluation of the outstanding and confirmatory issues that have been resolved since Supplement No. 2 was issued in January 1982, and addresses changes to the SER and its earlier supplements which have resulted from the receipt of additonal information from the applicant during the period of January throught October 1982

  8. Final environmental statement related to the operation of H.B. Robinson Nuclear Steam-Electric Plant, Unit 2: (Docket No. 50-261)

    International Nuclear Information System (INIS)

    The proposed action is the continuation of Facility Operating License DPR-23 to Carolina Power and Light Company for H.B. Robinson Unit 2. Unit 2, located adjacent to Lake Robinson in Darlington County, near Hartsville, South Carolina, employs a pressurized water reactor to produce up to 2200 megawatts thermal (MWt). A steam turbine-generator uses this heat to provide 700 megawatts electric (MWe) of net electrical power capacity. A design power level of 2300 MWt (730 MWe) has been requested and is considered in the assessments contained in this statement. The exhaust steam is cooled by a flow of water obtained from the discharged to a 2250-acre cooling lake, Lake Robinson. Land areas disturbed during construction of the plant, but not used, have been seeded to native grasses, trees, and shrubs. Construction of a cooling water discharge canal extension resulted in alteration of about 100 acres of wildlife habitat. Subsequently, the canal banks were seeded with pines and legumes. Some erosion has taken place in the pine-seeded areas. Some small fish are killed by impingement on the water intake screens. Organisms passing through the screens very likely do not survive their passage through the circulating water system. Operation of the plant will cause an increase in the temperature of Black Creek below Lake Robinson. A small impact exists due to production and, after processing, disposal or release of sanitary and chemical wastes. Unit 2 may discharge up to 500 pounds/day of chemicals (primarily sulfates). Under conditions of low flow into and out of the lake, this increases the sulfate concentration in the lake by less than 1 ppM over the normal 7.7 ppM

  9. New Brunswick Power Corporation annual report, 1993/94

    International Nuclear Information System (INIS)

    Net income for New Brunswick Power in the year 1993/94 was $23.7 million, up from $1.1 million the previous year. Total revenues decreased by $7.4 million as decreases in export sales were greater than in-province load growth and due to the impacts of a 5% rate increase in 1992 and 2.9% increase in January 1994. In-province energy sales revenues totalled $732.8 million, an increase of $25.1 million from 1992/93. Residential energy sales increased by 2.1% while the those to industrial customers declined by 1.4%, due to continuing economic difficulties in the pulp and paper and mining sector. Out of province revenues decreased by $33.3 million or 19.7%, with total energy exports decreasing by 688.6 GWh to 2453.6 GWh. A significant highlight of the year was integration of the Belledune generating station onto the New Brunswick sytem in October. A state-of-the-art coal fired facility, Belledune will contribute 450 MW to the system. Its flue gas scrubber will reduce sulfur dioxide emissions by 90%. 6 figs., 9 tabs

  10. New Brunswick Power Corporation annual report, 1993/94

    International Nuclear Information System (INIS)

    Net income for New Brunswick Power in the year 1993/94 was $23.7 million, up from $1.1 million the previous year. Total revenues decreased by $7.4 million as decreases in export sales were greater than in-province load growth and due to the impacts of a 5% rate increase in 1992 and 2.9% increase in January 1994. In-province energy sales revenues totalled $732.8 million, an increase of $25.1 million from 1992/93. Residential energy sales increased by 2.1% while the those to industrial customers declined by 1.4%, due to continuing economic difficulties in the pulp and paper and mining sector. Out of province revenues decreased by $33.3 million or 19.7%, with total energy exports decreasing by 688.6 GWh to 2453.6 GWh. A significant highlight of the year was integration of the Belledune generating station onto the New Brunswick system in October. A state-of-the-art coal fired facility, Belledune will contribute 450 MW to the system. Its flue gas scrubber will reduce sulfur dioxide emissions by 90%. 6 figs., 9 tabs

  11. Steam turbine

    OpenAIRE

    Vališ, Petr

    2010-01-01

    The master´s thesis concentrates on a project of steam turbine with controlled extraction points destined for a communal waste incineration plant. First, there the history of devices using steam as a moving medium is introduced and than follows the description of computing program, where the calculation was running. The master´s thesis subject consists in the thermodynamic project of turbine vaning, in basic project of gearbox including the check calculations and in technical economic compari...

  12. Steam Turbines

    Science.gov (United States)

    1981-01-01

    Turbonetics Energy, Inc.'s steam turbines are used as power generating systems in the oil and gas, chemical, pharmaceuticals, metals and mining, and pulp and paper industries. The Turbonetics line benefited from use of NASA research data on radial inflow steam turbines and from company contact with personnel of Lewis Research Center, also use of Lewis-developed computer programs to determine performance characteristics of turbines.

  13. Safety evaluation report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2: Docket No. 50-445 and 50-446

    International Nuclear Information System (INIS)

    Supplement 20 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Special Projects of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement presents the staff's evaluation of CPRT implementation of the Comanche Peak Response Team (CPRT) Program Plan and the issue-specific action plans (ISAPs), as well as the CPRT's investigations to determine the adequacy of various types of programs and hardware at CPSES. The results and conclusions of the CPRT activities are documented in a results report for each ISAP, a Collective Evaluation Report (CER), and a Collective Significance Report (CSR). This supplement also presents the staff's safety evaluation of TU Electric's root cause assessment of past CPSES design deficiencies and weaknesses. The NRC staff concludes that the CPRT has adequately implemented its investigative activities related to the design, construction, construction quality assurance/quality control, and testing at CPSES. The NRC staff further concludes that the CPRT evaluation of the results of its investigation is thorough and complete and its recommendations for corrective actions are sufficient to resolve identified deficiencies

  14. Saturated steam process with direct steam generating parabolic troughs

    Energy Technology Data Exchange (ETDEWEB)

    Eck, M. [DLR, Institute of Technical Thermodynamics, Pfaffenwaldring 38-40, 70569 Stuttgart (Germany); Zarza, E. [CIEMAT, Plataforma Solar de Almeria (PSA), P.O. Box 22, 04200 Tabernas (Almeria) (Spain)

    2006-11-15

    The direct steam generation (DSG) in parabolic trough collectors is an attractive option regarding the economic improvement of parabolic trough technology for solar thermal electricity generation in the multi Megawatt range. The European DISS project has proven the feasibility of the direct steam generation under real solar conditions in more than 4000 operation hours. Within the European R and D project INDITEP the detailed engineering for a pre-commercial DSG solar thermal power plant with an electrical power of 5MW is being performed. This small capacity was chosen to minimise the risk for potential investors. In regards to DSG solar thermal power plants, only steam cycles using superheated steam have been investigated so far. The paper will investigate the advantages, disadvantages, and design considerations of a steam cycle operated with saturated steam for the first time. For near term applications, saturated steam operated DSG plants might be an interesting alternative for power generation in the small capacity range due to some specific advantages: Simple set up of the collector field; Proven safe collector field operation; Higher thermal efficiency in the collector field. (author)

  15. Conception and design of steam power plants

    International Nuclear Information System (INIS)

    The manual presents the fundamentals of thermodynamics and fluid mechanics, the main components of steam power plants, and the power generation process. The following concepts and subjects are discussed at length: steam generator; steam turbines; turbogenerators; condensers; cooling technology; water/steam cycle and water treatment; design data of fossil-fuelled power plants; design and optimisation of nuclear power plant thermodynamics; pipelines and fittings; control systems in steam power plants; connection to the electricity grid and self-supply of thermal power plants; power plant transformer concepts and definitions. (HAG)

  16. Environmental contaminants in fish from Mere Brook - U.S. Naval Air Station, Brunswick, Maine

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — Mere Brook bisects three former landfills at the U.S. Naval Air Station in Brunswick, Maine (NASB). Leachate, soil, and sediment analyzed during Superfund remedial...

  17. New Brunswick Power Corporation: Business plan, 1994-1999

    International Nuclear Information System (INIS)

    The first publicly available business plan for the New Brunswick Power Corp. is presented. The five-year plan provides an overview of the Corporation's performance and directions, including possible future rate increases. A review of the corporate history of the utility is followed by a description of the strategic framework under which the Corporation conducts its business operations. The information presented includes customer requirements, power generation and transmission, system operations, personnel management, environmental protection, and external factors affecting operations. This overview demonstrates the complex issues facing the utility, the choices made in the past, and the matters that will have to be faced in the future. The business overview is followed by focused business plans in six key functional areas (facilities, operations, personnel, technology, environment, and finances) and comprehensive financial forecasts that outline a commitment to maintain competitive rates for customers. The reasoning behind the forecasts is explained and a glossary is included. 21 figs., 16 tabs

  18. New Brunswick Market Design Committee : Congestion management issues

    International Nuclear Information System (INIS)

    The restructuring of the New Brunswick wholesale power market comprises a number of issues that need to be resolved concerning transmission system related policy decisions and detailed design issues. The wholesale market structure, ownership structure, and means of preventing market power abuses all have an impact on the resolution of many of those issues. Some transmission related decisions regarding congestion management must be made, and they are examined in this document. The report includes a discussion of the issues related to congestion on the transmission system, a review of the decisions that remain to be made while proposing a number of alternatives, reviews decisions that other jurisdictions have made in somewhat similar circumstances. Finally, the advantages and disadvantages of each alternative are identified. Several high level transmission tariff design issues requiring to be addressed later in greater detail are listed in this document. 1 tab

  19. Safety evaluation report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446)

    International Nuclear Information System (INIS)

    Supplement 24 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement reports the status of certain issues that had not been resolved when the Safety Evaluation Report and Supplements 1, 2, 3, 4, 6, 12, 21, 22, and 23 to that report were published. This supplement also includes the evaluations for licensing items resolved since Supplement 23 was issued. Supplement 5 has not been issued. Supplements 7, 8, 9, 10, and 11 were limited to the staff evaluation of allegations investigated by the NRC Technical Review Team. Supplement 13 represented the staff's evaluation of the Comanche Peak Response Team (CPRT) Program Plan, which was formulated by the applicant to resolve various construction and design issues raised by sources external to TU Electric. Supplements 14 through 19 presented the staff's evaluation of the CPSES Corrective Action Program: large- and small-bore piping and pipe supports (Supplement 14); cable trays and cable tray hangers (Supplement 15); conduit supports (Supplement 16); mechanical, civil/structural, electrical, instrumentation and controls, and systems portions of the heating, ventilation, and air conditioning (HVAC) system workscopes (Supplement 17); HVAC structural design (Supplement 18); and equipment qualification (Supplement 19). Supplement 20 presented the staff's evaluation of the CPRT implementation of its Program Plan and the issue-specific action plans, as well as the CPRT's investigations to determine the adequacy of various types of programs and hardware at CPSES

  20. Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446)

    International Nuclear Information System (INIS)

    Supplement 23 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement reports the status of certain issues that had not been resolved when the Safety Evaluation Report and supplements 1, 2, 3, 4, 6, 12, 21, and 22 to that report were published. This supplement also includes the evaluations for licensing items resolved since Supplement 22 was issued. Supplement 5 has not been issued. Supplements 7, 8, 9, 10, and 11 were limited to the staff evaluation of allegations investigated by the NRC Technical Review Team. Supplement 13 presented the staff's evaluation of the Comanche Peak Response Team (CPRT) Program Plan, which was formulated by the applicant to resolve various construction and design issues raised by sources external to TU Electric. Supplements 14 through 19 presented the staff's evaluation of the CPSES Corrective Action Program: large- and small-bore piping and pipe supports (Supplement 14); cable trays and cable tray hangers (Supplement 15); conduit supports (Supplement 16); mechanical, civil/structural, electrical, instrumentation and controls, and systems portions of the heating, ventilation, and air conditioning (HVAC) system workscopes (Supplement 17); HVAC structural design (Supplement 18); and equipment qualification (Supplement 19). Supplement 20 presented the staff's evaluation of the Comanche Peak Response Team implementation of the CPRT Program

  1. New Staphylinidae (Coleoptera records with new collection data from New Brunswick, Canada: Omaliinae, Micropeplinae, Phloeocharinae, Olisthaerinae, and Habrocerinae

    Directory of Open Access Journals (Sweden)

    Reginald Webster

    2012-04-01

    Full Text Available Eleven species of Omaliinae are newly recorded from New Brunswick, bringing the total number of species known from the province to 32 described species. Supporting data are presented for the New Brunswick record of Geodromicus strictus (Fauvel reported by Majka et al. (2011. Micropeplus browni Campbell, Micropeplus laticollis Mäklin (Micropeplinae, Charyhyphus picipennis (LeConte (Phloeocharinae, Olisthaerus substriatus (Paykull (Olisthaerinae, Habrocerus capillaricornis (Gravenhorst, Habrocerus magnus LeConte, and Habrocerus schwarzi Horn (Habrocerinae are also newly recorded for New Brunswick. These are the first records of the latter four subfamilies from New Brunswick. Collection and bionomic data are presented for each species and discussed.

  2. Steam--electric plant air and water quality control data. Summary report for the year ended December 31, 1974

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-09-01

    This is the sixth annual report in a series based on FPC (Federal Power Commission) Form 67 supplemented with plant-by-plant annual generation and plant heat rate data from FPC Form No. 1. Information is included on growth of the electric power generation industry; quantities of coal, gas, and oil consumed for power generation in U.S. regions; heat, ash, and sulfur content of these fuels; emission data for fossil-fuel power plants and types and cost of air pollution equipment installed; and water pollution control and water use for condenser cooling. (LCL)

  3. Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446)

    International Nuclear Information System (INIS)

    Supplement 22 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station, Units 1 and 2 (NUREG-0797), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement reports the status of certain issues that had not been resolved at the time of publication of the Safety Evaluation Report and Supplements 1, 2, 3, 4, 6, 12, and 21 to that report. This supplement also includes the evaluations for licensing items resolved since Supplement 21 was issued. Supplement 5 has been cancelled. Supplements 7 through 11 were limited to the staff evaluation of allegations investigated by the NRC Technical Review Team. Supplement 13 presented the staff's evaluation of the Comanche Peak Response Team (CPRT) Program Plan, which was formulated by the applicant to resolve various construction and design issues raised by sources external to the applicant. Supplements 14 through 20 presented the staff's evaluation of the applicant's Corrective Action Program and CPRT activities. Items identified in Supplements 7, 8, 9, 10, 11, 13, 14, and 15 through 20 are not included in this supplement, except to the extent that they affect the applicant's Final Safety Analysis Report. 154 refs., 24 figs., 8 tabs

  4. Safety evaluation report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2: Docket Nos. 50-445 and 50-446

    International Nuclear Information System (INIS)

    Supplement 15 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Special Projects of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement presents the staff's evaluation of the applicant's Corrective Action Program (CAP) related to the design of cable trays and cable tray hangers. The scope and methodologies for the CAP workscope as summarized in Revision O to the cable tray and cable tray hanger project status report and as detailed in related documents referenced in this evaluation were developed to resolve various design issues raised by the Atomic Safety and Licensing Board (ASLB) the intervenor, Citizens Association for Sound Energy (CASE); the Comanche Peak Response Team (CPRT); CYGNA Energy Services (CYGNA); and the NRC staff. The NRC staff concludes that the CAP workscope for cable trays and cable tray hangers provides a comprehensive program for resolving the associated technical concerns identified by the ASLB, CASE, CPRT, CYGNA, and the NRC staff and its implementation ensures that the design of cable trays and cable tray hangers at CPSES satisfies the applicable requirements of 10 CFR Part 50

  5. Safety evaluation report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446)

    International Nuclear Information System (INIS)

    Supplement 18 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Special Projects of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement presents the staff's evaluation of the applicant's Corrective Action Program (CAP) related to the structural design of the heating, ventilation, and air conditioning (HVAC) systems. The scope and methodologies for the CAP workscope as summarized in Revision 0 to the HVAC project status report and as detailed in related documents referenced in this evaluation were developed to resolve the technical concerns identified in the HVAC area. The NRC staff concludes that the CAP workscope for the HVAC structural design provides a comprehensive program for resolving the associated technical concerns and its implementation ensures that the structural design of the HVAC systems at CPSES satisfies the applicable requirements of 10 CFR Part 50. 32 refs

  6. Comparison of food habits of white perch (Morone americana) in the heated effluent canal of a steam electric station and in an adjacent river system

    International Nuclear Information System (INIS)

    Analysis of the stomach contents of 97 white perch, Morone americana, taken from the effluent canal of a steam electric station (S.E.S.) and 106 white perch from adjacent Patuxent River waters indicated similar food habits from September 1970 through August 1971. However, 35 percent of all white perch taken from the heated effluent canal contained small pieces of coal and cinders, whereas only 3 percent of the river specimens contained such items in their stomachs. Fly ash and coal dust are present on the bottom of the S.E.S. canal, whereas little such material, if any, can be found on the river bottom in the study area. This suggests the canal fish were actively feeding in the heated effluent and not simply moving into the canal after feeding in the river. No significant difference (P greater than 0.05) was found between the average wet weight stomach contents of the river and canal fish within the same month

  7. Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446)

    International Nuclear Information System (INIS)

    Supplement 16 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Special Projects of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement presents the staff's evaluation of the applicant's Corrective Action Program (CAP) related to the design of conduit supports. The scope and methodologies for the CAP workscopes as summarized in Revision 0 to the conduit support project status reports and as detailed in related documents referenced in this evaluation were developed to resolve various design issues raised by the Comanche Peak Response Team (CPRT); CYGNA Energy Services (CYGNA); and the NRC staff. The NRC staff concludes that the CAP workscopes for conduit supports provide a comprehensive program for resolving the associated technical concerns identified by the CPRT, CYGNA, and the NRC staff. The NRC staff further concludes that implementation of the CAP workscope for conduit supports ensures that the design of conduit supports at CPSES satisfies the applicable requirements of 10 CFR Part 50

  8. Measurement of Sr-90 background levels in water, soil and milk around the site of the Comanche Peak Steam Electric Station

    International Nuclear Information System (INIS)

    Background concentrations of Sr-90 in water, soil and milk samples collected from preselected locations around the first nuclear power plant in Texas, the Comanche Peak Steam Electric Station at Glen Rose, were measured in the period 1980-82. Statistical analyses of measured data showed that: 1) in the first approximation, Sr-90 is distributed uniformly in the North Central Texas area; 2) no seasonal variation is observed in the concentrations measured in water, soil and milk; 3) the Sr-90 content of surface water is shown, however, to be higher than that of underground water; this difference might be explained by the atmospheric (fallout) origin of Sr-90 generated in atmospheric nuclear explosions before 1963; 4) in the area under investigation, Sr-90 concentrations turns out to be lower than those measured in northern parts of the US. This difference might be explained by the fact that the majority of atmospheric nuclear explosions were carried out at higher latitudes than that of Texas, and by the approximative conservation of latitude in the atmospheric motion of radioactive clouds

  9. Aerial radiological survey of the Comanche Peak Steam Electric Station and surrounding area, Glen Rose, Texas. Date of Survey: March 1982

    International Nuclear Information System (INIS)

    An aerial radiological survey was performed from 1 to 9 March 1982 over a 260-square-kilometer area centered on the Comanche Peak Steam Electric Station located in Somervell County, Texas. The survey was conducted by the Energy Measurements Group of EG and G for the US Nuclear Regulatory Commission. All gamma ray data were collected by flying parallel lines spaced 152 meters (500 feet) apart at an altitude of 91 meters (300 feet) above ground level. Count rates obtained from the aerial platform were converted to total exposure rates at 1 meter above the ground and are presented in the form of an isoradiation contour map. The observed exposure rates ranged from 6 to 12 microroentgens per hour (μR/h), with the average background ranging from 6 to 8 μR/h. These values include an estimated cosmic ray contribution of 3.8 μR/h. The exposure rates obtained from ground-based measurements taken in typical background locations within the survey area displayed positive agreement with the aerial data

  10. Saturated steam process with direct steam generating parabolic troughs

    Energy Technology Data Exchange (ETDEWEB)

    Eck, M. [Deutsches Zentrum fuer Luft- und Raumfahrt, Stuttgart (Germany). Inst. of Technical Thermodynamics; Zarza, E. [CIEMAT, Plataforma Solar de Almeria (PSA), Tabernas (Spain)

    2004-07-01

    The direct steam generation (DSG) in parabolic trough collectors is an attractive option regarding the economic improvement of parabolic trough technology for solar thermal electricity generation in the multi Megawatt range. The European DISS project has proven the feasibility of the direct steam generation under real solar conditions in more than 4000 operation hours. Within the European R and D project INDITEP the detailed engineering for a pre-commercial DSG solar thermal power plant with an electrical power of 5 MW is being performed. This small capacity is chosen to minimise the risk for potential investors. Regarding DSG solar thermal power plants only steam cycles using superheated steam have been investigated so far. In this paper a steam cycle operated with saturated steam is investigated for the first time. For near term applications this might be an interesting alternative in the chosen small capacity range. This choice would offer some specific advantages: (a) Lower complexity of power block and thus lower investment but also lower efficiency of the power block, (b) Simple set up of the collector field, (c) Proven safe operation and higher thermal efficiency of the collector field. (orig.)

  11. Safety evaluation report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446)

    International Nuclear Information System (INIS)

    Supplement 19 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Special Projects of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement presents the staff's evaluation of the Texas Utilities Electric Company's (lead applicant's) corrective action program (CAP) related to equipment qualification. The scope and methodology for the CAP workscope, as summarized in Revision 0 to the Equipment Qualification Project Status Report and as detailed in related documents, were developed to resolve various issues raised by the Comanche Peak Response Team (CPRT) and the NRC staff to ensure that plant equipment is appropriately environmentally and/or seismically and dynamically qualified and documented in accordance with the validated plant design resulting from other CAP scopes of work for Unit 1 and areas common to Units 1 and 2. The staff concludes that the CAP workscope for equipment qualification provides a comprehensive program for resolving the concerns identified by the CPRT and the NRC staff, including issues raised in the Comanche Peak Safety Evaluation Report and its supplements, and its implementation will ensure that the environmental and/or seismic and dynamic qualification of equipment at CPSES satisfies the validated plant design and the applicable requirements of 10 CFR Part 50. As is routine staff practice, the NRC staff will verify the adequacy of implementation of the environmental and seismic and dynamic equipment qualification program at CPSES during inspections that will take place before fuel loading. 97 refs

  12. Small and medium-sized high-temperature reactors for generation of electricity, process steam and district heat

    International Nuclear Information System (INIS)

    20 years of successful operation with the 15 MWe experimental power station (AVR) in Juelich and start up of power operation of the THTR 300 represent major steps towards commercial ultilization of the HTR. On the basis of the THTR 300 reference plant concept HTR's of flexible size can now be offered in the entire power range up to 600 MWe and as twin plants up to 1200 MWe. The HTR represents a universal source of energy with wide applications, offering the electrical and thermal power market a safe, environmentally compatible and economical supply of energy. The simplicity of its technology and its 'good nature' in operation and in response to accidents makes the HTR particularly well suited for countries just introducing nuclear technology (Liu)

  13. New Brunswick Laboratory. Progress report, October 1995--September 1996

    International Nuclear Information System (INIS)

    Fiscal year (FY) 1996 was a very good year for New Brunswick Laboratory (NBL), whose major sponsor is the Office of Safeguards and Security (NN-51) in the US Department of Energy (DOE), Office of Nonproliferation and National Security, Office of Security Affairs. Several projects pertinent to the NBL mission were completed, and NBL's interactions with partners and customers were encouraging. Among the partners with which NBL interacted in this report period were the International Atomic Energy Agency (IAEA), NN-51. Environmental Program Group of the DOE Chicago Operations Office, International Safeguards Project Office, Waste Isolation Pilot Plant (WIPP), Ukraine Working Group, Fissile Materials Assurance Working Group, National Institute of Standards and Technology (NIST), Nuclear Regulatory Commission (NRC), Institute for Reference Materials and Measurements (IRMM) in Belgium, Brazilian/Argentine Agency for Accounting and Control of Nuclear Materials (ABACC), Lockheed Idaho Technologies Company, and other DOE facilities and laboratories. NBL staff publications, participation in safeguards assistance and other nuclear programs, development of new reference materials, involvement in the updating and refinement of DOE documents, service in enhancing the science education of others, and other related activities enhanced NBL's status among DOE laboratories and facilities. Noteworthy are the facts that NBL's small inventory of nuclear materials is accurately accounted for, and, as in past years, its materials and human resources were used in peaceful nuclear activities worldwide

  14. New Brunswick Laboratory. Progress report, October 1995--September 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-04-01

    Fiscal year (FY) 1996 was a very good year for New Brunswick Laboratory (NBL), whose major sponsor is the Office of Safeguards and Security (NN-51) in the US Department of Energy (DOE), Office of Nonproliferation and National Security, Office of Security Affairs. Several projects pertinent to the NBL mission were completed, and NBL`s interactions with partners and customers were encouraging. Among the partners with which NBL interacted in this report period were the International Atomic Energy Agency (IAEA), NN-51. Environmental Program Group of the DOE Chicago Operations Office, International Safeguards Project Office, Waste Isolation Pilot Plant (WIPP), Ukraine Working Group, Fissile Materials Assurance Working Group, National Institute of Standards and Technology (NIST), Nuclear Regulatory Commission (NRC), Institute for Reference Materials and Measurements (IRMM) in Belgium, Brazilian/Argentine Agency for Accounting and Control of Nuclear Materials (ABACC), Lockheed Idaho Technologies Company, and other DOE facilities and laboratories. NBL staff publications, participation in safeguards assistance and other nuclear programs, development of new reference materials, involvement in the updating and refinement of DOE documents, service in enhancing the science education of others, and other related activities enhanced NBL`s status among DOE laboratories and facilities. Noteworthy are the facts that NBL`s small inventory of nuclear materials is accurately accounted for, and, as in past years, its materials and human resources were used in peaceful nuclear activities worldwide.

  15. Deformed glacial deposits of Passamaquoddy Bay area, New Brunswick

    International Nuclear Information System (INIS)

    The New Brunswick-Maine border area, centred around Passamaquoddy Bay, is characterized by a distinctly higher level of seismic activity compared with the very low level background activity of the region. In this same general area, post-glacial deformation including faulting, has been observed in glaciofluvial and ice contact deposits and the possibility that these structures may in some way related to neotectonic movements in the area has been suggested. A study was undertaken to document these structures and to investigate their origin. The studies show that structures related to collapse of sediments due to melting of buried ice masses are the most prominent post-depositional structures in the glacial sediments. A second group of structures includes failure phenomena such as slumping. These require the action of a mechanism leading to reduction of sediment strength which could be achieved by seismic shaking. However, such failure phenomena could also be brought about by non-seismic processes, thus a unique interpretation of the origin of these structures is difficult, if not impossible. Since seismic shaking is the most effective, regionally extensive trigger of a broad group of failure phenomena in soft sediments, the related structures are usually spread over a large area, but are restricted to a very short time gap. Although the establishment of such space and time relationships may be feasible, for example in extensive lake deposits, it is difficult to do so in patchy laterally variable deposits such as the glacial deposits in Passamaquoddy Bay area

  16. Steam boiler technology

    Energy Technology Data Exchange (ETDEWEB)

    Teir, S.

    2002-07-01

    The steam boiler technology e-Book is provided by the Laboratory of Energy Engineering and Environmental Protection at Helsinki University of Technology. The book covers the basics and the history of steam generation, modern boilers types and applications, steam/water circulation design, feedwater and steam systems components, heat exchangers in steam boilers, boiler calculations, thermal design of heat exchangers.

  17. New Coleoptera records from New Brunswick, Canada: Trogossitidae, Cleridae, and Melyridae, with an addition to the fauna of Nova Scotia

    Directory of Open Access Journals (Sweden)

    Reginald Webster

    2012-04-01

    Full Text Available Grynocharis quadrilineata (Melsheimer and Tenebroides corticalis (Melsheimer of the family Trogossitidae are newly recorded for New Brunswick, Canada. Additional records of the recently reported Calitys scabra (Thunberg and Ostoma fraterna (Randall are presented for the province. The record of O. fraterna is the first recent record of this species from New Brunswick. Additional New Brunswick records of the thaneroclerine, Zenodosus sanguineus (Say, are given, indicting that this species is common and widespread in the province. One species of Cleridae, Cymatodera bicolor (Say, is newly reported from New Brunswick, and the adventive Thanasimus formicarius Linnaeus is newly recorded from Nova Scotia and the Maritime provinces. Attalus morulus (LeConte and Dolichosoma foveicolle (Kirby, family Melyridae, are reported for the first time for New Brunswick and the Maritime provinces. Collection, habitat data, and distribution maps are presented for these species.

  18. Effects of steam pretreatment and co-production with ethanol on the energy efficiency and process economics of combined biogas, heat and electricity production from industrial hemp

    OpenAIRE

    Barta, Zsolt; Kreuger, Emma; Björnsson, Lovisa

    2013-01-01

    Background The study presented here has used the commercial flow sheeting program Aspen Plus™ to evaluate techno-economic aspects of large-scale hemp-based processes for producing transportation fuels. The co-production of biogas, district heat and power from chopped and steam-pretreated hemp, and the co-production of ethanol, biogas, heat and power from steam-pretreated hemp were analysed. The analyses include assessments of heat demand, energy efficiency and process economics in terms of an...

  19. Mathematical modeling of control system for the experimental steam generator

    OpenAIRE

    Podlasek Szymon; Lalik Krzysztof; Filipowicz Mariusz; Sornek Krzysztof; Kupski Robert; Raś Anita

    2016-01-01

    A steam generator is an essential unit of each cogeneration system using steam machines. Currently one of the cheapest ways of the steam generation can be application of old steam generators came from army surplus store. They have relatively simple construction and in case of not so exploited units – quite good general conditions, and functionality of mechanical components. By contrast, electrical components and control systems (mostly based on relay automatics) are definitely obsolete. It is...

  20. Steam Allocation Plan Considering Production and Electricity Generation%考虑生产与发电的蒸汽配置计划问题

    Institute of Scientific and Technical Information of China (English)

    张小雷; 张颜颜; 唐立新

    2012-01-01

    如何提高蒸汽系统整体的运行效率,减少蒸汽的放散损失,对于钢铁企业的节能减排、降低吨钢成本意义重大.针对蒸汽系统中不同类型的汽源设备运行方式差别较大的特点,以某大型钢铁企业蒸汽系统的实际运行为背景,建立了多汽源、多用户、多产品、分时的动态配置线性规划模型.该模型将不同汽源设备组成的系统作为一个整体进行研究,以更实际更直观的蒸汽发电量最大为目标,并利用约束从客观上保证了余热汽源的充分利用.最后根据现场数据,利用CPLEX得到了最优解.%How to imorove the operating efficiency of whole steam system and reduce the steam diffuion loss are of great significance so as to save energy, reduce emission and reduce the cost of per ton iron. This paper develops a time sharing dynamic linear programming model with multi-steam-source, multi-customer and multi-product by considering the operating differences of various steam source equipments in the steam system and using a real operation of steam system in an iron & steel enterprise as background. The model considers the combined system of different steam source facilities as a whole system. A practical and direct object of maximizing the steam electriciy generation is adopted, and the full use of the residual steam sources is guaranteed by constraint conditions. Finally, CPLEX is adopted to obtain the optimal solution based on the on-the-spot data.

  1. Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446). Supplement No. 7

    International Nuclear Information System (INIS)

    Supplement 7 to the Safety Evaluation Report for the Texas Utilities Electric Company application for a license to operate Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445, 50-446), located in Somervell County, Texas, has been jointly prepared by the Office of Nuclear Reactor Regulation and the Comanche Peak Technical Review of the US Nuclera Regulatory Commission. This supplement provides the results of the staff's evaluation and resolution of approximately 80 technical concerns and allegations in the areas of Electric/Instrumentation and Test Programs regarding construction and plant readiness testing practices at the Comanche Peak facility. Issues raised during Atomic Safety and Licensing Board hearings will be dealt with in future supplements to the Safety Evaluation Report

  2. Doing Local History: A Case Study of New Brunswick, New Jersey

    Science.gov (United States)

    Marino, Michael P.; Crocco, Margaret Smith

    2012-01-01

    This article provides a methodology that teachers can use to incorporate themes and ideas related to local history in their classrooms. Using the city of New Brunswick, New Jersey as a case study, the article offers different approaches that allow local history to be connected to wider themes in American history. The focus here on a small,…

  3. Women's Access to Training in New Brunswick. Training Matters: Working Paper Series.

    Science.gov (United States)

    McFarland, Joan

    A gender-based analysis of training that focuses on barriers to women because of changes in the availability of sponsorship leads to the conclusion that training programs for women in New Brunswick have been spotty at best. Women's training has occurred during the 1970s, 1980s, and 1990s under the aegis of the Canadian Manpower Training Program,…

  4. Hydrographic observations off Savannah and Brunswick, Georgia, March, May and September 1977 and January 1978

    Energy Technology Data Exchange (ETDEWEB)

    Singer, J J; Atkinson, L P; Chandler, W S; Bishop, S S

    1978-01-01

    Seasonal onshore-offshore sections were run in March, May and September 1977 and January 1978 off Savannah and Brunswick, Georgia. In each instance upwelling was observed at the shelf break with significant nutrient fluxes into the surface and/or shelf waters. There are indications that eddies may have been responsible for some of these observations.

  5. Environmental contaminants in golden shiners from Picnic Pond, U.S. Naval Air Station, Brunswick, Maine

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — On July 25, 1995, the U.S. Fish and Wildlife Service conducted a contaminant survey of fish from Picnic Pond on the U.S. Naval Air Station in Brunswick, Maine...

  6. The Ciidae (Coleoptera) of New Brunswick, Canada: New records and new synonyms.

    Science.gov (United States)

    Lopes-Andrade, Cristiano; Webster, Reginald P; Webster, Vincent L; Alderson, Chantelle A; Hughes, Cory C; Sweeney, Jon D

    2016-01-01

    The Ciidae of New Brunswick, Canada are reviewed. Seventeen species are recorded for New Brunswick, including the following 10 species that are newly recorded for the province: Ceracis singularis (Dury), Ceracis thoracicornis (Ziegler), Cis angustus Hatch, Cis fuscipes Mellié, Cis horridulus Casey, Cis striatulus Mellié, Dolichocis laricinus (Mellié), Malacocis brevicollis (Casey), Orthocis punctatus (Mellié), and Plesiocis cribrum Casey. Additional locality data are provided for the following species previously known from the province: Cis americanus Mannerheim, Cis creberrimus Mellié, Cis levettei (Casey), Cis submicans Abeille de Perrin, Dolichocis manitoba Dury, Hadreule elongatula (Gyllenhal), and Octotemnus glabriculus (Gyllenhal). Seven synonyms are proposed here; Cis pistoria Casey with Cis submicans Abeille de Perrin; Cis fraternus Casey, Cis macilentus Casey and Cis striolatus Casey with Cis striatulus Mellié; Dolichocis indistinctus Hatch with Dolichocis laricinus (Mellié); and Octotemnus denudatus Casey and Octotemnus laevis Casey with Octotemnus glabriculus (Gyllenhal). Lindgren funnel traps provided the majority of specimens for 15 of the 17 species reported from New Brunswick and were the sole source of specimens for seven of the 10 species newly reported here, suggesting they are a very useful tool for sampling Ciidae in the forests of New Brunswick. PMID:27110172

  7. Turbine cycle thermal performance analysis according to replacement of steam generator for Kori unit 1

    International Nuclear Information System (INIS)

    After replacement of steam generator of Kori unit 1, electrical output is recovered with increasing of main steam presure and main steam flowrate. For this review, heat balance calculation and performance data review is conducted by using PEPSE code. The Increasement of electrical output is about 10MW. The energy theory is used for analysis of electrical power improvement. As a result, the amount of energy input by main steam is more than amount of irreversivility on this turbine cycle

  8. Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446). Supplement No. 8

    International Nuclear Information System (INIS)

    Supplement 8 to the Safety Evaluation Report for the Texas Utilities Electric Company application for a license to operate Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445, 50-446), located in Somervell County, Texas, has been jointly prepared by the Office of Nuclear Reactor Regulation and the Comanche Peak Technical Review Team of the US Nuclear Regulatory Commission. This Supplement provides the results of the staff's evaluation and resolution of approximately 80 technical concerns and allegations relating to civil and structural and miscellaneous issues regarding construction and plant readiness testing practices at the Comanche Peak facility. Issues raised during recent Atomic Safety and Licensing Board hearings will be dealt with in future supplements to the Safety Evaluation Report

  9. 76 FR 8720 - Record of Decision for the Disposal and Reuse of Naval Air Station Brunswick, ME

    Science.gov (United States)

    2011-02-15

    ... Office (PMO) Northeast, 4911 Broad Street, Building 679, Philadelphia, Pennsylvania 19112-1303; telephone... viewing on the Navy's BRAC PMO Web site at http://www.bracpmo.navy.mil/BrunswickEIS.aspx along with...

  10. Toxicity tests and sediment chemistry at Site 9 (Neptune Drive Disposal Site) - U.S. Naval Air Station, Brunswick, Maine

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — During a remedial investigation of the U.S. Naval Air Station Superfund Site in Brunswick, Maine (NASB), elevated concentrations of total polycyclic aromatic...

  11. Methane reforming with fast nuclear reactor steam

    International Nuclear Information System (INIS)

    The paper considers the concept of utilizing nuclear fast reactor (FR) with a sodium coolant for methane steam reforming. Steam conditions of a power FR, e.g. the BN-600 now operating in Russia: steam pressure P=13.2 MPa and steam temperature T=500degC, do not absolutely comply with the catalytic reactor working parameters, which produces a synthetic gas (syngas), a mix of hydrogen and carbon oxide. In this connection, the present paper addresses a possibility of utilizing steam produced in one of three independent the BN-600 loops in an amount of 640 t/h for preparing a gas-steam mixture with T=500degC and its additional heating in a converter up to the operating temperature, T=850degC, at the expense of natural gas burning or electrical energy supplying. In this case, the fraction of burned natural gas burning or electrical energy supplying. In this case, the fraction of burned natural gas significantly decreases. It is estimated that steam parameters of the BN-600 afford to obtain ∼3·105 nm3/h of hydrogen. It is also considered a concept of nuclear heat transfer to remote regions to be achieved with the aid of syngas incoming from the converter, its cooling further and transmitting through a pipeline to the place of its utilization, where it is restored into methane with the heat extraction. (author)

  12. Steam Digest 2001

    Energy Technology Data Exchange (ETDEWEB)

    2002-01-01

    Steam Digest 2001 chronicles BestPractices Program's contributions to the industrial trade press for 2001, and presents articles that cover technical, financial and managerial aspects of steam optimization.

  13. More than wind: evaluating renewable energy opportunities for First Nations in Nova Scotia and New Brunswick

    Energy Technology Data Exchange (ETDEWEB)

    Campbell, Diana [MREM Canada (Canada)

    2011-04-15

    The Nova Scotia and New Brunswick governments have committed to developing the renewable energy sector in the coming years. However, due to a lack of information, First Nations are not familiar with renewable energy technologies and their economic opportunities. The aim of this paper is to provide First Nations with information on the different renewable energies. It has been noticed that First Nations have not seized either the opportunities offered by the Nova Scotia feed-in tariff nor the New Brunswick community energy policy and an overview of these policies is provided. In addition, information on renewable energy technologies is presented along with potential opportunities specific to each First Nation in the 2 provinces. This paper provides First Nations with useful information on renewable energy and with recommendations for immediate and long term action; it is expected that this document will result in a greater involvement of First Nations in the renewable energy sector.

  14. Analysis of infectious laryngotracheitis virus isolates from Ontario and New Brunswick by the polymerase chain reaction.

    Science.gov (United States)

    Alexander, H S; Key, D W; Nagy, E

    1998-01-01

    The polymerase chain reaction (PCR) was used to amplify DNA of infectious laryngotracheitis virus (ILTV) isolates obtained from field specimens. The examined 47 samples included 37 isolates representing 35 cases of infectious laryngotracheitis from Ontario and 10 isolates originating from 10 field cases in New Brunswick. The viruses were grown in either embryonated chicken eggs or cell culture, the DNA extracted and amplified using primers designed from the sequence information of a 1.1 kb BamHI fragment of the Ontario 1598 ILTV strain. Thirty-four of the Ontario isolates and all of the New Brunswick isolates were amplified successfully. This suggests that the selected primers would be useful for the majority of the isolates encountered in outbreaks of ILTV. Images Figure 1. Figure 2. PMID:9442943

  15. Analysis of infectious laryngotracheitis virus isolates from Ontario and New Brunswick by the polymerase chain reaction.

    OpenAIRE

    Alexander, H S; Key, D.W.; Nagy, E.

    1998-01-01

    The polymerase chain reaction (PCR) was used to amplify DNA of infectious laryngotracheitis virus (ILTV) isolates obtained from field specimens. The examined 47 samples included 37 isolates representing 35 cases of infectious laryngotracheitis from Ontario and 10 isolates originating from 10 field cases in New Brunswick. The viruses were grown in either embryonated chicken eggs or cell culture, the DNA extracted and amplified using primers designed from the sequence information of a 1.1 kb Ba...

  16. Sodium-water wastage and reactions program performed by general electric in support of the US. AEC LMFBR steam generator development

    International Nuclear Information System (INIS)

    This paper constitutes an interim report on the sodium-water reaction programs performed, using the GE-SOWAT, GE-SMALL LEAK BEHAVIOR RIG, and GE-PTTR facilities in support of LMFBR steam generator development and its application to the Clinch River Breeder Reactor Plant. Test data from these rigs are presented, including wastage data as a function of water injection rate, sodium temperature, and orifice geometry. Initial results for self-wastage of defects under prototypical conditions, and from proof-of-principle tests of a protected heat transfer tube concept are also presented. An analytical basis for wastage phenomena is suggested. (author)

  17. Strategies for steam

    International Nuclear Information System (INIS)

    This article is a review of worldwide developments in the steam turbine and heat recovery steam generator markets. The Far East is driving the market in HRSGs, while China is driving the market in orders placed for steam turbine prime movers. The efforts of several major suppliers are discussed, with brief technical details being provided for several projects

  18. Steam Digest Volume IV

    Energy Technology Data Exchange (ETDEWEB)

    None

    2004-07-01

    This edition of the Steam Digest is a compendium of 2003 articles on the technical and financial benefits of steam efficiency, presented by the stakeholders of the U.S. Department of Energy's BestPractices Steam effort.

  19. The Invisibility of Steam

    Science.gov (United States)

    Greenslade, Thomas B., Jr.

    2014-01-01

    Almost everyone "knows" that steam is visible. After all, one can see the cloud of white issuing from the spout of a boiling tea kettle. In reality, steam is the gaseous phase of water and is invisible. What you see is light scattered from the tiny droplets of water that are the result of the condensation of the steam as its temperature…

  20. Nuclear process steam for industry

    International Nuclear Information System (INIS)

    A joint industrial survey funded by the Bruce County Council, the Ontario Energy Corporation and Atomic Energy of Canada Limited was carried out with the cooperation of Ontario Hydro and the Ontario Ministry of Industry and Tourism. Its objective was to identify and assess the future needs and interest of energy-intensive industries in an Industrial Energy Park adjacent to the Bruce Nuclear Power Development. The Energy Park would capitalize on the infrastructure of the existing CANDU reactors and Ontario Hydro's proven and unique capability to produce steam, as well as electricity, at a cost currently about half that from a comparable coal-fired station. Four industries with an integrated steam demand of some 1 x 106 lb/h were found to be prepared to consider seriously the use of nuclear steam. Their combined plants would involve a capital investment of over $200 million and provide jobs for 350-400 people. The high costs of transportation and the lack of docking facilities were considered to be the major drawbacks of the Bruce location. An indication of steam prices would be required for an over-all economic assessment

  1. New Brunswick Site annual environmental report for calendar year 1991, New Brunswick, New Jersey. Formerly Utilized Sites Remedial Action Program (FUSRAP)

    Energy Technology Data Exchange (ETDEWEB)

    1992-09-01

    This document describes the environmental monitoring program at the New Brunswick Site (NBS) and surrounding area, implementation of the program, and monitoring results for 1991. The site, near New Brunswick,, New Jersey, is a 5.6-acre vacant, fenced, and grass-covered area. Environmental monitoring of NBS began in 1981 when the site was part of the US Department of Energy`s (DOE) Surplus Facilities Management Program. In 1990 responsibility for NBS was transferred to the Formerly Utilized Sites Remedial Action Program (FUSP.4P). FUSRAP is a DOE program to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the,early years of the nation`s atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The environmental monitoring program at NBS includes sampling networks for radon and thoron in air; external gamma radiation exposure; and radium-226, radium-228, thorium-228, thorium-230, thorium-232, americium-241, cesium-137, plutonium-239, and total uranium in surface water, sediment, and groundwater. Several nonradiological parameters are also measured in groundwater, surface water, and sediments. Monitoring results are compared with applicable Environmental Protection Agency standards, DOE derived concentration guides, dose limits, and other requirements in DOE orders. Environmental standards are established to protect public health and the environment.

  2. Integrated Gasification SOFC Plant with a Steam Plant

    DEFF Research Database (Denmark)

    Rokni, Masoud; Pierobon, Leonardo

    2011-01-01

    steam plant is presented and studied. The plant is called as IGSS (Integrated Gasification SOFC Steam plant). Different systems layouts are presented and investigated. Electrical efficiencies up to 56% are achieved which is considerably higher than the conventional integrated gasification combined......A hybrid Solid Oxide Fuel Cell (SOFC) and Steam Turbine (ST) plant is integrated with a gasification plant. Wood chips are fed to the gasification plant to produce biogas and then this gas is fed into the anode side of a SOFC cycle to produce electricity and heat. The gases from the SOFC stacks...... enter into a burner to burn the rest of the fuel. The offgases after the burner are now used to generate steam in a Heat Recovery Steam Generator (HRSG). The generated steam is expanded in a ST to produce additional power. Thus a triple hybrid plant based on a gasification plant, a SOFC plant and a...

  3. Safety evaluation report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446): Supplement No. 21

    International Nuclear Information System (INIS)

    Supplement 21 to the Safety Evaluation Report related to the operation of the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement reports the status of certain issues that had not been resolved when the Safety Evaluation Report and Supplements 1, 2, 3, 4, 6, and 12 to that report were published. This supplement also lists the new issues that have been identified since Supplement 12 was issued and includes the evaluations for licensing items resolved in this interim period. 21 refs

  4. Utilization of high CO2 content formation gas for steam and electricity generation; Aprovechamiento del gas de formacion con alto contenido de CO2 para generacion de vapor y electricidad

    Energy Technology Data Exchange (ETDEWEB)

    Villagomez, Paul; Lamino, Marcelo; Jacome, Jose; Pastor, Santiago [EcuadorTLC, Quito (Ecuador). Grupo PETROBRAS

    2008-07-01

    Ecuador TLC SA, as part of the PETROBRAS Group, respecting its mission to act safe, cost-effectiveness, social and environmental responsibility, currently operates an oil production project in the Ecuatorian Amazon, known as Block 18. In Block 18, the process of gas burning is response for launch approximately 10 MMSCF of the gas associated with 77% CO2 in the environment. For this reason it was built a centralized power generation plants (PGE), of 17.38 MW, taking advantage of the gas with 77% CO2 from boilers to burn it, using it as a source of heat in a combined cycle steam turbines, generating electricity. This project is environmentally efficient with reduced emissions of CO2 and as reducing fuel costs to zero. The results of CO2 reduction is a corporate goal of PETROBRAS and this project will contribute to reducing CO2 emissions by approximately 400,000 Ton over the life of the project.

  5. Nuclear steam-reheat options: Russian experience

    International Nuclear Information System (INIS)

    Concepts of nuclear reactors cooled with water at supercritical pressures were studied as early as the 1950s and 1960s in the USA and Russia. After a 30-year break, the idea of developing nuclear reactors cooled with SuperCritical Water (SCW) became attractive again as the ultimate development path for water cooling. The main objectives of using SCW in nuclear reactors are: 1) to increase the thermal efficiency of modern Nuclear Power Plants (NPPs) from 30 - 35% to about 45 - 50%, and 2) to decrease capital and operational costs and hence decrease electrical-energy costs. SCW NPPs will have much higher operating parameters compared to modern NPPs (pressure about 25 MPa and outlet temperature up to 625oC), and a simplified flow circuit, in which steam generators, steam dryers, steam separators, etc., can be eliminated. Also, higher SCW temperatures allow direct thermo-chemical production of hydrogen at low cost due to increased reaction rates. To achieve higher thermal efficiency a nuclear steam reheat has to be introduced inside a reactor. Currently, all supercritical turbines at thermal power plants have a steam-reheat option. In the 60's and 70's, Russia and some other countries have developed and implemented the nuclear steam reheat at subcritical-pressure in experimental reactors. There are some papers, mainly published in the open Russian literature, devoted to this important experience. Analysis of the Russian literature on nuclear steam-reheat option is presented in the current paper. (author)

  6. Method for operating a steam turbine of the nuclear type with electronic reheat control of a cycle steam reheater

    International Nuclear Information System (INIS)

    An electronic system is provided for operating a nuclear electric power plant with electronic steam reheating control applied to the nuclear turbine system in response to low pressure turbine temperatures, and the control is adapted to operate in a plurality of different automatic control modes to control reheating steam flow and other steam conditions. Each of the modes of control permit turbine temperature variations within predetermined constraints and according to predetermined functions of time. (Official Gazette)

  7. Steam generator specification design transients

    Energy Technology Data Exchange (ETDEWEB)

    Stevenson, D.H.

    1978-05-12

    This LTR documents LOFT Plant operational, upset, and emergency transients, and pressure and temperature conditions as generated by the LOFT Plant Dynamic analysis model of the primary system for use in steam generator specification. The results of this LTR have been supplemented by succeeding efforts as follows: FSAR analysis - (a) loss of load during full power operation, (b) loss of primary pump electrical power, and (c) loss of site power; and LOFT maneuvering analysis - (a) +-10% step change in steam flow, and (b) manual reactor trip. The initial plant conditions considered may differ from this LTR plant conditions. Items are outlined to document in this LTR other analyses which cover the same plant transients. 53 figs., 1 tab.

  8. The Electrical Design Technology and Practices of Saturated Steam Cogeneration Station in Dongling Zn Industry Co., Ltd.%东岭锌业饱和蒸汽余热发电站电气设计技术与实践

    Institute of Scientific and Technical Information of China (English)

    李元宏

    2013-01-01

      利用锌冶炼生产工艺外富裕的饱和蒸汽,采用低压饱和蒸汽发电技术进行发电是一种新型的先进技术。采用技术先进的饱和蒸汽补汽凝汽式汽轮发电机组,饱和蒸汽利用率高达95%以上,余热发电站电气设计有其独特的一些特点。%Through using the rich saturated steam of zinc smelting production technology, adopting low pressure saturated steam power generation technology to generate electricity is a new type of advanced technology. If we adopt the saturated steam supplement and condensing steam turbonator with advanced technology, the saturated steam utilization rate will be above 95%, and the electrical design of waste heat power station has its unique characteristics.

  9. Mathematical modeling of control system for the experimental steam generator

    Directory of Open Access Journals (Sweden)

    Podlasek Szymon

    2016-01-01

    Full Text Available A steam generator is an essential unit of each cogeneration system using steam machines. Currently one of the cheapest ways of the steam generation can be application of old steam generators came from army surplus store. They have relatively simple construction and in case of not so exploited units – quite good general conditions, and functionality of mechanical components. By contrast, electrical components and control systems (mostly based on relay automatics are definitely obsolete. It is not possible to use such units with cooperation of steam bus or with steam engines. In particular, there is no possibility for automatically adjustment of the pressure and the temperature of the generated steam supplying steam engines. Such adjustment is necessary in case of variation of a generator load. The paper is devoted to description of improvement of an exemplary unit together with construction of the measurement-control system based on a PLC. The aim was to enable for communication between the steam generator and controllers of the steam bus and steam engines in order to construction of a complete, fully autonomic and maintenance-free microcogeneration system.

  10. Mathematical modeling of control system for the experimental steam generator

    Science.gov (United States)

    Podlasek, Szymon; Lalik, Krzysztof; Filipowicz, Mariusz; Sornek, Krzysztof; Kupski, Robert; Raś, Anita

    2016-03-01

    A steam generator is an essential unit of each cogeneration system using steam machines. Currently one of the cheapest ways of the steam generation can be application of old steam generators came from army surplus store. They have relatively simple construction and in case of not so exploited units - quite good general conditions, and functionality of mechanical components. By contrast, electrical components and control systems (mostly based on relay automatics) are definitely obsolete. It is not possible to use such units with cooperation of steam bus or with steam engines. In particular, there is no possibility for automatically adjustment of the pressure and the temperature of the generated steam supplying steam engines. Such adjustment is necessary in case of variation of a generator load. The paper is devoted to description of improvement of an exemplary unit together with construction of the measurement-control system based on a PLC. The aim was to enable for communication between the steam generator and controllers of the steam bus and steam engines in order to construction of a complete, fully autonomic and maintenance-free microcogeneration system.

  11. Characterization of a steam plasma jet at atmospheric pressure

    International Nuclear Information System (INIS)

    An atmospheric steam plasma jet generated by an original dc water plasma torch is investigated using electrical and spectroscopic techniques. Because it directly uses the water used for cooling electrodes as the plasma-forming gas, the water plasma torch has high thermal efficiency and a compact structure. The operational features of the water plasma torch and the generation of the steam plasma jet are analyzed based on the temporal evolution of voltage, current and steam pressure in the arc chamber. The influence of the output characteristics of the power source, the fluctuation of the arc and current intensity on the unsteadiness of the steam plasma jet is studied. The restrike mode is identified as the fluctuation characteristic of the steam arc, which contributes significantly to the instabilities of the steam plasma jet. In addition, the emission spectroscopic technique is employed to diagnose the steam plasma. The axial distributions of plasma parameters in the steam plasma jet, such as gas temperature, excitation temperature and electron number density, are determined by the diatomic molecule OH fitting method, Boltzmann slope method and Hβ Stark broadening, respectively. The steam plasma jet at atmospheric pressure is found to be close to the local thermodynamic equilibrium (LTE) state by comparing the measured electron density with the threshold value of electron density for the LTE state. Moreover, based on the assumption of LTE, the axial distributions of reactive species in the steam plasma jet are estimated, which indicates that the steam plasma has high chemical activity.

  12. Fractured-aquifer hydrogeology from geophysical logs: Brunswick group and Lockatong Formation, Pennsylvania

    Science.gov (United States)

    Morin, R.H.; Senior, L.A.; Decker, E.R.

    2000-01-01

    The Brunswick Group and the underlying Lockatong Formation are composed of lithified Mesozoic sediments that constitute part of the Newark Basin in southeastern Pennsylvania. These fractured rocks form an important regional aquifer that consists of gradational sequences of shale, siltstone, and sandstone, with fluid transport occurring primarily in fractures. An extensive suite of geophysical logs was obtained in seven wells located at the borough of Lansdale, Pennsylvania, in order to better characterize the areal hydrogeologic system and provide guidelines for the refinement of numerical ground water models. Six of the seven wells are approximately 120 m deep and the seventh extends to a depth of 335 m. Temperature, fluid conductivity, and flowmeter logs are used to locate zones of fluid exchange and to quantify transmissivities. Electrical resistivity and natural gamma logs together yield detailed stratigraphic information, and digital acoustic televiewer data provide magnetically oriented images of the borehole wall from which almost 900 fractures are identified. Analyses of the geophysical data indicate that the aquifer penetrated by the deep well can be separated into two distinct structural domains, which may, in turn, reflect different mechanical responses to basin extension by different sedimentary units: 1. In the shallow zone (above 125 m), the dominant fracture population consists of gently dipping bedding plane partings that strike N46??E and dip to the northwest at about 11 degrees. Fluid flow is concentrated in the upper 80 m along these subhorizontal fractures, with transmissivities rapidly diminishing in magnitude with depth. 2. The zone below 125 m marks the appearance of numerous high-angle fractures that are orthogonal to the bedding planes, striking parallel but dipping steeply southeast at 77 degrees. This secondary set of fractures is associated with a fairly thick (approximately 60 m) high-resistivity, low-transmissivity sandstone unit that

  13. Generator of steam plasma for gasification of solid fuels

    Science.gov (United States)

    An'shakov, A. S.; Urbakh, E. K.; Rad'ko, S. I.; Urbakh, A. E.; Faleev, V. A.

    2013-12-01

    A structural design of an electric-arc steam plasma torch (plasmatron) with copper tubular electrodes has been proposed and implemented. Operational parameters are determined for the stable generation of steam plasma. Experimental data are presented on the energy characteristics of the plasma generator with the capacity up to 100 kW.

  14. Improvement in using steam for electric generation at the Los Azufres, Mich., geothermal field; Mejora en el aprovechamiento del vapor para generar energia electrica en el campo geotermico de Los Azufres, Mich.

    Energy Technology Data Exchange (ETDEWEB)

    Torres Rodriguez, Marco A.; Flores Armenta, Magaly; Mendoza Covarrubias, Alfredo [Comision Federal de Electricidad, Gerencia de Proyectos Geotermoelectricos, Morelia, Michoacan (Mexico)]. E-mail: magaly.flores@cfe.gob.mx

    2010-01-15

    Commercial exploitation in the Los Azufres geothermal field, Michoacan, Mexico, started in 1982 when the first five backpressure-power units of 5-MW each were commissioned. Nowadays the installed capacity is 188 MW from 14 units: five in the South Zone fed by steam produced from 18 production wells plus two binary-cycle power units fed by residual brines; and seven in the North Zone with steam supplied by 22 production wells. There are seven backpressure-power units with high specific consumption [between 14.5 and 13.6 tons per hour of steam (t/h) per MW]. Three operate in the South Zone and four in the North Zone. This paper shows a way to achieve more efficient use of the geothermal resource by replacing the seven backpressure units, which have completed their useful lifetime-or are close to do it-with two, new condensing power units with lower specific consumption: one unit of 50 MW to be located in the North Zone and the other of 25 MW to be placed in the South Zone. No new wells need be drilled. In this way, the average specific consumption would be reduced to 8.8-7.2 t/h per MW (saving 47% of the steam), the income for electric generation would be increased and the steam-extraction rate would remain the same. [Spanish] En 1982 empezo la explotacion comercial del campo geotermico de Los Azufres, Mich., Mexico, con la instalacion y puesta en servicio de las primeras cinco unidades turbogeneradoras a contrapresion de 5 MW cada una. Actualmente la capacidad instalada es de 188 MW, con catorce unidades: cinco en la zona sur, alimentadas por el vapor de 18 pozos productores, mas dos unidades de ciclo binario que utilizan salmuera residual, y siete unidades en la zona norte, alimentadas por 22 pozos. Hay siete unidades a contrapresion con un consumo especifico elevado [entre 14.5 y 13.6 toneladas por hora (t/h) de vapor por MW], tres de las cuales se localizan en la zona sur y cuatro en la zona norte. En este documento se presenta un proyecto para hacer mas

  15. Steam turbine and generator system for ABWR

    International Nuclear Information System (INIS)

    The advanced boiling water reactor (ABWR), with a number of superior characteristics including high reliability and large capacity, has been developed. The first ABWR units have been realized as Units No. 6 and 7 of The Tokyo Electric Power Co., Inc.'s Kashiwazaki-Kariwa Nuclear Power Station. Based on its considerable experience in the construction and maintenance of nuclear steam turbine and generator systems, Toshiba has developed the world's largest class steam turbine as well as generator systems with high efficiency, high reliability, small turbine buildings and a short construction period, and has been constructing Kashiwazaki-Kariwa Unit No. 7 jointly with General Electric Co. of the United States. We have been developing additional techniques to further improve the efficiency and maintainability of the steam turbine and generator system of the next ABWR plant, based on techniques that have been verified with fossil-fuel power plants. (author)

  16. An overview of the applications for early warning and mapping of the flood events in New Brunswick

    DEFF Research Database (Denmark)

    Mioc, Darka; McGillivray, E.; Anton, F.;

    2014-01-01

    This paper gives an overview of the on-line flood warning implementation in the province of New Brunswick, Canada. The on-line flood warning applications are available via the “River Watch” website provided by the New Brunswick Department of Environment. Advanced GIS technology combined with...... hydrological modelling, provide a mapping and visualization tool that can be used by emergency managers and the general public to predict possible flood zones. The applications developed for “River Watch” support the processing of large amounts of digital terrain and hydrological data, which are then....... The searchable historical database containing reports about the impact of past floods and estimated damages provides a valuable insight into the past of the province of New Brunswick and the motivation for development of the system for flood prediction and management....

  17. New Staphylinidae (Coleoptera records with new collection data from New Brunswick and an addition to the fauna of Quebec: Staphylininae

    Directory of Open Access Journals (Sweden)

    Reginald Webster

    2012-04-01

    Full Text Available Forty-four species of Staphylininae are newly reported from New Brunswick, bringing the total number of species known from the province to 126. Quedius criddlei (Casey is reported for the first time from Quebec. Bisnius cephalotes (Gravenhorst is removed from the faunal list of New Brunswick due to a lack of supporting voucher specimens. Additional locality data are presented for seven species either recently recorded from the province or with few previous records and little habitat data. We provide the first documented records of Atrecus americanus (Casey, Quedius erythrogaster Mannerheim, Quedius labradorensis labradorensis Smetana, Quedius plagiatus (Mannerheim, and Neobisnius terminalis (LeConte from New Brunswick. Collection and habitat data are presented and discussed for all species.

  18. Wood supply : what bioenergy resources are available as harvest residue and non-merchantable wood in New Brunswick?

    International Nuclear Information System (INIS)

    This paper examines resources available for bioenergy production in New Brunswick. An estimate of New Brunswick harvest levels, based on New Brunswick Forest Products Association web site figures was presented. Private wood lots harvest levels were also provided, with all estimates based on volume per year. Market conditions were discussed, with an emphasis on the dictates of price and availability for private wood lot owners. Market conditions and unused volume statistics were discussed. Various forest management options include the use of veneer, saw log, stud wood and pulp wood. Details of bioenergy percentages and potential were presented and general silviculture issues were discussed. It was concluded that many of the trade-offs of bioenergy involve placing more demands on forests, and that purchase prices will increasingly dictate volumes obtained from private wood lots. tabs, figs

  19. Unsteady coupling effects of wet steam in steam turbines flows

    International Nuclear Information System (INIS)

    In addition to conventional turbomachinery problems, both the behavior and performances of steam turbines are highly dependent on the vapour thermodynamic state and the presence of a liquid phase. EDF, the main French electricity producer, is interested in further developing its' modelling capabilities and expertise in this area to allow for operational studies and long-term planning. This PhD thesis explores the modelling of wetness formation and growth in a steam turbine and an analysis of the coupling between the liquid phase and the main flow unsteadiness. To this end, the work in this thesis took the following approach. Wetness was accounted for using a homogeneous model coupled with transport equations to take into account the effects of non-equilibrium phenomena, such as the growth of the liquid phase and nucleation. The real gas attributes of the problem demanded adapted numerical methods. Before their implementation in the 3D elsA solver, the accuracy of the chosen models was tested using a developed one-dimensional nozzle code. In this manner, various condensation models were considered, including both poly-dispersed and monodispersed behaviours of the steam. Finally, unsteady coupling effects were observed from several perspectives (1D, 1D - 3D, 3D), demonstrating the ability of the method of moments to sustain unsteady phenomena which were not apparent in a simple monodispersed model. (author)

  20. Integrated Gasification SOFC Plant with a Steam Plant

    OpenAIRE

    Rokni, Masoud; Pierobon, Leonardo

    2011-01-01

    A hybrid Solid Oxide Fuel Cell (SOFC) and Steam Turbine (ST) plant is integrated with a gasification plant. Wood chips are fed to the gasification plant to produce biogas and then this gas is fed into the anode side of a SOFC cycle to produce electricity and heat. The gases from the SOFC stacks enter into a burner to burn the rest of the fuel. The offgases after the burner are now used to generate steam in a Heat Recovery Steam Generator (HRSG). The generated steam is expanded in a ST to prod...

  1. Nuclear steam generator

    International Nuclear Information System (INIS)

    A nuclear steam generator has a blowdown pump arranged to pump water from the blowdown line through a filter for return to the steam generator. The piping is arranged so that the pump may operate to reverse the direction of pumping through the blowdown line whereby reverse circulation may be established during wet lay up of the steam generator. A blower is arranged to withdraw nitrogen from an upper elevation in the steam generator and inject the nitrogen into the blowdown line in combination with the pumped reverse circulation during wet lay up. (author)

  2. Redesign of Steam Strainer

    OpenAIRE

    Jannesson, Ann

    2008-01-01

    This thesis was done at Siemens Industrial Turbomachinery AB in Finspång. Placed in the inlet to a steam turbine is a filter, a steam strainer, which separates particles and larger objects from the steam. These particles and objects will cause solid particle erosion in the actual turbine if they pass by. The strainer is exposed to large pressure drops when clogged, i.e., static loads which require a good creep resistance in the material. The temperature of the steam in the turbines is increas...

  3. Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446). Supplement No. 11

    International Nuclear Information System (INIS)

    Supplement 11 to the Safety Evaluation Report for the Texas Utilities Electric Company application for a license to operate Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445, 50-446), located in Somervell County, Texas, has been jointly prepared by the Office of Nuclear Reactor Regulation and the Comanche Peak Technical Review Team (TRT) of the US Nuclear Regulatory Commission (NRC) and is in two parts. Part 1 (Appendix 0) of this supplement provides the results of the TRT's evaluation of approximately 124 concerns and allegations relating specifically to quality assurance and quality control (QA/QC) issues regarding construction proctices at the Comanche Peak facility. Part 2 (Appendix P) contains an overall summary and conclusion of the QA/QC aspects of the NRC Technical Review Team efforts as reported in supplemental Safety Evaluation Report SERs 7, 8, 9, and 10. Since QA/QC issues are also contained in each of the other supplements, the TRT considered that such a summary and conclusion from all supplements was necessary for a complete TRT description of QA/QC activities at Comanche Peak

  4. An Isothermal Steam Expander for an Industrial Steam Supplying System

    OpenAIRE

    Chen-Kuang Lin; Guang-Jer Lai; Yoshiyuki Kobayashi; Masahiro Matsuo; Min-Chie Chiu

    2015-01-01

    Steam is an essential medium used in the industrial process. To ensure steam quality, small and middle scale boilers are often adopted. However, because a higher steam pressure (compared to the necessary steam pressure) is generated, the boiler’s steam pressure will be reduced via a pressure regulator before the steam is directed through the process. Unfortunately, pressure is somewhat wasted during the reducing process. Therefore, in order to promote energy efficiency, a pressure regulator i...

  5. Stage 1: Expression of interest and consultation document for natural gas distribution in New Brunswick

    International Nuclear Information System (INIS)

    The New Brunswick government intends to award a franchise to establish natural gas distribution in the province. To this end, the province wishes to invite bids from qualified entities to establish gas distribution facilities. The province will select the preferred bidder(s) through a two-stage competitive bidding process. This document details the province's policy objectives, questions and issues to be addressed in stage 1 of the process, and the schedule for the process. Appendices include copies of relevant provincial statutes and regulations

  6. The development of 1530 MW steam turbine for Advanced PWR

    International Nuclear Information System (INIS)

    MITSUBISHI has been manufacturing 27 nuclear steam turbines and total output is over 20,000 MW since the 1970 first delivery of nuclear steam turbine. Based on these our successful experiences, MITSUBISHI is making a continuous effort to develop the most modern steam turbine with the lager capacity, higher efficiency and higher reliability. And now, the first Advanced PWR is being planned to be built at Tsuruga No.3 and No.4 by Japan Atomic Power Co. as the largest plant with an electric power of about 1530 MW. To apply this Advanced PWR plants, we are going forward planing and developing the largest capacity nuclear steam turbine. This paper shows the key technologies of target capacity nuclear steam turbine such as 54 inches low pressure last blade, and the advanced technologies to realize high performance and high reliability steam turbine. (author)

  7. STEAM INJECTION TREATABILITY STUDIES

    Science.gov (United States)

    The approach used is to inject steam into 1- dimensional columns that have been packed with contaminated soil from the site. Temperatures in the system are monitored aliquots of the effluent collected for analysis. A sample of the initial soil, the final steamed soil, the effluen...

  8. Replacement nuclear steam generators

    International Nuclear Information System (INIS)

    This paper reviews past and current practices in the replacement of nuclear steam generators. Plants where steam generator replacement has occurred are reviewed to see what changes have been made, and how the evolving technology has significantly reduced outage time and man-rem exposures. Current preferences in design and material are reviewed. 3 refs., 3 tabs., 2 figs

  9. Study of Constant Voltage Control on Small Steam Generator Based on PID Algorithm

    Directory of Open Access Journals (Sweden)

    Yanjun Xiao

    2014-03-01

    Full Text Available The object of this study is a kind of 3 kW small steam generator, which can recover waste heat through making use of 0.1~0.3 MPa steam. This can exploit secondary energy efficiently. The electricity generated can be commonly used as factory lighting, heating, fan and emergency power supply. But the generation voltage of the existed steam turbine is instable, especially when the steam pressure and the load of the generator changes suddenly. This can pose a threat to electrical safety and greatly limit the market of small steam generator. In this study, PID control algorithm is used to control the amount of steam into the turbine of generator system. And the closed-loop control system can make a real-time feedback regulation to the steam, so that the generator voltage can be stable. The user's electrical safety requirements are satisfied as well.

  10. An Isothermal Steam Expander for an Industrial Steam Supplying System

    Directory of Open Access Journals (Sweden)

    Chen-Kuang Lin

    2015-01-01

    Full Text Available Steam is an essential medium used in the industrial process. To ensure steam quality, small and middle scale boilers are often adopted. However, because a higher steam pressure (compared to the necessary steam pressure is generated, the boiler’s steam pressure will be reduced via a pressure regulator before the steam is directed through the process. Unfortunately, pressure is somewhat wasted during the reducing process. Therefore, in order to promote energy efficiency, a pressure regulator is replaced by a steam expander. With this steam expander, the pressure will be transformed into mechanical energy and extracted during the expansion process. A new type of isothermal steam expander for an industrial steam supplying system will be presented in the paper. The isothermal steam expander will improve the energy efficiency of a traditional steam expander by replacing the isentropic process with an isothermal expansion process. With this, steam condensation will decrease, energy will increase, and steam quality will be improved. Moreover, the mathematical model of the isothermal steam expander will be established by using the Schmidt theory, the same principle used to analyze Stirling engines. Consequently, by verifying the correctness of the theoretical model for the isothermal steam expander using experimental data, a prototype of 100 c.c. isothermal steam expander is constructed.

  11. Steam generator life management

    International Nuclear Information System (INIS)

    Steam generators are a critical component of a nuclear power reactor, and can contribute significantly to station unavailability, as has been amply demonstrated in Pressurized Water Reactors (PWRs). CANDU steam generators are not immune to steam generator degradation, and the variety of CANDU steam generator designs and tube materials has led to some unexpected challenges. However, aggressive remedial actions, and careful proactive maintenance activities, have led to a decrease in steam generator-related station unavailability of Canadian CANDUs. AECL and the CANDU utilities have defined programs that will enable existing or new steam generators to operate effectively for 40 years. Research and development work covers corrosion and mechanical degradation of tube bundles and internals, chemistry, thermal hydraulics, fouling, inspection and cleaning, as well as provision for specially tool development for specific problem solving. A major driving force is development of CANDU-specific fitness-for-service guidelines, including appropriate inspection and monitoring technology to measure steam generator condition. Longer-range work focuses on development of intelligent on-line monitoring for the feedwater system and steam generator. New designs have reduced risk of corrosion and fouling, are more easily inspected and cleaned, and are less susceptible to mechanical damage. The Canadian CANDU utilities have developed programs for remedial actions to combat degradation of performance (Gentilly-2, Point Lepreau, Bruce A/B, Pickering A/B), and have developed strategic plans to ensure that good future operation is ensured. This report shows how recent advances in cleaning technology are integrated into a life management strategy, discusses downcomer flow measurement as a means of monitoring steam generator condition, and describes recent advances in hideout return as a life management tool. The research and development program, as well as operating experience, has identified

  12. Steam generator life management

    Energy Technology Data Exchange (ETDEWEB)

    Tapping, R.L. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Nickerson, J. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada); Spekkens, P.; Maruska, C. [Ontario Hydro, Toronto, Ontario (Canada)

    1998-01-01

    Steam generators are a critical component of a nuclear power reactor, and can contribute significantly to station unavailability, as has been amply demonstrated in Pressurized Water Reactors (PWRs). CANDU steam generators are not immune to steam generator degradation, and the variety of CANDU steam generator designs and tube materials has led to some unexpected challenges. However, aggressive remedial actions, and careful proactive maintenance activities, have led to a decrease in steam generator-related station unavailability of Canadian CANDUs. AECL and the CANDU utilities have defined programs that will enable existing or new steam generators to operate effectively for 40 years. Research and development work covers corrosion and mechanical degradation of tube bundles and internals, chemistry, thermal hydraulics, fouling, inspection and cleaning, as well as provision for specially tool development for specific problem solving. A major driving force is development of CANDU-specific fitness-for-service guidelines, including appropriate inspection and monitoring technology to measure steam generator condition. Longer-range work focuses on development of intelligent on-line monitoring for the feedwater system and steam generator. New designs have reduced risk of corrosion and fouling, are more easily inspected and cleaned, and are less susceptible to mechanical damage. The Canadian CANDU utilities have developed programs for remedial actions to combat degradation of performance (Gentilly-2, Point Lepreau, Bruce A/B, Pickering A/B), and have developed strategic plans to ensure that good future operation is ensured. This report shows how recent advances in cleaning technology are integrated into a life management strategy, discusses downcomer flow measurement as a means of monitoring steam generator condition, and describes recent advances in hideout return as a life management tool. The research and development program, as well as operating experience, has identified

  13. Role of the statistician in the decommissioning of the New Brunswick Laboratory and other nuclear facilities

    International Nuclear Information System (INIS)

    This report examines what the statistician can contribute to decommissioning operations, with particular emphasis on the New Brunswick Laboratory (NBL) currently scheduled for decommissioning beginning in FY81. In the opinion of the author, a professional statistician should be a full member of the planning team directing decommissioning operations at the New Brunswick Laboratory. This opinion is based in part on the familiarity with the valuable contributions made by statisticians toward the cleanup of transuranics in soil on the Enewetak Atoll. More generally, however, the professional statistician can help plan the decommissioning effort to help ensure that representative data are obtained, analyzed and, interpreted in appropriate ways so that RA decisions can be made with the required confidence. The statistician's contributions at the NBL could include providing guidance on the number and location of samples and in-situ measurements, analyzing and interpreting these data, designing a data management and documentation system, interfacing with the certification contractor's statistician, and assisting in writing documentation and final reports. In all cases, the statistician should work closely with the professional health physicist and others on the planning team in a closely coordinated effort of planning and data analysis

  14. Political Partisanship, Bureaucratic Pragmatism and Acadian Nationalism: New Brunswick, Canada's 1920 History Textbook Controversy

    Science.gov (United States)

    Helyar, Frances

    2014-01-01

    During a time of post-war sensitivity to Canadian nationalism and patriotism, public feeling was aroused in 1920 New Brunswick regarding a world history textbook with a new chapter about the First World War. The American author made no reference to Canada's war efforts. The subsequent public discussion focused on issues of patriotism,…

  15. Diverse tetrapod trackways in the Lower Pennsylvanian Tynemouth Creek Formation, near St. Martins, southern New Brunswick, Canada

    DEFF Research Database (Denmark)

    Falcon-Lang, Howard J; Gibling, Martin R; Benton, Michael J;

    2010-01-01

    Newly discovered tetrapod trackways are reported from eight sites in the Lower Pennsylvanian Tynemouth Creek Formation of southern New Brunswick, Canada. By far the most abundant and well-preserved tracks comprise pentadactyl footprints of medium size (32–53 mm long) with slender digits and a nar...

  16. New Staphylinidae (Coleoptera records with new collection data from New Brunswick, Canada: Scaphidiinae, Piestinae, Osorinae, and Oxytelinae

    Directory of Open Access Journals (Sweden)

    Reginald Webster

    2012-04-01

    Full Text Available Nine species of Scaphidiinae are newly reported for New Brunswick, Canada, bringing the total number of species known from the province to 12. Scaphium castanipes Kirby, Baeocera inexspectata Löbl and Stephen, Baeocera securiforma (Cornell, Scaphisoma repandum Casey, and Toxidium gammaroides LeConte are reported for the first time from the Maritime provinces. Siagonum punctatum LeConte and Siagonum stacesmithi Hatch, and the subfamily Piestinae are reported for the first time from New Brunswick. The subfamily Osoriinae is reported for the first time from New Brunswick and the Maritime provinces based on the collection of three species: Clavilispinus prolixus (LeConte, Thoracophorus costalis (Erichson, and a Lispinodes species. The Lispinodes species is also newly recorded for Canada. Six species of Oxytelinae are newly recorded from New Brunswick, bringing the total number of species of this subfamily known to the province to 20. Apocellus sphaericollis (Say and Platystethus americanus Erichson are new to the Maritime provinces. Additional locality and bionomic data are presented for Mitosynum vockerothi Campbell, and the male genitalia are illustrated for the first time. Collection and bionomic data are presented for all included species.

  17. Steam boiler technology

    Energy Technology Data Exchange (ETDEWEB)

    Teir, S.

    2003-07-01

    This book is the published version of the e-book with the same name. The interactive lecture slides, which accompany most chapters, exist only in the online version and on the attached CD-Rom. The Steam Boiler Technology e-book is the main course book for the course on steam boiler technology provided by the Laboratory of Energy Engineering and Environmental Protection at Helsinki University of Technology. The steam boiler technology e-Book is provided by the Laboratory of Energy Engineering and Environmental Protection at Helsinki University of Technology. The book covers the basics and the history of steam generation, modern boilers types and applications, steam/water circulation design, feedwater and steam systems components, heat exchangers in steam boilers, boiler calculations, thermal design of heat exchangers. The chapters of the second edition have been corrected based on reader and reviewer comments, and four new chapters have been added. The user interface of the electronic version has also been updated. The password for the online book will be changed once a year. If you have problems accessing the online book, or need a new password, please contact sebastian.teir@hut.fi.

  18. Steam generator tube failures

    Energy Technology Data Exchange (ETDEWEB)

    MacDonald, P.E.; Shah, V.N.; Ward, L.W.; Ellison, P.G.

    1996-04-01

    A review and summary of the available information on steam generator tubing failures and the impact of these failures on plant safety is presented. The following topics are covered: pressurized water reactor (PWR), Canadian deuterium uranium (CANDU) reactor, and Russian water moderated, water cooled energy reactor (VVER) steam generator degradation, PWR steam generator tube ruptures, the thermal-hydraulic response of a PWR plant with a faulted steam generator, the risk significance of steam generator tube rupture accidents, tubing inspection requirements and fitness-for-service criteria in various countries, and defect detection reliability and sizing accuracy. A significant number of steam generator tubes are defective and are removed from service or repaired each year. This wide spread damage has been caused by many diverse degradation mechanisms, some of which are difficult to detect and predict. In addition, spontaneous tube ruptures have occurred at the rate of about one every 2 years over the last 20 years, and incipient tube ruptures (tube failures usually identified with leak detection monitors just before rupture) have been occurring at the rate of about one per year. These ruptures have caused complex plant transients which have not always been easy for the reactor operators to control. Our analysis shows that if more than 15 tubes rupture during a main steam line break, the system response could lead to core melting. Although spontaneous and induced steam generator tube ruptures are small contributors to the total core damage frequency calculated in probabilistic risk assessments, they are risk significant because the radionuclides are likely to bypass the reactor containment building. The frequency of steam generator tube ruptures can be significantly reduced through appropriate and timely inspections and repairs or removal from service.

  19. Steam generator tube failures

    International Nuclear Information System (INIS)

    A review and summary of the available information on steam generator tubing failures and the impact of these failures on plant safety is presented. The following topics are covered: pressurized water reactor (PWR), Canadian deuterium uranium (CANDU) reactor, and Russian water moderated, water cooled energy reactor (VVER) steam generator degradation, PWR steam generator tube ruptures, the thermal-hydraulic response of a PWR plant with a faulted steam generator, the risk significance of steam generator tube rupture accidents, tubing inspection requirements and fitness-for-service criteria in various countries, and defect detection reliability and sizing accuracy. A significant number of steam generator tubes are defective and are removed from service or repaired each year. This wide spread damage has been caused by many diverse degradation mechanisms, some of which are difficult to detect and predict. In addition, spontaneous tube ruptures have occurred at the rate of about one every 2 years over the last 20 years, and incipient tube ruptures (tube failures usually identified with leak detection monitors just before rupture) have been occurring at the rate of about one per year. These ruptures have caused complex plant transients which have not always been easy for the reactor operators to control. Our analysis shows that if more than 15 tubes rupture during a main steam line break, the system response could lead to core melting. Although spontaneous and induced steam generator tube ruptures are small contributors to the total core damage frequency calculated in probabilistic risk assessments, they are risk significant because the radionuclides are likely to bypass the reactor containment building. The frequency of steam generator tube ruptures can be significantly reduced through appropriate and timely inspections and repairs or removal from service

  20. Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446). Supplement No. 13

    International Nuclear Information System (INIS)

    Supplement 13 to the Safety Evaluation Report related to the operation of Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission (NRC). The facility is located in Somervell County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement presents the staff's evaluation of the Comanche Peak Response Team (CPRT) Program Plan which was formulated by the applicant to resolve various construction and design issues raised by the Atomic Safety and Licensing Board, allegers, intervenor Citizens Association for Sound Energy (CASE), NRC inspections of various types, and Cygna Energy Services while conducting its independent design assessment. The NRC staff concludes that the CPRT Program Plan provides an overall structure for addressing all existing issues and any future issues which may be identified from further evaluations, and if properly implemented will provide important evidence of the design and construction quality of CPSES, and will identify any needed corrective action. The report identifies items to be addressed by the NRC staff during the implementation phase

  1. Technical and economic analysis of steam-injected gas-turbine cogeneration

    Science.gov (United States)

    Larson, Eric D.; Williams, Robert H.

    1985-11-01

    Industrial cogeneration is gaining popularity as an energy and money saving alternative to separate steam and electricity generation. Among cogeneration technologies, gas-turbine systems are attractive largely because of their lower capital cost and high thermodynamic efficiency. However, at industrial plants where steam and electricity loads vary daily, seasonally, or unpredictably, the economics of conventional gas turbines are often unfavorable due to low capacity utilization. Steam-injected gas-turbine cogeneration overcomes the part-load problem by providing for excess steam to be injected back into the turbine to raise electrical output and generating efficiency. Under provisions of the Public Utilities Regulatory Policies Act, any excess electricity can be sold to the local grid at the prevailing avoided cost of electricity. Steam-injected gas-turbine cogeneration can result in a consistently high rate of return on investment over a wide range of variation in process steam loads. Moreover, this technology can also give rise to greater annual electricity production and fuel savings per unit of process steam generated, compared to simple-cycle cogeneration, making the technology attractive from the perspective of society, as well as that of the user. Steam-injected gas-turbines may soon find applications in electric utility base-load generation, as well, since it appears that electrical generating efficiencies in excess of 50% can be obtained from turbines producing of the order of 100 MW of electricity at a fully-installed capital cost as low as 500/kW.

  2. Fuel ethanol production using nuclear-plant steam

    International Nuclear Information System (INIS)

    In the United States, the production of fuel ethanol from corn for cars and light trucks has increased from about 6 billion liters per year in 2000 to 19 billion liters per year in 2006. A third of the world's liquid fuel demands could ultimately be obtained from biomass. The production of fuel ethanol from biomass requires large quantities of steam. For a large ethanol plant producing 380 million liters of fuel ethanol from corn per year, about 80 MW(t) of 1-MPa (∼180 deg. C) steam is required. Within several decades, the steam demand for ethanol plants in the United States is projected to be tens of gigawatts, with the worldwide demand being several times larger. This market may become the largest market for cogeneration of steam from nuclear electric power plants. There are strong incentives to use steam from nuclear power plants to meet this requirement. The cost of low-pressure steam from nuclear power plants is less than that of natural gas, which is now used to make steam in corn-to-ethanol plants. Steam from nuclear power plants reduces greenhouse gases compared with steam produced from fossil fuels. While ethanol is now produced from sugarcane and corn, the next-generation ethanol plants will use more abundant cellulose feedstocks. It is planned that these plants will burn the lignin in the cellulosic feedstocks to provide the required steam. Lignin is the primary non-sugar-based component in cellulosic biomass that can not be converted to ethanol. Low-cost steam from nuclear plants creates the option of converting the lignin to other liquid fuels and thus increase the liquid fuel production per unit of biomass. Because liquid fuel production from biomass is ultimately limited by the availability of biomass, steam from nuclear plants can ultimately increase the total liquid fuels produced from biomass. (author)

  3. Liquid metal steam generator

    International Nuclear Information System (INIS)

    A liquid metal heated steam generator is described which in the event of a tube failure quickly exhausts out of the steam generator the products of the reaction between the water and the liquid metal. The steam is generated in a plurality of bayonet tubes which are heated by liquid metal flowing over them between an inner cylinder and an outer cylinder. The inner cylinder extends above the level of liquid metal but below the main tube sheet. A central pipe extends down into the inner cylinder with a centrifugal separator between it and the inner cylinder at its lower end and an involute deflector plate above the separator so that the products of a reaction between the liquid metal and the water will be deflected downwardly by the deflector plate and through the separator so that the liquid metal will flow outwardly and away from the central pipe through which the steam and gaseous reaction products are exhausted. (U.S.)

  4. French steam generator

    International Nuclear Information System (INIS)

    After recalling the potential damage mode of tubes of steam generator, the author recalls the safety criteria used in France. The improvements and the process of damage prejudice and reparation for tubular bundle are presented

  5. Backpressure Steam turbine

    OpenAIRE

    Chrástek, Pavel

    2012-01-01

    The diploma works demonstrates the thermodynamic calculation and design of the geometry flow profile of the back-pressure steam turbine for specified inlet and outlet conditions of steam. Next target of the work is to design the drawing of the turbine axial cross section. Structuring of this diploma work calculation is following: - regulating stage thermodynamic calculation - turbine stages calculation - equalizing-balancing piston calculation - entire turbine intrinsic efficiency and power r...

  6. Safety evaluation report related to the operation of Comanche Peak Steam Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446)

    International Nuclear Information System (INIS)

    Supplement 14 to the Safety Evaluation Report related to the operation of the Comanche Peak Stam Electric Station (CPSES), Units 1 and 2 (NUREG-0797), has been prepared by the Office of Special Projects of the US Nuclear Regulatory Commission (NRC). The facility is located in Somerville County, Texas, approximately 40 miles southwest of Fort Worth, Texas. This supplement presents the staff's evaluation of the applicants' Corrective Action Program (CAP0 related to large ans small bore piping and pipe supports. The scope and methodologies for CAP workshop as summarized in revision O to the large and small bore piping project status reports and as detailed in related documents referenced in this evaluation were developed to resolve various design issues raised by the Atomic Safety and Licensing Board (ASLB);the intervenor, Citizens Association for Sound Energy (CASE);the Camanche Peak Response Team (CPRT);SYGNA Energy Services (CYGNA);and the NRC staff. The NRC staff concludes that the CAP workscopes for large and small bore piping provide a comprehensive program for resolving the associated technical concerns identified by the ASLB, CASE, CPRT, CYGNA, and the NRC staff and their implementation ensures that the design of large and small bore piping and pipe supports at CPSES satisfies the applicable requirements of 10 CFR 50

  7. Learning through EC directive based SEA in spatial planning? Evidence from the Brunswick Region in Germany

    International Nuclear Information System (INIS)

    This paper presents results of an international comparative research project, funded by the UK Economic and Social Research Council (ESRC) and the Academy for Sustainable Communities (ASC) on the 'learning potential of appraisal (strategic environmental assessment - SEA) in spatial planning'. In this context, aspects of 'single-loop' and 'double-loop' learning, as well as of individual, organisational and social learning are discussed for emerging post-EC Directive German practice in the planning region (Zweckverband) of Brunswick (Braunschweig), focusing on four spatial plan SEAs from various administrative levels in the region. It is found that whilst SEA is able to lead to plan SEA specific knowledge acquisition, comprehension, application and analysis ('single-loop learning'), it is currently resulting only occasionally in wider synthesis and evaluation ('double-loop learning'). Furthermore, whilst there is evidence that individual and occasionally organisational learning may be enhanced through SEA, most notably in small municipalities, social learning appears to be happening only sporadically.

  8. Development of low-pressure-loss steam separator with design by analysis and test (2). Verification of the full-scale steam separator performance with improved swirler

    International Nuclear Information System (INIS)

    The purpose of this study is to develop a new BWR steam separator with a lower pressure loss of more than 20% than the current steam separator while maintaining the steam separation performance. Reducing the pressure loss of steam separators is advantageous in that it reduces the required recirculation pump power and hence increases the net electrical power output. In previous studies, a low-pressure-loss steam separator was developed by three-dimensional two-phase flow simulations verified by 1/2.22-scale model experiment. In this study, performance tests for a full-scale steam separator with an improved swirler were conducted under actual reactor operating conditions of 7.17 MPa and 287degC. The obtained results demonstrate that pressure loss decreases by about 25% and the separation performance is similar to that of the current steam separator under rated reactor conditions. (author)

  9. Safety evaluation report related to the operation of Susquehanna Steam Electric Station, Units 1 and 2. Docket Nos. 50-387 and 50-388, Pennsylvania Power and Light Company, Allegheny Electric Cooperative, Inc

    International Nuclear Information System (INIS)

    Information is presented concerning site characteristics; design criteria for systems and components; reactor thermal and hydraulic characteristics; reactor coolant pressure boundary; engineered safety features; instrumentation and control; electrical power systems; auxiliary systems; conduct of operations; quality assurance; and TMI-2 requirements

  10. Electrical engineer's reference book

    CERN Document Server

    Laughton, M A

    1985-01-01

    Electrical Engineer's Reference Book, Fourteenth Edition focuses on electrical engineering. The book first discusses units, mathematics, and physical quantities, including the international unit system, physical properties, and electricity. The text also looks at network and control systems analysis. The book examines materials used in electrical engineering. Topics include conducting materials, superconductors, silicon, insulating materials, electrical steels, and soft irons and relay steels. The text underscores electrical metrology and instrumentation, steam-generating plants, turbines

  11. CANDU energy for steam assisted gravity drainage

    International Nuclear Information System (INIS)

    Traditional open-pit mining has been used by industry for many years to remove oil sands from shallow deposits. To increase production capacity, the industry is looking for new technology to exploit bitumen from deep deposits. Among them, SAGD (Steam-Assisted Gravity Drainage) appears to be the most promising approach. It uses steam to remove bitumen from underground reservoirs. Recently, the SAGD recovery process has been put into commercial operation by major oil companies.Atomic Energy Canada Limited has assessed the use of the ACR-1000 as a source of heat and electricity for oil sand extraction and processing. The ACR-1000 design is an evolutionary development of the familiar CANDU technology, adding innovations to enhance economics, operations, and safety margins. The net electrical output from a standard ACR-1000 will be close to 1100 MWe, depending on local cooling water temperature

  12. Steam explosion studies review

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Moon Kyu; Kim, Hee Dong

    1999-03-01

    When a cold liquid is brought into contact with a molten material with a temperature significantly higher than the liquid boiling point, an explosive interaction due to sudden fragmentation of the melt and rapid evaporation of the liquid may take place. This phenomenon is referred to as a steam explosion or vapor explosion. Depending upon the amount of the melt and the liquid involved, the mechanical energy released during a vapor explosion can be large enough to cause serious destruction. In hypothetical severe accidents which involve fuel melt down, subsequent interactions between the molten fuel and coolant may cause steam explosion. This process has been studied by many investigators in an effort to assess the likelihood of containment failure which leads to large scale release of radioactive materials to the environment. In an effort to understand the phenomenology of steam explosion, extensive studies has been performed so far. The report presents both experimental and analytical studies on steam explosion. As for the experimental studies, both small scale tests which involve usually less than 20 g of high temperature melt and medium/large scale tests which more than 1 kg of melt is used are reviewed. For the modelling part of steam explosions, mechanistic modelling as well as thermodynamic modelling is reviewed. (author)

  13. Steam explosion studies review

    International Nuclear Information System (INIS)

    When a cold liquid is brought into contact with a molten material with a temperature significantly higher than the liquid boiling point, an explosive interaction due to sudden fragmentation of the melt and rapid evaporation of the liquid may take place. This phenomenon is referred to as a steam explosion or vapor explosion. Depending upon the amount of the melt and the liquid involved, the mechanical energy released during a vapor explosion can be large enough to cause serious destruction. In hypothetical severe accidents which involve fuel melt down, subsequent interactions between the molten fuel and coolant may cause steam explosion. This process has been studied by many investigators in an effort to assess the likelihood of containment failure which leads to large scale release of radioactive materials to the environment. In an effort to understand the phenomenology of steam explosion, extensive studies has been performed so far. The report presents both experimental and analytical studies on steam explosion. As for the experimental studies, both small scale tests which involve usually less than 20 g of high temperature melt and medium/large scale tests which more than 1 kg of melt is used are reviewed. For the modelling part of steam explosions, mechanistic modelling as well as thermodynamic modelling is reviewed. (author)

  14. Optimum sizing of steam turbines for concentrated solar power plants

    Directory of Open Access Journals (Sweden)

    Andreas Poullikkas, Constantinos Rouvas, Ioannis Hadjipaschalis, George Kourtis

    2012-01-01

    Full Text Available In this work, a selection of the optimum steam turbine type and size for integration in concentrated solar power (CSP plants is carried out. In particular, the optimum steam turbine input and output interfaces for a range of CSP plant capacity sizes are identified. Also, efficiency and electricity unit cost curves for various steam turbine capacities are estimated by using a combination of the Steam Pro software module of the Thermoflow Suite 18 package and the IPP v2.1 optimization software tool. The results indicate that the estimated efficiency and the expected specific capital cost of the power block are very important criteria in choosing the best steam turbine size of a CSP plant. For capacity sizes of 10kWe up to 50MWe, the steam turbine efficiency increases and the steam turbine expected specific capital cost of the power block decreases at a high rate, whereas for larger sizes they remain almost constant. Thus, there is significant efficiency gains to be realized and large cost savings in increasing the turbine size up to 50MWe. Finally, although the cost of electricity of a CSP plant with capacities greater than 1MWe is significantly reduced to less than 1US$/kWh, currently such technology can only become economically viable through supporting schemes.

  15. Polymer dispersant addition qualification program for steam generator use

    International Nuclear Information System (INIS)

    One of the major problems encountered in the steam generators of nuclear power plants is the accumulation of sludge. Sludge deposition affects the thermal efficiency of a steam generator and has often been implicated in corrosion of steam generator tubing at the tubesheet and tube support plate locations. The majority of the sludge in steam generators is composed of iron oxide (Fe3O4) with other metal oxides, depending upon the materials used in the construction of the pre-boiler cycle. Over time, even with careful system cycle water chemistry control, corrosion products may accumulate in the steam generator. Several utilities have undertaken programs to reduce the amount of sludge in their steam generators. In particular, Commonwealth Edison Company (ComEd) in conjunction with the Electric Power Research Institute (EPRI) and Babcock and Wilcox have defined a 'generic' chemical addition qualification program. The basic details of this program is reported here. This program will determine the effect of chemical additives (for instance polymer addition), to the feedwater, on the materials of construction of steam generators, with emphasis on the tubing material. It will also determine if the steam generator pressure boundary and internal components will be adversely affected during their design life by the use of the candidate chemical additives. (O.M.)

  16. Energy efficiency of CHP using condensing steam turbine with extraction

    International Nuclear Information System (INIS)

    The paper presents an investigation of energy efficiency of two CHP techniques– using only condensing steam turbine with extraction (single cycle) and using gas turbine with condensing steam turbine with extraction (double cycle) . The energy efficiency is estimated on base of two energy efficiency coefficients – brutto and effective electrical and by the fuel saving in case of CHP system comparatively with the SHP. The investigations are done by modeling using GateCycle software

  17. Design and construction of a steam generator with feedback

    International Nuclear Information System (INIS)

    The EARTH project aims to develop technologies to design and build systems that generate electricity in space, using microreactors. One of the activities within the TERRA project aims to build a closed thermal cycle Rankine type in order to test a Tesla turbine type. The objective of this work is to design and build a steam generator with feedback, which should ensure a satisfactory range of steam supply, security system, feedback system and heating system

  18. Gas-based electricity production: which possibilities? - Thermal plants with steam generator; Perspectives for mini-cogeneration in collective housing; Electricity production by gas plants: which orientations on a middle term?

    International Nuclear Information System (INIS)

    A set of articles proposes a comparison between coal fired and natural gas fired power stations, discusses the perspectives of low power cogeneration installations for collective housing (some examples are evoked). It also reports interventions of a meeting on middle-term orientation for gas-based electricity production during which interveners addressed several issues such as the opportunity of investment in new infrastructures, the evolution of the gas sector, modulation means

  19. Nuclear steam for underground

    International Nuclear Information System (INIS)

    When we speak of oil reserves approaching exhaustion, we generally mean only the economic reserves. Only an estimated 15% of the entire petroleum reserves of the Earth have been consumed to date. In order to exploit unconventional sources of oil, large amounts of capital and energy will be required. Nuclear power plants would be able to provide the heat economically for the steam needed to drive the crude oil out of the rock in 'tertiary extraction'. According to a study by Kraftwerk Union and Veba-Oel-Entwicklungs GmbH nuclear steam is already cheaper than oil-produced steam. Over an operating life of twenty years, the total advantage would add up to 15,000 million deutschmarks. (orig.)

  20. Steam process cogeneration using nuclear energy

    International Nuclear Information System (INIS)

    Use of energy in a sustainable manner is to make processes more efficient. Oil industry requires of electricity and steam for refinery and petrochemical processes, nuclear energy can be a clean energy alternative. Cogeneration is an option to be assessed by Mexico to provide additional value to electricity generation. Mexico is a country with oil resources that requires process heat for gasoline production among other things. With the concern about the climate change and sustain ability policies it is adequate to use cogeneration as a way to optimize energy resources. Currently there is a national program that considers cogeneration for several Mexican refineries, and the first choices are combined cycle plants and thermo power plants using residual oil. This is long term program. The pebble bed modular reactor (PBMR) is a next generation reactors that works with very high temperatures that can be used to produce steam process along with electricity, in this work two different couplings are assessed for the PBMR reactor to produce steam process, the two couplings are compared for using in the Mexican refineries and some conclusions are given. (Author)

  1. Study of Constant Voltage Control on Small Steam Generator Based on PID Algorithm

    OpenAIRE

    Yanjun Xiao; Xuewei Ma; Wei Shao; Yuming Guan

    2014-01-01

    The object of this study is a kind of 3 kW small steam generator, which can recover waste heat through making use of 0.1~0.3 MPa steam. This can exploit secondary energy efficiently. The electricity generated can be commonly used as factory lighting, heating, fan and emergency power supply. But the generation voltage of the existed steam turbine is instable, especially when the steam pressure and the load of the generator changes suddenly. This can pose a threat to electrical safety and great...

  2. Volume reduction of dry active waste by use of a waste sorting table at the Brunswick nuclear power plant

    International Nuclear Information System (INIS)

    Carolina Power and Light Company's Brunswick nuclear power plant has been using a National Nuclear Corporation Model WST-18 Waste Sorting Table to monitor and sort dry active waste for segregating uncontaminated material as a means of low-level waste volume reduction. The WST-18 features 18 large-area, solid scintillation detectors arranged in a 3 x 6 array underneath a sorting/monitoring surface that is shielded from background radiation. An 11-week study at Brunswick showed that the use of the waste sorting table resulted in dramatic improvements in both productivity (man-hours expended per cubic foot of waste processed) and monitoring quality over the previous hand-probe frisking method. Use of the sorting table since the study has confirmed its effectiveness in volume reduction. The waste sorting table paid for its operation in volume reduction savings alone, without accounting for the additional savings from recovering reusable items

  3. Gas--steam turbine combined cycle power plants

    Energy Technology Data Exchange (ETDEWEB)

    Christian, J.E.

    1978-10-01

    The purpose of this technology evaluation is to provide performance and cost characteristics of the combined gas and steam turbine, cycle system applied to an Integrated Community Energy System (ICES). To date, most of the applications of combined cycles have been for electric power generation only. The basic gas--steam turbine combined cycle consists of: (1) a gas turbine-generator set, (2) a waste-heat recovery boiler in the gas turbine exhaust stream designed to produce steam, and (3) a steam turbine acting as a bottoming cycle. Because modification of the standard steam portion of the combined cycle would be necessary to recover waste heat at a useful temperature (> 212/sup 0/F), some sacrifice in the potential conversion efficiency is necessary at this temperature. The total energy efficiency ((electric power + recovered waste heat) divided by input fuel energy) varies from about 65 to 73% at full load to 34 to 49% at 20% rated electric power output. Two major factors that must be considered when installing a gas--steam turbine combines cycle are: the realiability of the gas turbine portion of the cycle, and the availability of liquid and gas fuels or the feasibility of hooking up with a coal gasification/liquefaction process.

  4. Digital implementation, simulation and tests in MATLAB of the models of Steam line, the turbines, the pressure regulator of a BWR type nucleo electric power plant; Implementacion digital, simulacion y pruebas en MATLAB de los modelos de la linea de vapor, las turbinas y el regulador de presion de una central Nucleoelectrica tipo BWR

    Energy Technology Data Exchange (ETDEWEB)

    Lopez R, A. [UNAM, Laboratorio de Analisis de Ingenieria de Reactores Nucleares, DEPFI, Campus Morelos, en IMTA Jiutepec, Morelos (Mexico)]. e-mail: andyskamx@yahoo.com.mx

    2004-07-01

    In this phase of the project they were carried out exhaustive tests to the models of the steam lines, turbines and pressure regulator of a BWR type nucleo electric central for to verify that their tendencies and behaviors are it more real possible. For it, it was necessary to also analyze the transfer functions of the different components along the steam line until the power generator. Such models define alone the dominant poles of the system, what is not limitation to reproduce a wide range of anticipated transitoriness of a power station operation. In the same manner, it was integrated and proved the integrated model form with the models of feeding water of the SUN-RAH, simulating the nuclear reactor starting from predetermined entrances of the prospective values of the vessel. Also it was coupled with the graphic interface developed with the libraries DirectX implementing a specific monitoring panel for this system. (Author)

  5. Patricia steam generator tests

    International Nuclear Information System (INIS)

    The Patricia GV program is a joint program of CEA, French utilities, and FRAMATOME. It aims at a better knowledge of the pressurized water reactor steam generator behavior under small break loss of coolant accident conditions. It has two parts: Patricia GVl deals with the primary side of the steam generator and is presently completed. Patricia GV2 deals with the secondary side dry-out phenomenon and is still in progress. Objectives, test facilities, test procedures, and results of the program are discussed

  6. High performance steam development

    Energy Technology Data Exchange (ETDEWEB)

    Duffy, T.; Schneider, P. [Solar Turbines Inc., San Diego, CA (United States)

    1995-10-01

    Over 30 years ago U.S. industry introduced the world`s highest temperature (1200{degrees}F at 5000 psig) and most efficient power plant, the Eddystone coal-burning steam plant. The highest alloy material used in the plant was 316 stainless steel. Problems during the first few years of operation caused a reduction in operating temperature to 1100{degrees}F which has generally become the highest temperature used in plants around the world. Leadership in high temperature steam has moved to Japan and Europe over the last 30 years.

  7. Public forest policy development in New Brunswick, Canada: multiple streams approach, advocacy coalition framework, and the role of science

    OpenAIRE

    William F. A. Anderson; MacLean, David A.

    2015-01-01

    In a 15-year case study, we used the multiple streams approach (MSA) and the advocacy coalition framework (ACF) to examine a controversial industry-led proposal for increased harvest of Crown forests in New Brunswick, Canada, in an adversarial policy subsystem. Study participants were queried on their perceptions of policy problems and reasons for community attention, the relationship between science and policy, and whether policy decisions were consistent with scientific understanding. Thema...

  8. Steam generator sludge removal apparatus

    International Nuclear Information System (INIS)

    The present invention relates to equipment for cleaning steam generators and in particular to a high pressure fluid lance for cleaning sludge off the steam generator tubes away from an open tube lane. 6 figs

  9. Steam generators - problems and prognosis

    Energy Technology Data Exchange (ETDEWEB)

    Tapping, R.L

    1997-05-01

    Steam-generator problems, largely a consequence of corrosion and fouling, have resulted in increased inspection requirements and more regulatory attention to steam-generator integrity. In addition, utilities have had to develop steam-generator life-management strategies, including cleaning and replacement, to achieve design life. This paper summarizes the pertinent data to 1993/1994, and presents an overview of current steam-generator management practices. (author)

  10. Steam Rankine Solar Receiver, phase 2

    Science.gov (United States)

    Deanda, L. E.; Faust, M.

    1981-01-01

    A steam rankine solar receiver (SRSR) based on a tubular concept was designed and developed. The SRSR is an insulated, cylindrical coiled tube boiler which is mounted at the focal plane of a fully tracking parabolic solar reflector. The concentrated solar energy received at the focal plane is then transformed to thermal energy through steam generation. The steam is used in a small Rankine cycle heat engine to drive a generator for the production of electrical energy. The SRSR was designed to have a dual mode capability, performing as a once through boiler with and without reheat. This was achieved by means of two coils which constitute the boiler. The boiler core size of the SRSR is 17.0 inches in diameter and 21.5 inches long. The tube size is 7/16 inch I.D. by 0.070 inch wall for the primary, and 3/4 inch I.D. by 0.125 inch wall for the reheat section. The materials used were corrosion resistant steel (CRES) type 321 and type 347 stainless steel. The core is insulated with 6 inches of cerablanket insulation wrapped around the outer wall. The aperture end and the reflector back plate at the closed end section are made of silicon carbide. The SRSR accepts 85 kwth and has a design life of 10,000 hrs when producing steam at 1400 F and 2550 psig.

  11. Consolidated nuclear steam generator

    International Nuclear Information System (INIS)

    An improved system of providing power has a unique generating means for nuclear reactors with a number of steam generators in the form of replaceable modular units of the expendable type to attain the optimum in effective and efficient vaporization of fluid during the generating power. The system is most adaptable to undrground power plants and marine usage

  12. Consolidated nuclear steam generator

    International Nuclear Information System (INIS)

    The invention described relates to an improved system of providing power having a unique generating means of the nuclear reactor variety adapted with a plurality of steam generators in the form of replaceable modular units of the expendable type for the attainment of the optimum in effective and efficient vaporization of fluid during the process of generating power

  13. Numerical discretization analysis of a HTR steam generator model for the thermal-hydraulics code trace

    OpenAIRE

    Esch Markus; Knoche Dietrich; Hurtado Antonio

    2014-01-01

    For future high temperature reactor projects, e. g., for electricity production or nuclear process heat applications, the steam generator is a crucial component. A typical design is a helical coil steam generator consisting of several tubes connected in parallel forming cylinders of different diameters. This type of steam generator was a significant component used at the thorium high temperature reactor. In the work presented the temperature profile is bein...

  14. V. C. Summer Nuclear Station steam generator replacement

    International Nuclear Information System (INIS)

    The Virgil C. Summer Steam Generator Replacement Project involved the first-ever replacement of an existing steam generator with a different and later vintage component from the original equipment manufacturer (OEM), in this case Westinghouse Model Delta-75 steam generators to replace Westinghouse Model D-3 steam generators, which had been plaguing South Carolina Electric and Gas Company's (SCE and G) Virgil C. Summer Nuclear Plant since shortly after initial operation in 1982. This project also involved the first use of laser metrology technology for steam generator-to-reactor coolant system severance cutting, machining, and component fitup and the first use of an impregnated sponge blast media for reactor coolant system pipe end decontamination. The sequence of events leading to the decision to replace steam generators and during the replacement process is described. Intensive planning and teamwork, combined with input from SCE and G and the use of mockups to train the work force in a simulated radiological environment, were instrumental in achieving world-record schedule performance and setting a new US record for the lowest accumulated radiation exposure during a steam generator replacement project while completing the project without a single lost workday case incident

  15. Modelling and simulation of the steam line, the high and low pressure turbines and the pressure regulator for the SUN-RAH nucleo electric university simulator; Modelado y simulacion de la linea de vapor, las turbinas de alta y de baja presion y el regulador de presion para el simulador universitario de nucleo electricas SUN RAH

    Energy Technology Data Exchange (ETDEWEB)

    Lopez R, A. [DEPFI, Campus Morelos, en IMTA Jiutepec, Morelos, UNAM (Mexico)]. e-mail: andyskamx@yahoo.com.mx

    2003-07-01

    In the following article the development of a simulator that allows to represent the dynamics of the following systems: steam line, nozzle, vapor separator, reheater, high pressure turbine, low pressure turbine, power generator and the pressure regulator of a nucleo electric power station. We start from the supposition that this plant will be modeled from a nuclear reactor type BWR (Boiling Water Reactor), using models of reduced order that represent the more important dynamic variables of the physical processes that happen along the steam line until the one generator. To be able to carry out the simulation in real time the Mat lab mathematical modeling software is used, as well as the specific simulation tool Simulink. It is necessary to point out that the platform on which the one is executed the simulator is the Windows operating system, to allow the intuitive use that only this operating system offers. The above-mentioned obeys to that the objective of the simulator it is to help the user to understand some of the dynamic phenomena that are present in the systems of a nuclear plant, and to provide a tool of analysis and measurement of variables to predict the desirable behavior of the same ones. The model of a pressure controller for the steam lines, the high pressure turbine and the low pressure turbine is also presented that it will be the one in charge of regulating the demand of the system according to the characteristics and critic restrictions of safety and control, assigned according to those wanted parameters of performance of this system inside the nucleo electric plant. This simulator is totally well defined and it is part of the University student nucleo electric simulator with Boiling Water Reactor (SUN-RAH), an integral project and of greater capacity. (Author)

  16. Effect of liquid waste discharges from steam generating facilities

    International Nuclear Information System (INIS)

    This report contains a summary of the effects of liquid waste discharges from steam electric generating facilities on the environment. Also included is a simplified model for use in approximately determining the effects of these discharges. Four basic fuels are used in steam electric power plants: three fossil fuels--coal, natural gas, and oil; and uranium--presently the basic fuel of nuclear power. Coal and uranium are expected to be the major fuels in future years. The following power plant effluents are considered: heat, chlorine, copper, total dissolved solids, suspended solids, pH, oil and grease, iron, zinc, chrome, phosphorus, and trace radionuclides

  17. Effect of liquid waste discharges from steam generating facilities

    Energy Technology Data Exchange (ETDEWEB)

    McGuire, H.E. Jr.

    1977-09-01

    This report contains a summary of the effects of liquid waste discharges from steam electric generating facilities on the environment. Also included is a simplified model for use in approximately determining the effects of these discharges. Four basic fuels are used in steam electric power plants: three fossil fuels--coal, natural gas, and oil; and uranium--presently the basic fuel of nuclear power. Coal and uranium are expected to be the major fuels in future years. The following power plant effluents are considered: heat, chlorine, copper, total dissolved solids, suspended solids, pH, oil and grease, iron, zinc, chrome, phosphorus, and trace radionuclides.

  18. Evolution of Xstrata's tailings dam safety program in New Brunswick and Ontario

    Energy Technology Data Exchange (ETDEWEB)

    Small, C.A. [AMEC Earth and Environmental Ltd., Fredericton, NB (Canada); Yashychyn, D. [Xstrata Copper, Timmins, ON (Canada); Morris, N. [Xstrata Zinc, Miramichi, NB (Canada); Schwenger, R.; Butler, B. [Xstrata Zinc, Bathurst, NB (Canada)

    2007-07-01

    Xstrata mine operations in Ontario and New Brunswick were presented along with a review of the dam safety challenges that the company has faced over the years. In particular, this paper described the initiatives undertaken to ensure the structural stability of mine tailings and water dams that have been constructed at Xstrata's major mining operations in eastern Canada. The tailings and mine water dams at these sites range in height up to 40 metres, and are constructed primarily of earth and rock fill. This paper also included a description of Xstrata's dam safety management program, how it evolved and what is presently in place. The program ensures that the dams are constructed and operated safely, particularly since the service life of these dams is estimated to be hundreds of years. With the advent of the Mining Association of Canada Guidelines for Managing Tailings Facilities, Xstrata has improved its dam safety program to include more frequent inspections, dam safety reviews, peer reviews, and risk assessments.

  19. Preliminary chronostratigraphy of the Tetagouche and Fournier groups in northern New Brunswick

    International Nuclear Information System (INIS)

    Seven U-Pb zircon ages of volcanic rocks from northern New Brunswick are reported and a preliminary stratigraphy of the middle Ordovician Tetagouche and Fournier groups is presented. Deposition of the Tetagouche Group started with calcareous rocks of the Vallee Lourdes Formation in the Late Arenig (>470 Ma). Quartz- and feldspar-phyric felsic volcanic rocks of the immediately overlying Nepisiquit Falls Formation yielded U-Pb zircon ages between ca. 471 and 469 Ma. These volcanic rocks are time stratigraphic equivalents of the feldspar-phyric dacites of the Spruce Lake Formation, which yielded a U-Pb zircon age of ca. 470 Ma, and tholeiitic and alkalic pillow basalts of the structurally overlying Canoe Landing Lake Formation. The final phase of rhyolitic to dacitic volcanism is marked by the emplacement of distinct quartz- and feldspar-phyric dacitic porphyries at ca. 465 Ma, thus limiting silicic volcanism to the Late Arenig and llanvim. During the Ilandeilo and Caradoc (ca. 464-457 Ma) volcanic activity in the Tetagouche Group was characterized by extrusion of alkali basalts and minor comendites, interlayered with dark shales and siltstones of the Boucher Brook Formation. Oceanic crust of the Fournier Group was also formed during this period. (author). 29 refs., 1 tab., 10 figs

  20. Post-Taconic blueschist suture in the northern Appalachians of northern New Brunswick, Canada

    Energy Technology Data Exchange (ETDEWEB)

    van Staal, C.R.; Ravenhurst, C.E.; Roddick, J.C. (Geological Survey of Canada, Ottawa, Ontario (Canada)); Winchester, J.A. (Univ. of Keele (England)); Langton, J.P. (Queen' s Univ., Kingston, Ontario (Canada))

    1990-11-01

    A narrow belt of Late Ordovician-Early Silurian blueschist, at least 70 km long, separates an allochthonous fragment of back-arc oceanic crust of the Middle Ordovician Fournier Group from underlying, rift-related volcanic rocks of the Middle Ordovician Tetagouche Group in northern New Brunswick, Canada. The basalts on both sides of the blueschist belt are predominantly metamorphosed to greenschist facies conditions. The blueschist belt is interpreted to be an out-of-sequence thrust zone that accommodated tectonic transport of higher pressure rocks on top of lower pressure rocks during post-peak blueschist facies metamorphism. The blueschists have higher Fe{sub 2}O{sub 3}/FeO ratios and total iron contents in comparison to otherwise chemically equivalent basalts of the Fournier and Tetagouche Groups that have been metamorphosed into greenschists. The blueschist belt was probably the site of channelized flow of oxidizing fluids during active deformation ina subduction complex formed during the closure of a wide Taconic back-arac basin in Late Ordovician-Silurian time.

  1. Sticks and stones: racism as experienced by adolescents in New Brunswick.

    Science.gov (United States)

    Baker, C; Varma, M; Tanaka, C

    2001-12-01

    The purpose of the study was to describe both the nature of racism as experienced by adolescent self-described victims in the province of New Brunswick and their response to the perceived racist incidents. A qualitative methodology based on the constructivist paradigm was used. In-depth interviews were conducted with non-White adolescent victims of racism and with parents of victims. Although the study was initiated in response to an eruption of publicity about teenage racial violence, the findings indicate that racist incidents were not a new phenomenon for the participants. They described a low-key but long-term problem that had begun when they entered the public school system. Name-calling was by far the most common form of racism identified and it played a part in most of the other incidents described; dismissed as harmless by authority figures, it appeared to have long-term consequences for its targets. The participants' response to racism was found to have three phases: splintered universe, spiralling resistance, and disengagement. The results suggest that nurses working in the field of school health should address issues of racism among children and adolescents. PMID:11845626

  2. Acadian biospeleology: composition and ecology of cave fauna of Nova Scotia and southern New Brunswick, Canada.

    Directory of Open Access Journals (Sweden)

    Moseley Max

    2007-01-01

    Full Text Available The vertebrate and invertebrate fauna, environment and habitats of caves and disused mines in Nova Scotia and southern NewBrunswick are provisionally catalogued and described, based on field collections made over many years. The area was glaciatedand the subterranean fauna consists of non-troglobites all of which have arrived and colonised the caves during or following finalrecession of the Pleistocene glaciers. The statistical composition of the fauna at the higher taxonomic level is similar to that inOntario, but is less species rich and there are some notable ecological and other differences. Porcupine dung accumulations are animportant habitat in the region, constituting a cold-temperate analogue of the diverse guano habitats of southern and tropical caves.Parietal assemblages are, as in other cold temperate regions, an important component of the invertebrate fauna but here includespecies derived directly from dung communities: another parallel with tropical guano caves. An unanticipated finding is the numberof non-indigenous species now utilising local caves. These appear to have colonised unfilled ecological niches, suggesting thatpost-glacial recolonisation of the subterranean habitat in Nova Scotia has been relatively delayed. Finally the general and regionalsignificance of the subterranean fauna is briefly discussed.

  3. Steam generator tube integrity program. Phase I report

    International Nuclear Information System (INIS)

    The results are presented of the pressure tests performed as part of Phase I of the Steam Generator Tube Integrity (SGTI) program at Battelle Pacific Northwest Laboratory. These tests were performed to establish margin-to-failure predictions for mechanically defected Pressurized Water Reactor (PWR) steam generator tubing under operating and accident conditions. Defect geometries tested were selected because they simulate known or expected defects in PWR steam generators. These defect geometries are Electric Discharge Machining (EDM) slots, elliptical wastage, elliptical wastage plus through-wall slot, uniform thinning, denting, denting plus uniform thinning, and denting plus elliptical wastage. All defects were placed in tubing representative of that currently used in PWR steam generators

  4. Steam engine research for solar parabolic dish

    Science.gov (United States)

    Demler, R. L.

    1981-01-01

    The parabolic dish solar concentrator provides an opportunity to generate high grade energy in a modular system. Most of the capital is projected to be in the dish and its installation. Assurance of a high production demand of a standard dish could lead to dramatic cost reductions. High production volume in turn depends upon maximum application flexibility by providing energy output options, e.g., heat, electricity, chemicals and combinations thereof. Subsets of these options include energy storage and combustion assist. A steam engine design and experimental program is described which investigate the efficiency potential of a small 25 kW compound reheat cycle piston engine. An engine efficiency of 35 percent is estimated for a 700 C steam temperature from the solar receiver.

  5. Steam separator latch assembly

    Science.gov (United States)

    Challberg, Roy C.; Kobsa, Irvin R.

    1994-01-01

    A latch assembly removably joins a steam separator assembly to a support flange disposed at a top end of a tubular shroud in a nuclear reactor pressure vessel. The assembly includes an annular head having a central portion for supporting the steam separator assembly thereon, and an annular head flange extending around a perimeter thereof for supporting the head to the support flange. A plurality of latches are circumferentially spaced apart around the head flange with each latch having a top end, a latch hook at a bottom end thereof, and a pivot support disposed at an intermediate portion therebetween and pivotally joined to the head flange. The latches are pivoted about the pivot supports for selectively engaging and disengaging the latch hooks with the support flange for fixedly joining the head to the shroud or for allowing removal thereof.

  6. Failure Analysis of Retired Steam Generator Tubings

    International Nuclear Information System (INIS)

    Since the first commercial operation of Kori-1 in 1978, 20 units of nuclear power plants are operated, and the it covers 40 % of total electricity in Korea as of 2008. A steam generator tube rupture incident occurred in the Ulchin unit 4 in 2002, which made the public sensitive to nuclear power plant. In order to keep the nuclear energy as a main energy source, the integrity of steam generator should be demonstrated. It is important to improve a flaw detection capability of the eddy current testing(ECT) in steam generator(SG) tubings in order to maintain the tube integrity. A quantified evaluation on the flaws on SG tubings, which is crucial for the tube integrity evaluation is not satisfactory. It is necessary to utilize the retired SG having various types of corrosion damages. In addition, an examination of pulled tube from Kori 1 retired steam generator will give us information about effectiveness of a remedial action(TiO2 addition) which was applied to mitigate ODSCC. A crack growth model is also needed to ensure a tube repair criteria for a next fuel cycle based on the ASME safety evaluation code, which has to meet a requirement that the flaws have to sustain under three times of normal operation pressure difference and 1.4 times of severe accident condition. In this project, hardware such as semi hot lab for pulled tube examination and modification of transportation cask for pulled tube and software such as procedure of transportation of radioactive steam generator tube and non-destructive and destructive examination of pulled tube were established. The non-destructive and destructive examination of pulled tubes from Kori 1 retired steam generator were performed in the semi hot lab. An effect of remedial actions applied to Kori 1 retired steam generator, PWSCC trend and bulk water chemistry and crevice chemistry in Kori 1 were evaluated. An electrochemical decontamination technology for pulled tube was developed to reduce a radiation exposure and enhance

  7. Infrared steam laser cleaning

    OpenAIRE

    Frank, Pascal; Lang, Florian; Mosbacher, Mario; Boneberg, Johannes; Leiderer, Paul

    2008-01-01

    Steam Laser Cleaning with a pulsed infrared laser source is investigated. The infrared light is tuned to the absorption maximum of water (λ = 2.94 µm, 10 ns), whereas the substrates used are transparent (glass, silicon). Thus a thin liquid water layer condensed on top of the contaminated substrate is rapidly heated. The pressure generated during the subsequent phase explosion generates a cleaning force which exceeds the adhesion of the particles. We examine the cleaning threshold in single sh...

  8. Steam boiler for fytomass

    OpenAIRE

    Baláš, Jiří

    2008-01-01

    The purpose of this Diploma Thesis was the construction design of the steam boiler for fytomass. For the specified parameters of biomass have been gradually implemented stoichiometric calculations of which are further based calculation of enthalpies of combustion gas. In the next part have been dealt with heat balance of the boiler, the efficiency of the boiler, recirculation of exhaust gases and the temperature of the combustion gases in outlet from fire. Thereinafter, the proposal of partic...

  9. Proceedings of the 2007 Annual Meeting of the Canadian Mathematics Education Study Group = Actes de la Rencontre Annuelle 2007 du Groupe Canadien d'Etude en Didactique des Mathematiques (31st, Fredricton, New Brunswick, Canada, Jun 8-12, 2007)

    Science.gov (United States)

    Liljedahl, Peter, Ed.

    2008-01-01

    This submission contains the Proceedings of the 2007 Annual Meeting of the Canadian Mathematics Education Study Group (CMESG), held at the University of New Brunswick in Fredricton, New Brunswick. The CMESG is a group of mathematicians and mathematics educators who meet annually to discuss mathematics education issues at all levels of learning.…

  10. Steamed over SAGD

    International Nuclear Information System (INIS)

    Gulf Canada Resources asked the Alberta Energy and Utilities Board (AEUB) to suspend natural gas production by other producers on Gulf's Surmount lease, a huge pool of oilsands, because they were testing a new technology developed by the Alberta Energy Department called SAGD (steam assisted gravity drainage). SAGD recovers bitumen from oilsands through the use of a pair of horizontal wells, placed one above the other. Steam is injected into the upper well, heating and thinning the bitumen which then drains down to the producing well which pumps it to the surface. While drilling the wells, Gulf had noticed pressure variations which they believe are due to gas production. They claim that the reservoir must be free of outside influences while they test combinations of steam pressure, temperature and volume for optimal productivity. The six gas producers in the area claim that their gas production is not affecting Gulf's oilsands reserves. If the suspension takes place, the AEUB could order Gulf to compensate the gas producers for lost production. 1 fig

  11. Steam generator life management

    International Nuclear Information System (INIS)

    'Full-Text:' Steam Generator Life Management responsibility embodies doing whatever is necessary to maintain the steam generation equipment of a nuclear plant in effective, reliable service. All comes together in that most critical deliverable, namely the submission of the documentation which wins approval for return to service after an outage program. Life management must address all aspects of SG reliability over the life of the plant. Nevertheless, the life management activities leading up to return to service approval is where all of it converges. Steam Generator Life Management activities entail four types of work, all equally important in supporting the objective of successful operation. These activities are i) engineering functions; including identification of inspection and maintenance requirements, outage planning and scope definition plus engineering assessment, design and analysis as necessary to support equipment operation, ii) fitness of service work; including the expert evaluation of degradation mechanisms, disposition of defects for return to service or not, and the fitness for service analysis as required to justify ongoing operation with acceptable defects, iii) inspection work; including large scale eddy current inspection of tubing, the definition of defect size and character, code inspections of pressure vessel integrity and visual inspections for integrity and iv) maintenance work; including repairs, retrofits, cleaning and modifications, all as necessary to implement the measures defined during activities i) through iii). The paper discusses the approach and execution of the program for the achievement of the above objectives and particularly of items i) and ii). (author)

  12. Wet steam wetness measurement in a 10 MW steam turbine

    Directory of Open Access Journals (Sweden)

    Kolovratník Michal

    2014-03-01

    Full Text Available The aim of this paper is to introduce a new design of the extinction probes developed for wet steam wetness measurement in steam turbines. This new generation of small sized extinction probes was developed at CTU in Prague. A data processing technique is presented together with yielded examples of the wetness distribution along the last blade of a 10MW steam turbine. The experimental measurement was done in cooperation with Doosan Škoda Power s.r.o.

  13. Investigation of Condensation Nuclei in Superheated Steam in Steam Turbines

    Czech Academy of Sciences Publication Activity Database

    Hrubý, Jan; Kolovratník, M.; Bartoš, Ondřej; Moravec, Pavel; Zíková, Naděžda; Ždímal, Vladimír; Jiříček, I.

    Londýn: British & Irish Association for Properties of Water and Steam (BIAPWS) a Institution of Mechanical Engineers, 2013, 016-016. [International Conference on the Properties of Water and Steam /16./ ICPWS. University of Greenwich, Londýn (GB), 01.09.2013-05.09.2013] Institutional support: RVO:61388998 ; RVO:67985858 Keywords : heterogeneous nucleation * steam turbine * diffusion battery Subject RIV: BJ - Thermodynamics; CF - Physical ; Theoretical Chemistry (UCHP-M)

  14. Environmental factors accounting during TPP's and NPP's steam turbine cooling system selection

    International Nuclear Information System (INIS)

    The environmental impact factors of TPP's and NPP's steam turbine cooling systems are considered. The method of environmental factors accounting during steam turbine cooling systems selection is given.The approximate calculation results of electricity cost generating components related with the cooling systems of 'dry', 'wet' and 'combined' types considering compensation costs of negative environmental impacts is introduced

  15. Features of steam turbine cooling by the example of an SKR-100 turbine for supercritical steam parameters

    Science.gov (United States)

    Arkadyev, B. A.

    2015-10-01

    Basic principles of cooling of high-temperature steam turbines and constructive solutions used for development of the world's first cooled steam turbine SKR-100 (R-100-300) are described. Principal differences between the thermodynamic properties of cooling medium in the steam and gas turbines and the preference of making flow passes of cooled cylinders of steam turbines as reactive are shown. Some of its operation results and their conclusions are given. This turbine with a power of 100 MW, initial steam parameters approximately 30 MPa and 650°C, and back pressure 3 MPa was made by a Kharkov turbine plant in 1961 and ran successfully at a Kashira GRES (state district power plant) up to 1979, when it was taken out of use in a still fully operating condition. For comparison, some data on construction features and operation results of the super-high pressure cylinder of steam turbines of American Philo 6 (made by General Electric Co.) and Eddystone 1 (made by Westinghouse Co.) power generating units, which are close to the SKR-100 turbine by design initial steam parameters and the implementation time, are given. The high operational reliability and effectiveness of the cooling system that was used in the super-high pressure cylinder of the SKR-100 turbine of the power-generating unit, which were demonstrated in operation, confirms rightfulness and expediency of principles and constructive solutions laid at its development. As process steam temperatures are increased, the realization of the proposed approach to cooling of multistage turbines makes it possible to limit for large turbine parts the application of new, more expensive high-temperature materials, which are required for making steam boilers, and, in some cases, to do completely away with their utilization.

  16. Process for purifying geothermal steam

    Science.gov (United States)

    Li, C.T.

    Steam containing hydrogen sulfide is purified and sulfur recovered by passing the steam through a reactor packed with activated carbon in the presence of a stoichiometric amount of oxygen which oxidizes the hydrogen sulfide to elemental sulfur which is adsorbed on the bed. The carbon can be recycled after the sulfur has been recovered by vacuum distillation, inert gas entrainment or solvent extraction. The process is suitable for the purification of steam from geothermal sources which may also contain other noncondensable gases.

  17. Regenerative superheated steam turbine cycles

    Science.gov (United States)

    Fuller, L. C.; Stovall, T. K.

    1980-01-01

    PRESTO computer program was developed to analyze performance of wide range of steam turbine cycles with special attention given to regenerative superheated steam turbine cycles. It can be used to model standard turbine cycles, including such features as process steam extraction, induction and feedwater heating by external sources, peaking, and high back pressure. Expansion line efficiencies, exhaust loss, leakages, mechanical losses, and generator losses are used to calculate cycle heat rate and generator output. Program provides power engineer with flexible aid for design and analysis of steam turbine systems.

  18. Cancer Institute of New Jersey: University of Medicine and Dentistry of New Jersey, New Brunswick, New Jersey. Environmental Assessment

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    The Department of Energy (DOE) proposes to authorize the University of Medicine and Dentistry of New Jersey to proceed with the design, construction, and equipping of the proposed Clinical Treatment and Research Facility of the University of New Jersey on the New Brunswick campus. The facility will provide for the integration of new and existing clinical outpatient cancer treatment with basic and clinical research to expedite the application of new discoveries in cancer treatment. Based on the analysis in the environmental assessment, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA).

  19. Production and certification of an equal atom plutonium isotopic standard - the New Brunswick Laboratory certified reference material (CRM) No. 128

    International Nuclear Information System (INIS)

    The US Department of Energy (DOE), New Brunswick Laboratory (NBL) has produced an equal atom 239Pu/242Pu isotopic standard, NBL CRM No. 128. Provisional certification of this standard relative to uranium was completed in 1984 and the material made available for distribution to the nuclear community. Certification of the 239Pu/242Pu ratio on an absolute basis has now been accomplished using highly accurate and precise chemical and mass spectrometric measurement techniques. The absolute certification of NBL CRM No. 128 has established it as the primary reference for calibrating the measurement of plutonium isotopic ratios

  20. Development of site-specific soil cleanup criteria: New Brunswick Laboratory, New Jersey site

    International Nuclear Information System (INIS)

    The potential human exposure which results from the residual soil radioactivity at a decommissioned site is a prime concern during D and D projects. To estimate this exposure, a pathway analysis approach is often used to arrive at the residual soil radioactivity criteria. The development of such a criteria for the decommissioning of the New Brunswick Laboratory, New Jersey site is discussed. Contamination on this site was spotty and located in small soil pockets spread throughout the site area. Less than 1% of the relevant site area was contaminated. The major contaminants encountered at the site were 239Pu, 241Am, normal and natural uranium, and natural thorium. During the development of the pathway analysis to determine the site cleanup criteria, corrections for the inhomogeneity of the contamination were made. These correction factors and their effect upon the relevant pathway parameters are presented. Major pathways by which radioactive material may reach an individual are identified and patterns of use are specified (scenario). Each pathway is modeled to estimate the transfer parameters along the given pathway, such as soil to air to man, etc. The transfer parameters are then combined with dose rate conversion factors (ICRP 30 methodology) to obtain soil concentration to dose rate conversion factors (pCi/g/mrem/yr). For an appropriate choice of annual dose equivalent rate, one can then arrive at a value for the residual soil concentration. Pathway modeling, transfer parameters, and dose rate factors for the three major pathways; inhalation, ingestion and external exposure, which are important for the NBL site, are discussed

  1. An Integrated RFID and Barcode Tagged Item Inventory System for Deployment at New Brunswick Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Younkin, James R [ORNL; Kuhn, Michael J [ORNL; Gradle, Colleen [New Brunswick Laboratory, Argonne, IL; Preston, Lynne [U.S. Department of Energy, Office of Health, Safety and Security; Thomas, Brigham B. [ORNL; Laymance, Leesa K [ORNL; Kuziel, Ron [DOE SC - Chicago Office

    2012-01-01

    New Brunswick Laboratory (NBL) has a numerous inventory containing thousands of plutonium and uranium certified reference materials. The current manual inventory process is well established but is a lengthy process which requires significant oversight and double checking to ensure correctness. Oak Ridge National Laboratory has worked with NBL to develop and deploy a new inventory system which utilizes handheld computers with barcode scanners and radio frequency identification (RFID) readers termed the Tagged Item Inventory System (TIIS). Certified reference materials are identified by labels which incorporate RFID tags and barcodes. The label printing process and RFID tag association process are integrated into the main desktop software application. Software on the handheld computers syncs with software on designated desktop machines and the NBL inventory database to provide a seamless inventory process. This process includes: 1) identifying items to be inventoried, 2) downloading the current inventory information to the handheld computer, 3) using the handheld to read item and location labels, and 4) syncing the handheld computer with a designated desktop machine to analyze the results, print reports, etc. The security of this inventory software has been a major concern. Designated roles linked to authenticated logins are used to control access to the desktop software while password protection and badge verification are used to control access to the handheld computers. The overall system design and deployment at NBL will be presented. The performance of the system will also be discussed with respect to a small piece of the overall inventory. Future work includes performing a full inventory at NBL with the Tagged Item Inventory System and comparing performance, cost, and radiation exposures to the current manual inventory process.

  2. Mercury concentrations in seabird tissues from Machias Seal Island, New Brunswick, Canada

    Energy Technology Data Exchange (ETDEWEB)

    Bond, Alexander L., E-mail: abond@mun.ca [Atlantic Cooperative Wildlife Ecology Research Network, University of New Brunswick, PO Box 4400, Fredericton, New Brunswick, E3B 5A3 (Canada); Department of Biology, University of New Brunswick, PO Box 4400, Fredericton, New Brunswick, E3B 5A3 (Canada); Diamond, Antony W. [Atlantic Cooperative Wildlife Ecology Research Network, University of New Brunswick, PO Box 4400, Fredericton, New Brunswick, E3B 5A3 (Canada); Department of Biology, University of New Brunswick, PO Box 4400, Fredericton, New Brunswick, E3B 5A3 (Canada)

    2009-07-01

    Mercury is a pervasive environmental contaminant, the anthropogenic portion of which is increasing globally, and in northeastern North America in particular. Seabirds frequently are used as indicators of the marine environment, including mercury contamination. We analysed paired samples for total mercury (Hg) concentrations in feathers and blood from adult and chick, albumen, and lipid-free yolk of seven seabirds breeding on Machias Seal Island, New Brunswick, Canada - Arctic Tern (Sterna paradisaea), Atlantic Puffin (Fratercula arctica), Common Eider (Somateria mollissima), Common Murre (Uria aalge), Common Tern (Sterna hirundo), Leach's Storm-petrel (Oceanodroma leucorhoa), and Razorbill (Alca torda). We also used stable-isotope ratios of carbon ({delta}{sup 13}C), and nitrogen ({delta}{sup 15}N) to evaluate the relationship between carbon source and trophic position and mercury. We found high Hg concentrations across tissue types in Leach's Storm-petrels, and Razorbills, with lower concentrations in other species, the lowest being in Common Eiders. Storm-petrels prey on mesopelagic fish that accumulate mercury, and Razorbills feed on larger, older fish that bioaccumulate heavy metals. Biomagnification of Hg, or the increase in Hg concentration with trophic position as measured by {delta}{sup 15}N, was significant and greater in albumen than other tissues, whereas in other tissues, {delta}{sup 15}N explained little of the overall variation in Hg concentration. Hg concentrations in egg components are higher on Machias Seal Island than other sites globally and in the Gulf of Maine region, but only for some species. Further detailed investigations are required to determine the cause of this trend.

  3. Steam generator tube performance

    International Nuclear Information System (INIS)

    A survey of steam generator operating experience for 1986 has been carried out for 184 pressurized water and pressurized heavy-water reactors, and 1 water-cooled, graphite-moderated reactor. Tubes were plugged at 75 of the reactors (40.5%). In 1986, 3737 tubes were plugged (0.14% of those in service) and 3148 tubes were repaired by sleeving. A small number of reactors accounted for the bulk of the plugged tubes, a phenomenon consistent with previous years. For 1986, the available tubesheet sludge data for 38 reactors has been compiled into tabular form, and sludge/deposit data will be incorporated into all future surveys

  4. steam power plants re powering with gas turbine review

    International Nuclear Information System (INIS)

    Re powering faith gas turbine means integration of new gas turbine in existing power plant. Such integration yield higher efficiencies lower operating and maintenance costs and reduction in pollution emission. This paper summarizes the results of a feasibility study that inquired the possibilities of such integration in Israel Electric Corporation - IEC's existing steam power plants (oil fired)

  5. Super critical water reactor for use in steam generation for recovery of bitumen resources

    International Nuclear Information System (INIS)

    The process of recovering the bitumen (oil sand) resources in Alberta requires steam at high pressures. To help reduce the carbon footprint of exploiting these fuel resources, an innovative new design of a CANDU super critical water reactor (CANDU-SCWR) is being considered to provide the high pressure steam required for the steam assisted gravity drainage (SAGD) process. The high temperature and pressure associated with the CANDU-SCWR allow for the high pressure, temperature steam to be produced without supplementary energy. The Petroleum Technology Alliance of Canada (PTAC) has specified the SAGD process requires steam at 11 MPa and near 100% steam quality, and net electrical power of 106 MWe. This paper examines steam cycle and design options to meet the steam and power requirements defined by PTAC. Steam cycle options are examined focusing on the optimization of steam and power conversion. Additionally passive safety and cooling for both the heat transport and moderation systems are considered and their impact on performance are examined. As the CANDU-SCWR is at a preliminary stage of design, basic design parameters have been defined based on preliminary assessments. This paper is focused on a reactor with the following basic design assumptions: Vertical fuel channel; Re-entrant fuel channels; Pu-Th fuel; and Batch refuelling. (author)

  6. Steamdrive direct contact steam generation for SAGD

    Energy Technology Data Exchange (ETDEWEB)

    Betzer-Zilevitch, Maoz [Society of Petroleum Engineers (Canada)

    2011-07-01

    Recently, focus has been shifted from the traditional once-through steam generator (OTSG) to the use of an evaporator and industrial high-pressure (HP) steam boilers in steam assisted gravity drainage (SAGD) steam generation technologies. As a result, the temperatures and pressures attainable are significantly higher than required for injection. This excess steam enthalpy drives the novel steam generation method presented in this paper. The process generates additional steam from highly contaminated oily water with zero liquid waste discharge using industrial boiler superheated steam. The process generates tailor-made pressure and temperature steam required for injection into the underground oil bearing formation. An additional 8-24% steam can be generated from highly contaminated oily water as is seen from the simulation results. The amount of additional steam generated is directly proportional to the temperature of the driving steam and the decrease in pressure of the formation.

  7. Materials for advanced ultrasupercritical steam turbines

    Energy Technology Data Exchange (ETDEWEB)

    Purgert, Robert [Energy Industries Of Ohio Inc., Independence, OH (United States); Shingledecker, John [Energy Industries Of Ohio Inc., Independence, OH (United States); Saha, Deepak [Energy Industries Of Ohio Inc., Independence, OH (United States); Thangirala, Mani [Energy Industries Of Ohio Inc., Independence, OH (United States); Booras, George [Energy Industries Of Ohio Inc., Independence, OH (United States); Powers, John [Energy Industries Of Ohio Inc., Independence, OH (United States); Riley, Colin [Energy Industries Of Ohio Inc., Independence, OH (United States); Hendrix, Howard [Energy Industries Of Ohio Inc., Independence, OH (United States)

    2015-12-01

    The U.S. Department of Energy (DOE) and the Ohio Coal Development Office (OCDO) have sponsored a project aimed at identifying, evaluating, and qualifying the materials needed for the construction of the critical components of coal-fired power plants capable of operating at much higher efficiencies than the current generation of supercritical plants. This increased efficiency is expected to be achieved principally through the use of advanced ultrasupercritical (A-USC) steam conditions. A limiting factor in this can be the materials of construction for boilers and for steam turbines. The overall project goal is to assess/develop materials technology that will enable achieving turbine throttle steam conditions of 760°C (1400°F)/35MPa (5000 psi). This final technical report covers the research completed by the General Electric Company (GE) and Electric Power Research Institute (EPRI), with support from Oak Ridge National Laboratory (ORNL) and the National Energy Technology Laboratory (NETL) – Albany Research Center, to develop the A-USC steam turbine materials technology to meet the overall project goals. Specifically, this report summarizes the industrial scale-up and materials property database development for non-welded rotors (disc forgings), buckets (blades), bolting, castings (needed for casing and valve bodies), casting weld repair, and casting to pipe welding. Additionally, the report provides an engineering and economic assessment of an A-USC power plant without and with partial carbon capture and storage. This research project successfully demonstrated the materials technology at a sufficient scale and with corresponding materials property data to enable the design of an A-USC steam turbine. The key accomplishments included the development of a triple-melt and forged Haynes 282 disc for bolted rotor construction, long-term property development for Nimonic 105 for blading and bolting, successful scale-up of Haynes 282 and Nimonic 263 castings using

  8. Combining the nuclear power plant steam cycle with gas turbines

    International Nuclear Information System (INIS)

    Nuclear steam power plants (NPP) are characterized by low efficiency, compared to steam power plants using fossil fuels. This is due to the relatively low temperature and pressure-throttling conditions of the NPP compared to those using fossil fuel. The light water pressurized water reactor (LW PWR) commercially known as AP600 was suggested for Kuwait cogeneration power desalting plant (CPDP). It has 600 MW nominal power capacity and 33% overall efficiency. Meanwhile, the Kuwaiti Ministry of Electricity and Water (MEW) installed plenty of gas turbines (GTs) to cover the drastic increase in the peak electrical load during the summer season. Combining some of these GTs with the AP600 can increase the capacity and efficiency of the combined plant, compared to either the GT open cycle or the NPP separate plants. This paper investigates the feasibility of utilizing the hot gases leaving the GT to superheat the steam leaving the steam generator of the AP600 NPP, as well as heating the feed water returning to the steam generator of the NPP condenser. This drastically increases the power output and the efficiency of the NPP. Detailed modifications to the NPP power cycle and the resulting enhancement of its performance are presented.

  9. Hydrogen-based power generation from bioethanol steam reforming

    Energy Technology Data Exchange (ETDEWEB)

    Tasnadi-Asztalos, Zs., E-mail: tazsolt@chem.ubbcluj.ro; Cormos, C. C., E-mail: cormos@chem.ubbcluj.ro; Agachi, P. S. [Babes-Bolyai University, Faculty of Chemistry and Chemical Engineering, 11 Arany Janos, Postal code: 400028, Cluj-Napoca (Romania)

    2015-12-23

    This paper is evaluating two power generation concepts based on hydrogen produced from bioethanol steam reforming at industrial scale without and with carbon capture. The power generation from bioethanol conversion is based on two important steps: hydrogen production from bioethanol catalytic steam reforming and electricity generation using a hydrogen-fuelled gas turbine. As carbon capture method to be assessed in hydrogen-based power generation from bioethanol steam reforming, the gas-liquid absorption using methyl-di-ethanol-amine (MDEA) was used. Bioethanol is a renewable energy carrier mainly produced from biomass fermentation. Steam reforming of bioethanol (SRE) provides a promising method for hydrogen and power production from renewable resources. SRE is performed at high temperatures (e.g. 800-900°C) to reduce the reforming by-products (e.g. ethane, ethene). The power generation from hydrogen was done with M701G2 gas turbine (334 MW net power output). Hydrogen was obtained through catalytic steam reforming of bioethanol without and with carbon capture. For the evaluated plant concepts the following key performance indicators were assessed: fuel consumption, gross and net power outputs, net electrical efficiency, ancillary consumptions, carbon capture rate, specific CO{sub 2} emission etc. As the results show, the power generation based on bioethanol conversion has high energy efficiency and low carbon footprint.

  10. Hydrogen-based power generation from bioethanol steam reforming

    Science.gov (United States)

    Tasnadi-Asztalos, Zs.; Cormos, C. C.; Agachi, P. S.

    2015-12-01

    This paper is evaluating two power generation concepts based on hydrogen produced from bioethanol steam reforming at industrial scale without and with carbon capture. The power generation from bioethanol conversion is based on two important steps: hydrogen production from bioethanol catalytic steam reforming and electricity generation using a hydrogen-fuelled gas turbine. As carbon capture method to be assessed in hydrogen-based power generation from bioethanol steam reforming, the gas-liquid absorption using methyl-di-ethanol-amine (MDEA) was used. Bioethanol is a renewable energy carrier mainly produced from biomass fermentation. Steam reforming of bioethanol (SRE) provides a promising method for hydrogen and power production from renewable resources. SRE is performed at high temperatures (e.g. 800-900°C) to reduce the reforming by-products (e.g. ethane, ethene). The power generation from hydrogen was done with M701G2 gas turbine (334 MW net power output). Hydrogen was obtained through catalytic steam reforming of bioethanol without and with carbon capture. For the evaluated plant concepts the following key performance indicators were assessed: fuel consumption, gross and net power outputs, net electrical efficiency, ancillary consumptions, carbon capture rate, specific CO2 emission etc. As the results show, the power generation based on bioethanol conversion has high energy efficiency and low carbon footprint.

  11. Hydrogen-based power generation from bioethanol steam reforming

    International Nuclear Information System (INIS)

    This paper is evaluating two power generation concepts based on hydrogen produced from bioethanol steam reforming at industrial scale without and with carbon capture. The power generation from bioethanol conversion is based on two important steps: hydrogen production from bioethanol catalytic steam reforming and electricity generation using a hydrogen-fuelled gas turbine. As carbon capture method to be assessed in hydrogen-based power generation from bioethanol steam reforming, the gas-liquid absorption using methyl-di-ethanol-amine (MDEA) was used. Bioethanol is a renewable energy carrier mainly produced from biomass fermentation. Steam reforming of bioethanol (SRE) provides a promising method for hydrogen and power production from renewable resources. SRE is performed at high temperatures (e.g. 800-900°C) to reduce the reforming by-products (e.g. ethane, ethene). The power generation from hydrogen was done with M701G2 gas turbine (334 MW net power output). Hydrogen was obtained through catalytic steam reforming of bioethanol without and with carbon capture. For the evaluated plant concepts the following key performance indicators were assessed: fuel consumption, gross and net power outputs, net electrical efficiency, ancillary consumptions, carbon capture rate, specific CO2 emission etc. As the results show, the power generation based on bioethanol conversion has high energy efficiency and low carbon footprint

  12. Steam generator module

    International Nuclear Information System (INIS)

    The module of the steam generator is arranged such that the first working medium flows through the tubes of the heat exchange bundle and the second working medium flows through the intertube space. At least one side of the module is provided with a lid which is provided with a system of through-flow apertures. The apertures are expanded and provided with a thread in the direction of the outer side of the lid. They are coaxial with the tubes of the heat exchange bundle at the point of their anchorage in the tube plate. The apertures are closed with plugs with a male thread and the sealing surfaces are formed between the thread joint and the space of the first working medium. The plugs extend into the space of the heat exchange bundle and form a throttle which replaces the classical stop and allow for dismantling. This arrangement of the modular steam generator allows the control of the inner surfaces of heat exchange pipes and also the cleaning of these inner surfaces. (E.S.)

  13. Steam generator materials

    International Nuclear Information System (INIS)

    In order to keep the nuclear power plant(NPP)s safe and increase their operating efficiency, axial stress corrosion cracking(SCC)(IGA/IGSCC, PWSCC, PbSCC) test techniques were developed and SCC property data of the archive steam generator tubing materials having been used in nuclear power plants operating in Korea were produced. The data obtained in this study were data-based, which will be used to clarify the damage mechanisms, to operate the plants safely, and to increase the lifetime of the tubing. In addition, the basic technologies for the improvement of the SCC property of the tubing materials, for new SCC inhibition, for damaged tube repair, and for manufacturing processes of the tubing were developed. In the 1 phase of this long term research, basic SCC test data obtained from the archive steam generator tubing materials used in NPPs operating in Korea were established. These basic technologies developed in the 1 phase will be used in developing process optimization during the 2 phase in order to develop application technologies to the field nuclear power plants

  14. Condensation in steam turbines

    Energy Technology Data Exchange (ETDEWEB)

    St' astny, M. [SKODA ENERGO zavod TURBINY, Plzen (Czech Republic); Sejna, M. [PC Progress, Praha (Czech Republic)

    1999-07-01

    A new theoretical model has been developed for the computation of a transonic flow of wet-steam through a turbine cascade with consideration of the condensation, completed by investigation of the solubility of NaCl impurity and its concentration in condensation droplets in the flow field. The system of governing equations consists of the 2D Euler Equations linked with other equations for homogeneous condensation, phase exchanges and transport of the liquid phase. The parallel heterogeneous condensation is evaluated on the assumption that, at the saturation line, are present droplets, that originate by the nucleation in the salt solution zone. The flow field with condensation in a typical turbine cascade is discussed. The heterogeneous condensation effect is also tested. The NaCl solubility falls rapidly to zero near the saturation line. The concentration of the NaCl in the droplets of condensation indicates the origin of the salt solution zone for transonic flow. They are analysed the conditions at the profile surface and in the blade boundary layers and the conclusions for the deposit creation and blade surface corrosion are derived. The conclusions are in agreement with the findings on the blades of actual steam turbines. (orig.)

  15. EP 1000 steam generator tube rupture analyses

    International Nuclear Information System (INIS)

    European electrical utility organizations together with Westinghouse and Ansaldo are participating in a program to utilize the Westinghouse passive nuclear plant technology to develop a plant which meets the European Utility Requirements (EUR) and is expected to be licensable in Europe. The program was initiated in 1994 and the plant is designated EP1000. The EP1000 design is notable for simplicity that comes from a reliance on passive safety systems to enhance plant safety. The use of passive safety systems has provided significant and measurable improvements in plant simplification, safety, reliability, investment protection and plant costs. These systems use only natural forces such as gravity, natural circulation, and compressed gas to provide the driving forces for the systems to adequately cool the reactor core following an initiating event. The EP1000 builds up on the Westinghouse passive nuclear plant technology to enhance plant safety and meet European Utility Requirements and specific European National Safety Criteria. This paper summarizes the main results of the Steam Generator Tube Rupture (SGTR) analysis activity, performed in Phase 2B of the European Passive Plant Program. The purpose of the study is to provide evidence that the passive safety system performance provides a significant improvement in terms of safety, providing significant margins to steam generator overfilling and reducing the need for operator actions. The behavior of the EP1000 plant following SGTR accidents has been analyzed by means of the RELAP5/Mod3.2 code. Sensitivity cases were performed, to address the impact of varying the number of steam generator tubes that rupture, and the potential adverse interactions that could result from operation of control systems (i.e., Chemical and Volume Control System, Startup Feedwater). Analyses have also been performed to define and verify improved protection system logic to avoid possible steam generator safety valve challenges both in the

  16. Steam generator tube integrity program

    Energy Technology Data Exchange (ETDEWEB)

    Dierks, D.R.; Shack, W.J. [Argonne National Laboratory, IL (United States); Muscara, J.

    1996-03-01

    A new research program on steam generator tubing degradation is being sponsored by the U.S. Nuclear Regulatory Commission (NRC) at Argonne National Laboratory. This program is intended to support a performance-based steam generator tube integrity rule. Critical areas addressed by the program include evaluation of the processes used for the in-service inspection of steam generator tubes and recommendations for improving the reliability and accuracy of inspections; validation and improvement of correlations for evaluating integrity and leakage of degraded steam generator tubes, and validation and improvement of correlations and models for predicting degradation in steam generator tubes as aging occurs. The studies will focus on mill-annealed Alloy 600 tubing, however, tests will also be performed on replacement materials such as thermally-treated Alloy 600 or 690. An overview of the technical work planned for the program is given.

  17. Derivation of guidelines for uranium residual radioactive material in soil at the New Brunswick Site, Middlesex County, New Jersey

    International Nuclear Information System (INIS)

    Residual radioactive material guidelines for uranium in soil were derived for the New Brunswick Site, located in Middlesex County, New Jersey. This site has been designated for remedial action under the Formerly Utilized Sites Remedial Action Program of the US Department of Energy (DOE). Residual radioactive material guidelines for individual radionuclides of concern and total uranium were derived on the basis of the requirement that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works in the immediate vicinity of the New Brunswick Site should not exceed a dose of 30 mrem/yr following remedial action for the current-use and likely future-use scenarios or a dose of 100 mrem/yr for less likely future-use scenarios. The DOE residual radioactive material guideline computer code, RESRAD, was used in this evaluation; RESRAD implements the methodology described in the DOE manual for establishing residual radioactive material guidelines. The guidelines derived in this report are intended to apply to the remediation of these remaining residual radioactive materials at the site. The primary radionuclides of concern in these remaining materials are expected to be radium-226 and, to a lesser extent, natural uranium and thorium. The DOE has established generic cleanup guidelines for radium and thorium in soil; however, cleanup guidelines for other radionuclides must be derived on a site-specific basis

  18. Who Is Using What in the Public Schools: The Interrelationships among Alcohol, Drug and Tobacco Use by Adolescents in New Brunswick Classrooms.

    Science.gov (United States)

    Grobe, Cary; Campbell, Elaine

    1990-01-01

    Attempted to discover patterns of alcohol, drug, and tobacco use among public school children in New Brunswick using Provincial School Drug Survey (PSDS), an existing large-scale assessment. Recoded variables in PSDS dataset to derive profiles of typical tobacco, cannabis, and alcohol users. Found increase in predictive accuracy of regression…

  19. Third steam-gas plant in Slovakia

    International Nuclear Information System (INIS)

    There are currently two large steam/gas plants in Slovakia, in Bratislava and Ruzomberok, and a third company is to start producing electricity and heat using natural gas. Although Siemens and the Swiss company, Advanced Power, have been discussing creating a steam/gas plant in Malzenice close to Trnava, it seems that Adato, Levice will be the first to launch production. Adato plans to build a facility worth 2 bil. Sk (54.05 mil. EUR) at the Gena industrial park in Levice. Although it is to employ only 35 people, the whole region would benefit. Levice wants to attract more investors that will need more electricity and according to the Mayor of Levice, Stefan Misak, the heat produced by the steam/gas plant will represent a good option for old town boilers. The executive officer and sole owner of Adato, Miroslav Gazo, stressed that the company could not cover the whole costs of the planned investment on its own. Several investors have already shown interest in financing the project and one foreign and two local investors are in negotiations. Adato has a state permit, has signed a contract with the town, has found suppliers of technologies abroad and has signed a preliminary contract with energy consumers. The company is not rushing into the project without having a risk assessment in place. We know that gas prices are going up. But our project will be profitable even under the least optimistic scenarios of gas price development,' said M. Gazo. He is negotiating with the gas utility, Slovensky plynarensky priemysel, and other gas suppliers. (authors)

  20. Predicting water temperatures using a deterministic model: Application on Miramichi River catchments (New Brunswick, Canada)

    Science.gov (United States)

    Caissie, Daniel; Satish, Mysore G.; El-Jabi, Nassir

    2007-04-01

    SummaryWater temperature influences many physical, chemical and biological properties of rivers. It also influences the distribution of fish and many aquatic organisms within the river environment. Hence, a good understanding of the thermal regime of rivers is essential for effective management of fisheries and aquatic resources. This study deals with the modelling of river water temperature using a deterministic model. This model calculates the net heat flux at the water surface using meteorological conditions within the study area. The water temperature model was applied on two watercourses of different size and thermal characteristics, but within a similar meteorological region, i.e. the Little Southwest Miramichi River and Catamaran Brook (New Brunswick, Canada). Data from 1992 to 1994 were used to calibrate the model, while data from 1995 to 1999 were used for the model validation. Results showed equally good agreement between observed and predicted water temperatures during the calibration period for both rivers with a root-mean-square error (RMSE) of 1.49 °C for the Little Southwest Miramichi River compared to 1.51 °C for Catamaran brook. During the validation period, RMSEs were calculated at 1.55 °C for the Little Southwest Miramichi River and 1.61 °C for Catamaran Brook. Poorer model performances were generally observed early in the season (e.g. spring), especially for the Little Southwest Miramichi River due to the influence of snowmelt conditions, while late summer to autumn performances showed among the best results for both rivers. Late autumn performances were more variable in Catamaran Brook and presumably influenced by the groundwater, geothermal conditions and potentially riparian shading. The geothermal aspect was further investigated at Catamaran Brook (using 1998 data) and results revealed that although geothermal fluxes are present, they explained very little of the unexplained variability (<0.1 °C). Similar to previous studies, the net

  1. Validating Evapotranspiraiton Equations Using Bowen Ratio in New Brunswick, Maritime, Canada

    Directory of Open Access Journals (Sweden)

    John Monteith

    2008-01-01

    Full Text Available Three methods including the Penman-Monteith (PM, Priestley-Taylor (PT, and 1963 Penman equation (PE for calculating daily reference evapotranspiration (ETo were evaluated in the Maritime region of Canada with the data collected from 2004 to 2007. An automatically operated meteorological station located on the Potato Research Centre, Agriculture and Agri-Food Canada, Fredericton, New Brunswick, Canada, was used to collect required meteorological data for evapotranspiration modeling. A Bowen Ratio system (BR was setup near the Environment Canada grade one weather station to provide evapotranspiration observations for the validation research of reference evapotranspiration models. The results showed that the prediction from each of the tested models had a certain degree of offset in comparison with the observations obtained by the BR method. All of the tested models slightly overestimated evapotranspiration compared to the BR system by 5-14%, depending on the method. However, the PM generated a better fit to the pooled dataset while the PT produced the best prediction for the 2007 validation dataset. The PM generated the best estimation of evapotranspiration for year 2004 during a inter-annual comparison. The BR revealed that the average daytime ET for the site was around 2.5 mm day-1(±0.1 averaged for Julian day 157-276 in 2004 to 2006 and possible condensation was 0.16 mm day-1 for the same period. Crop coefficient (Kc varied with different models, for example, 0.42 for the PM, 0.44 for the PT, and 0.67 for the PE with a slight yearly variation. With this set of Kc values, a validation with additional dataset collected in 2007 indicated that all three equations achieved a good fit with observations using the above Kc values. The PT performed slightly better than the other two models. A single factor analysis did not show any statistically significant difference between predicted and measured ET. With a consideration of simplicity and

  2. Applied research concerning the direct steam generation in parabolic troughs

    Energy Technology Data Exchange (ETDEWEB)

    Eck, M.; Eickhoff, M. [German Aerospace Center (DLR), Inst. of Technical Thermodynamics, Stuttgart (Germany); Zarza, E.; Valenzuela, L. [CIEMAT - Plataforma Solar de Almeria, Almeria (Spain); Rheinlaender, J. [Center for Solar Energy and Hydrogen Research, Baden-Wuerttemberg (ZSW), Stuttgart (Germany)

    2003-04-01

    With levelized electricity costs (LEC) of 10-12 USCts/kWh the well-known SEGS (Solar Electric Generating Systems) plants in California are presently the most successful solar technology for electricity generation [Price and Cable (2001) Proc. ASME Int. Solar Energy Conf. Forum 2001]. The SEGS plants apply a two-circuit system, consisting of the collector circuit and the Rankine cycle of the power block. These two-circuits are connected via a heat exchanger. In the case of the Direct Steam Generation (DSG) in the collector field [Zarza et al. (2001) Proc. Solar Forum 2001, Washington], the two-circuit system turns into a single-circuit system, where the collector field is directly coupled to the power block. This renders a lower investment and higher process temperatures resulting in a higher system efficiency. Due to the lower investment and the higher efficiency a reduction of the LEC of 10% is expected when the DSG process is combined with improved components of the solar collectors [Zarza (2002) DISS Phase II Final Report, EU Contract No. JOR3-CT98-0277]. Within the European DISS (Direct Solar Steam) project the feasibility of the direct steam generation has been proven in more than 3700 operation hours. Steam conditions of 100 bar and 400 deg C have been demonstrated. This paper presents the main scientific results of the DISS project that aims at the investigation and demonstration of the DSG process in parabolic troughs under real solar conditions. (Author)

  3. Integration of direct steam generation with parabolic trough collector for electricity production. Project INDITEP 310; Integracion de la tecnologia de generacion directa de vapor con colectores cilindro-parabolicos para produccion de electricidad. Proyecto INDITEP 310

    Energy Technology Data Exchange (ETDEWEB)

    Leon, J.; Zarza, E.; Valenzuela, L.

    2004-07-01

    The Plataforma Solar de Almeria (PSA) held during the latest years the test campaign of a new concept of direct steam generation in a real size parabolic trough collector row using solar energy. It has been experimentally demonstrated the possibility of replacing thermal oil by water as heat transfer fluid and the process technical and technological viability. The INDITEP project applies the acquired acknowledge for improving the efficiency and to reduce costs, designing, developing, testing and assessing new components able of improving technologically the system, the operating procedures for solar power plants and, performing a social and economic study of the technology. (Author)

  4. ULTRA-SUPERCRITICAL STEAM CORROSION

    Energy Technology Data Exchange (ETDEWEB)

    Holcomb, G.R.; Alman, D.E.; Bullard, S.B.; Covino, B.S., Jr.; Cramer, S.D.; Ziomek-Moroz, M.

    2003-04-22

    Efficiency increases in fossil energy boilers and steam turbines are being achieved by increasing the temperature and pressure at the turbine inlets well beyond the critical point of water. To allow these increases, advanced materials are needed that are able to withstand the higher temperatures and pressures in terms of strength, creep, and oxidation resistance. As part of a larger collaborative effort, the Albany Research Center (ARC) is examining the steam-side oxidation behavior for ultrasupercritical (USC) steam turbine applications. Initial tests are being done on six alloys identified as candidates for USC steam boiler applications: ferritic alloy SAVE12, austenitic alloy Super 304H, the high Cr-high Ni alloy HR6W, and the nickel-base superalloys Inconel 617, Haynes 230, and Inconel 740. Each of these alloys has very high strength for its alloy type. Three types of experiments are planned: cyclic oxidation in air plus steam at atmospheric pressure, thermogravimetric ana lysis (TGA) in steam at atmospheric pressure, and exposure tests in supercritical steam up to 650 C (1202 F) and 34.5 MPa (5000 psi). The atmospheric pressure tests, combined with supercritical exposures at 13.8, 20.7, 24.6, and 34.5 MPa (2000, 3000, 4000, and 5000 psi) should allow the determination of the effect of pressure on the oxidation process.

  5. Erosion corrosion in wet steam

    International Nuclear Information System (INIS)

    The effect of different remedies against erosion corrosion in wet steam has been studied in Barsebaeck 1. Accessible steam systems were inspected in 1984, 1985 and 1986. The effect of hydrogen peroxide injection of the transport of corrosion products in the condensate and feed water systems has also been followed through chemical analyses. The most important results of the project are: - Low alloy chromium steels with a chromium content of 1-2% have shown excellent resistance to erosion corrosion in wet steam. - A thermally sprayed coating has shown good resistance to erosion corrosion in wet steam. In a few areas with restricted accessibility minor attacks have been found. A thermally sprayed aluminium oxide coating has given poor results. - Large areas in the moisture separator/reheater and in steam extraction no. 3 have been passivated by injection of 20 ppb hydrogen peroxide to the high pressure steam. In other inspected systems no significant effect was found. Measurements of the wall thickness in steam extraction no. 3 showed a reduced rate of attack. - The injection of 20 ppb hydrogen peroxide has not resulted in any significant reduction of the iron level result is contrary to that of earlier tests. An increase to 40 ppb resulted in a slight decrease of the iron level. - None of the feared disadvantages with hydrogen peroxide injection has been observed. The chromium and cobalt levels did not increase during the injection. Neither did the lifetime of the precoat condensate filters decrease. (author)

  6. CANDU steam generator life management

    International Nuclear Information System (INIS)

    Steam generators are a critical component of a nuclear power reactor, and can contribute significantly to station unavailability, as has been amply demonstrated in Pressurized Water Reactors (PWRs). CANDU steam generators are not immune to steam generator degradation, and the variety of CANDU steam generator designs and tube materials has led to some unexpected challenges. However, aggressive remedial actions, and careful proactive maintenance activities, have led to a decrease in steam generator-related station unavailability of Canadian CANDUs. AECL and the CANDU utilities have defined programs that will enable existing or new steam generators to operate effectively for 40 years. Research and development work covers corrosion and mechanical degradation of tube bundles and internals, chemistry, thermalhydraulics, fouling, inspection and cleaning, as well as provision for specially tool development for specific problem solving. A major driving force is development of CANDU-specific fitness-for-service guidelines, including appropriate inspection and monitoring technology to measure steam generator condition. Longer-range work focuses on development of intelligent on-line monitoring for the feedwater system and steam generator. New designs have reduced risk of corrosion and fouling, are more easily inspected and cleaned, and are less susceptible to mechanical damage. The Canadian CANDU utilities have developed programs for remedial actions to combat degradation of performance (Gentilly-2, Point Lepreau, Bruce A/B, Pickering A/B), and have developed strategic plans to ensure that good future operation is ensured. The research and development program, as well as operating experience, has identified where improvements in operating practices and/or designs can be made in order to ensure steam generator design life at an acceptable capacity factory. (author)

  7. CANDU steam generator life management

    Energy Technology Data Exchange (ETDEWEB)

    Tapping, R.L. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Nickerson, J. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada); Spekkens, P.; Maruska, C. [Ontario Hydro, Toronto, Ontario (Canada)

    1998-01-01

    Steam generators are a critical component of a nuclear power reactor, and can contribute significantly to station unavailability, as has been amply demonstrated in Pressurized Water Reactors (PWRs). CANDU steam generators are not immune to steam generator degradation, and the variety of CANDU steam generator designs and tube materials has led to some unexpected challenges. However, aggressive remedial actions, and careful proactive maintenance activities, have led to a decrease in steam generator-related station unavailability of Canadian CANDUs. AECL and the CANDUutilities have defined programs that will enable existing or new steam generators to operate effectively for 40 years. Research and development work covers corrosion and mechanical degradation of tube bundles and internals, chemistry, thermalhydraulics, fouling, inspection and cleaning, as well as provision for specially tool development for specific problem solving. A major driving force is development of CANDU-specific fitness-for-service guidelines, including appropriate inspection and monitoring technology to measure steam generator condition. Longer-range work focuses on development of intelligent on-line monitoring for the feedwater system and steam generator. New designs have reduced risk of corrosion and fouling, are more easily inspected and cleaned, and are less susceptible to mechanical damage. The Canadian CANDU utilities have developed programs for remedial actions to combat degradation of performance (Gentilly-2, Point Lepreau, Bruce A/B, Pickering A/B), and have developed strategic plans to ensure that good future operation is ensured. The research and development program, as well as operating experience, has identified where improvements in operating practices and/or designs can be made in order to ensure steam generator design life at an acceptable capacity factory. (author)

  8. CANDU steam generator life management

    International Nuclear Information System (INIS)

    Steam generators are a critical component of a nuclear power reactor, and can contribute significantly to station unavailability, as has been amply demonstrated in PWRs. Canadian Deuterium Uranium (CANDU trademark) steam generators are not immune to steam generator degradation, and the variety of CANDU steam generator designs and tube materials has led to some unexpected challenges. However, aggressive remedial actions, and careful proactive maintenance activities, have resulted in a decrease in steam generator-related station unavailability of Canadian CANDU reactors. AECL and the CANDU utilities have defined programs that will enable existing or new steam generators to operate effectively for 40 years. Research and development (R and D) work covers corrosion and mechanical degradation of tube bundles and internals, chemistry, thermalhydraulics, fouling, inspection and cleaning, as well as provision for speciality tool development for specific problem solving. A major driving force is development of CANDU-specific fitness-for-service (FFS) guidelines, including appropriate inspection and monitoring technology to measure steam generator condition. This paper will also show how recent advances in cleaning technology are integrated into a life management strategy. Longer-range work focuses on development of intelligent on-line monitoring for the feedwater system and steam generator. New steam generator designs have reduced risk of corrosion and fouling, are more easily inspected and cleaned, and are less susceptible to mechanical damage. The Canadian CANDU utilities have developed programs for remedial actions to combat degradation of performance (Gentilly-2, Point Lepreau, Bruce-A/B, Pickering-A/B) and strategic plans to ensure that good future operation is ensured. (orig.)

  9. Design and operating experience of 1000MW high-temperature steam turbine

    Energy Technology Data Exchange (ETDEWEB)

    Matsukuma, Masaharu; Magoshi; Ryotaro; Nakano, Takashi; Tashiro; Hikaru; Tanaka, Yoshinori

    1999-07-01

    The applicable steam conditions for large-capacity fossil-fuel thermal power plants over 500 MW in Japan have conventionally been 24.2MPa and 538/566 C. Mitsubishi Heavy Industries, Ltd. (MHI) has established, through wide-scale development programs, the technologies for design and materials of steam turbines with steam temperature 593 C, and has applied the steam conditions of 24.2MPa and 538/593 C to the large-capacity 700 MW turbine, Hekinan No. 3 Unit for Chubu Electric Power Co., Inc. According to the further development of high-temperature design, MHI has successfully developed and manufactured the 1000 MW turbine, Matsuura No. 2 Unit, Electric Power Development Co., Ltd. with a steam condition of 600 C class main steam and reheating steam temperature for the first time in the world. The unit, that was first rolled with steam in January 1997, started commercial operation in July 1997. This paper describes the features of design and operating experience of this unit after about one year's commercial operation.

  10. Advanced technologies on steam generators

    Energy Technology Data Exchange (ETDEWEB)

    Sakata, Kaoru; Nakamura, Yuuki [Mitsubishi Heavy Industry Co., Takasago (Japan); Nakamori, Nobuo; Mizutani, Toshiyuki; Uwagawa, Seiichi; Saito, Itaru [Mitsubishi Heavy Industry Co., Kobe (Japan); Matsuoka, Tsuyoshi [Mitsubishi Heavy Industry Co., Yokohama (Japan)

    1997-12-31

    The thermal-hydraulic tests for a horizontal steam generator of a next-generation PWR (New PWR-21) were performed. The purpose of these tests is to understand the thermal-hydraulic behavior in the secondary side of horizontal steam generator during the plant normal operation. A test was carried out with cross section slice model simulated the straight tube region. In this paper, the results of the test is reported, and the effect of the horizontal steam generator internals on the thermalhydraulic behavior of the secondary side and the circulation characteristics of the secondary side are discussed. (orig.). 3 refs.

  11. Wet-steam erosion of steam turbine disks and shafts

    International Nuclear Information System (INIS)

    A study of wet-steam erosion of the disks and the rotor bosses or housings of turbines in thermal and nuclear power plants shows that the rate of wear does not depend on the diagrammed degree of moisture, but is determined by moisture condensing on the surfaces of the diaphragms and steam inlet components. Renovating the diaphragm seals as an assembly with condensate removal provides a manifold reduction in the erosion.

  12. Development and Transient Analysis of a Helical-coil Steam Generator for High Temperature Reactors

    International Nuclear Information System (INIS)

    A high temperature gas-cooled reactor (HTGR) is under development by the Next Generation Nuclear Plant (NGNP) Project at the Idaho National Laboratory (INL). Its design emphasizes electrical power production which may potentially be coupled with process heat for hydrogen production and other industrial applications. NGNP is considering a helical-coil steam generator for the primary heat transport loop heat exchanger based on its increased heat transfer and compactness when compared to other steam generators. The safety and reliability of the helical-coil steam generator is currently under evaluation as part of the development of NGNP. Transients, such as loss of coolant accidents (LOCA), are of interest in evaluating the safety of steam generators. In this study, a complete steam generator inlet pipe break (double ended pipe break) LOCA was simulated by an exponential loss of primary side pressure. For this analysis, a model of the helical-coil steam generator was developed using RELAP5-3D, an INL inhouse systems analysis code. The steam generator model behaved normally during the transient simulating the complete steam generator inlet pipe break LOCA. Further analysis is required to comprehensively evaluate the safety and reliability of the helical-coil steam generator design in the NGNP setting.

  13. Prediction of localized flow velocities and turbulence in a PWR steam generator: Final report

    International Nuclear Information System (INIS)

    The Steam Generator Project Office (SGPO) of the Steam Generator Owners Group and Electric Power Research Institute has developed a methodology for prediction of steam generator tube buffeting and associated material wear. Turbulent buffeting of steam generator tubes causes low amplitude vibratory response which results in fretting wear at support locations. Concerns raised at the Zion Nuclear Power Plant regarding the useful life of their steam generators prompted this study, in which the SGPO methodology is applied to analysis of the Westinghouse Model 51 steam generator. The specific intent of this project was to calculate turbulent buffeting forces within the tube bank of an operating Model 51 steam generator as a first step in the overall SGPO tube vibration and wear prediction strategy. Attention is focused on flow in the vicinity of anti-vibration bars (U-bend region) and on the flow that leaves the downcomer to impact against peripheral tubes. Other projects utilized the buffeting forces calculated here to determine tube vibratory response, tube-support plate impact statistics, and material wear rates. Besides successfully calculating hydraulic buffeting loads within the tube bank, the present project has enhanced the SGPO methodology and has identified hitherto unnoticed flow phenomena that occur in the steam generator. Experiments have also been carried out to validate numerical computations of the steam generator flow field

  14. AI reference LMFBR steam-generator development

    International Nuclear Information System (INIS)

    The Design Data Sheets summarize the key parameters being used in the design and analysis of the AI Prototype LMFBR Steam Generator. These Data Sheets supplement SDD-097-330-002, Steam Generator System, 1450 psi Steam Conditions. This document will serve as the baseline design data control until a GE/RRD approved steam generator specification with ordering data is received

  15. CT imaging of steam and steam/foam laboratory experiments

    International Nuclear Information System (INIS)

    This paper reports on the CT imaging technique together with temperature and pressure measurements used to follow the steam propagation during steam and steam foam injection experiments in a three dimensional laboratory steam injection model. During the design period, the advantages and disadvantages of different geometries were examined to find out which could best represent radial and gravity override flows and also fit the dimensions of the scanning field of the CT scanner. As a result of this analysis a 3D rectangular box with dimensions 20 x 20 x 7.5 cm was constructed. This box simulates one quarter of a five spot pattern. Aluminum, Teflon and Fiberfrax were chosen as supporting and insulating materials. Teflon was placed between the porous medium and the aluminum shell so that the rate of heat transfer in the porous medium would be much faster than that in the aluminum during a steam injection run. During experiments, steam was injected continuously at a constant rate into the water saturated model and CT scans were taken at six different cross sections of the model

  16. A balanced strategy in managing steam generator thermal performance

    International Nuclear Information System (INIS)

    This paper presents a balanced strategy in managing thermal performance of steam generator designed to deliver rated megawatt thermal (MWt) and megawatt electric (MWe) power without loss with some amount of thermal margin. A steam generator (SG) is a boiling heat exchanger whose thermal performance may degrade because of steam pressure loss. In other words, steam pressure loss is an indicator of thermal performance degradation. Steam pressure loss is mainly a result of either 1) tube scale induced poor boiling or 2) tube plugging historically resulting from tubing corrosion, wear due to flow induced tube vibration or loose parts impact. Thermal performance degradation was historically due to tube plugging but more recently it is due to poor boiling caused by more bad than good constituents of feedwater impurities. The whole SG industry still concentrates solely on maintenance programs towards preventing causes for tube plugging and yet almost no programs on maintaining adequate boiling of fouled tubes. There can be an acceptable amount of tube scale that provides excellent boiling capacity without tubing corrosion, as operational experience has repeatedly demonstrated. Therefore, future maintenance has to come up balanced programs for allocating limited resources in both maintaining good boiling capacity and preventing tube plugging. This paper discusses also thermal performance degradation due to feedwater impurity induced blockage of tube support plate and thus subsequent water level oscillations, and how to mitigate them. This paper provides a predictive management of tube scale for maintaining adequate steam pressure and stable water level without loss in MWt/MWe or recovering from steam pressure loss or water level oscillations. This paper offers a balanced strategy in managing SG thermal performance to fulfill its mission. Such a strategy is even more important in view of the industry trend in pursuing extended power uprate as high as 20 percent

  17. Steam generator blowdown system upgrades

    International Nuclear Information System (INIS)

    The steam generator blowdown (SGBD) system is used to remove impurities from the steam generators in order to maintain steam generator (SG) water chemistry within specifications. The original SGBD systems at Diablo Canyon power plant (DCPP) were designed in the early 1970s, and since that time the industry has changed its practices regarding water chemistry. DCPP has operated its SGBD system above its design flow rate. This resulted in a history of high maintenance and unreliable operation. Subsequently, DCPP implemented extensive modifications in order to accommodate the higher industry standard flow rates. These modifications resulted in a more reliable and rugged system. Additionally, significant savings were realized due to an increase in net plant output and a reduction in the required plant makeup water by recovering steam generator blowdown. (author)

  18. Regulation of ageing steam generators

    International Nuclear Information System (INIS)

    Recent years have seen leaks and shutdowns of Canadian CANDU plants due to steam generator tube degradation by mechanisms including stress corrosion cracking, fretting and pitting. Failure of a single steam generator tube, or even a few tubes, would not be a serious safety related event in a CANDU reactor. The leakage from a ruptured tube is within the makeup capacity of the primary heat transport system, so that as long as the operator takes the correct actions, the off-site consequences will be negligible. However, assurance that no tubes deteriorate to the point where their integrity could be seriously breached as result of potential accidents, and that any leakage caused by such an accident will be small enough to be inconsequential, can only be obtained through detailed monitoring and management of steam generator condition. This paper presents the AECB's current approach and future regulatory directions regarding ageing steam generators. (author)

  19. Evolution of design of steam generator for sodium cooled reactors

    International Nuclear Information System (INIS)

    The first sodium cooled reactor was the experimental breeder reactor (EBR-I) in usa which was commissioned in 1951 and was incidentally the first nuclear reactor to generate electrical energy. This was followed by fast breeder reactors in USSR, UK, france, USA, japan, germany and India. The use of sodium as a coolant is due to its low moderation which helps in breeding fissile fuel from fertile materials and also its high heat transfer coefficient at comparatively low velocities. The good heat transfer properties introduce thermal stresses when there are rapid changes in the sodium temperatures. Also sodium has a chemical affinity with air and water. The steam generators for sodium cooled reactors have to allow for these novel conditions and in addition, unlike other components. Choices have to be made whether it is a recirculation type as in most fossil plants or an once through unit, the power rating, shape of the tube (straight, helical, U-tube), materials (Ferritic or austenitic), with free level of sodium or not, sodium on tube side or shell side and so on. With higher pressures and steam temperatures reheating steam after partial expansion in the turbine becomes essential as in conventional turbines. For this purpose the choice of reheating fluid viz sodium or live main steam has to be made. This paper traces the evolution of steam generator designs in the different sodium cooled reactors (chronologically) and the operation experience. 16 figs., 1 tab

  20. Research program plan: steam generators

    International Nuclear Information System (INIS)

    This document presents a plan for research in Steam Generators to be performed by the Materials Engineering Branch, MEBR, Division of Engineering Technology, (EDET), Office of Nuclear Regulatory Research. It is one of four plans describing the ongoing research in the corresponding areas of MEBR activity. In order to answer the questions posed, the Steam Generator Program has been organized with the three elements of non-destructive examination; mechanical integrity testing; and corrosion, cleaning and decontamination

  1. Detection of the high vibration origin in the body of an electrical generator driven by steam turbine applying diagnostic techniques; Deteccion del origen de alta vibracion en el cuerpo de un generador electrico accionado por turbinas de vapor aplicando tecnicas de diagnostico

    Energy Technology Data Exchange (ETDEWEB)

    Martinez Bravo, Fernando (Mexico)

    2007-11-15

    One of the problems that electric generators present is the high vibration due to causes that can go from simple mechanical unbalance, misalignment, mechanical relaxation, resonance or some other interaction that can influence in the system. In this document is presented the vibration analysis of an electric generator with a capacity of 350 MW, driven by a steam turbine composed of three stages (high pressure, intermediate pressure and low pressure) connected to the electric generator through a rigid connection. [Spanish] Uno de los problemas que se presentan en los generadores electricos es la alta vibracion debida a causas que pueden ir desde un simple desbalance mecanico, desalineamiento, aflojamiento mecanico, resonancia o alguna otra interaccion que pueda influir en el sistema. Se presenta en este documento el analisis de vibracion de un generador electrico con una capacidad de 350 MW, impulsado por una turbina de vapor compuesta de tres etapas (alta presion, presion intermedia y baja presion) acopladas al generador electrico a traves de un acoplamiento rigido.

  2. Options for Steam Generator Decommissioning

    International Nuclear Information System (INIS)

    Selecting the best option for decommissioning steam generators is a key consideration in preparing for decommissioning PWR nuclear power plants. Steam Generators represent a discrete waste stream of large, complex items that can lend themselves to a variety of options for handling, treatment, recycling and disposal. Studsvik has significant experience in processing full size Steam Generators at its metal recycling facility in Sweden, and this paper will introduce the Studsvik steam generator treatment concept and the results achieved to date across a number of projects. The paper will outline the important parameters needed at an early stage to assess options and to help consider the balance between off-site and on-site treatment solutions, and the role of prior decontamination techniques. The paper also outlines the use of feasibility studies and demonstration projects that have been used to help customers prepare for decommissioning. The paper discusses physical, radiological and operational history data, Pro and Contra factors for on- and off-site treatment, the role of chemical decontamination prior to treatment, planning for off-site shipments as well as Studsvik experience This paper has an original focus upon the coming challenges of steam generator decommissioning and potential external treatment capacity constraints in the medium term. It also focuses on the potential during operations or initial shut-down to develop robust plans for steam generator management. (authors)

  3. Steam reforming of ethanol

    DEFF Research Database (Denmark)

    Trane-Restrup, Rasmus; Dahl, Søren; Jensen, Anker Degn

    2013-01-01

    Steam reforming (SR) of oxygenated species like bio-oil or ethanol can be used to produce hydrogen or synthesis gas from renewable resources. However, deactivation due to carbon deposition is a major challenge for these processes. In this study, different strategies to minimize carbon deposition on...... Ni-based catalysts during SR of ethanol were investigated in a flow reactor. Four different supports for Ni were tested and Ce0.6Zr0.4O2 showed the highest activity, but also suffered from severe carbon deposition at 600 °C or below. Operation at 600 °C or above were needed for full conversion of...... ethanol over the most active catalysts at the applied conditions. At these temperatures the offgas composition was close to the thermodynamical equilibrium. Operation at high temperatures, 700 °C and 750 °C, gave the lowest carbon deposition corresponding to 30–60 ppm of the carbon in the feed ending as...

  4. Photon steam engines

    International Nuclear Information System (INIS)

    Modern society relies heavily on the conversion of heat into mechanical work. The first heat engines were responsible for the industrial revolution, but behind the scenes they were also fuelling the development of thermodynamics. In 1824 Sadi Carnot's interest in improving the performance of steam engines led him to think about the efficiency of a heat engine in a new and fundamental way. He concluded that the maximum efficiency of a heat engine that absorbs heat from a reservoir at a given temperature, T2, and rejects heat to another reservoir at a lower temperature, T1, is η = 1 - T1/T2. In other words it is impossible to extract work from a single heat bath - a rule that we now know to be a consequence of the second law of thermodynamics. Then came quantum mechanics. Some quantum systems can at first work appear to violate classical thermodynamics basic laws. Now Marlan Scully and coworkers at Texas A and M University and Herbert Walther at the Max-Planck Institute of Quantum optics in Garching have proposed a 'quantum Carnot engine' that displays features that are simply not possible with classical engine. (U.K.)

  5. Using Net-Zero Energy Projects to Enable Sustainable Economic Redevelopment at the Former Brunswick Air Naval Base

    Energy Technology Data Exchange (ETDEWEB)

    Huffman, S.

    2011-10-01

    A Study Prepared in Partnership with the Environmental Protection Agency for the RE-Powering America's Land Initiative: Siting Renewable Energy on Potentially Contaminated Land and Mine Sites. The Brunswick Naval Air Station is a naval air facility and Environmental Protection Agency (EPA) Super Fund site that is being cleaned up, and closed down. The objective of this report is not only to look at the economics of individual renewable energy technologies, but also to look at the systemic benefits that can be gained when cost-effective renewable energy technologies are integrated with other systems and businesses in a community; thus multiplying the total monetary, employment, and quality-of-life benefits they can provide to a community.

  6. Inventory of orphan oil and natural gas wells in the Dover and Gautreau Village areas of Westmorland County, New Brunswick

    International Nuclear Information System (INIS)

    In 1997, the Government of New Brunswick conducted an inventory of orphan wells in the vicinity of Dover and Gautreau Village in Westmorland County. The term orphan wells refers to those oil and natural gas wells which have been abandoned and have no owner. An abandoned well refers to those wells that are no longer active and have been properly plugged. A total of 19 orphan wells were discovered with the help of landowners and historical maps. These wells are believed to have dated from 1860 to 1906. The locations of the wells were determined digitally using the Global Positioning System. The environmental conditions around the orphan wells were evaluated and classified according to a proposed system used by the State of Michigan. The wells were separated into three categories based on the amount of petroleum contamination of soil and water. Water contamination was further divided into contamination of groundwater and surface water. 7 refs., 34 figs

  7. The social and policy contexts of the New Brunswick Declaration on Research Ethics, Integrity, and Governance: a commentary.

    Science.gov (United States)

    van den Hoonaard, Will C

    2013-04-01

    This paper explores the social and policy implications of the "New Brunswick Declaration on Research Ethics, Integrity, and Governance" developed at the Ethics Rupture Summit in Fredericton, N.B., Canada, October 2012. It discusses the Declaration and the Summit in relation to the usual criticism and analysis of research ethics regimes, and considers reasons why the immense prior literature has had little impact on regulatory bodies. Because the Declaration, like the Illinois White Paper, has quickly achieved considerable attention relative to most other such documents, and because much further deliberation has evolved since the Summit, we offer here a commentary on each of the eight principles contained in the Declaration in the hope of further stimulating discussion and consolidating the progress that now seems underway. PMID:23651934

  8. Significance of buried landscape in subsurface migration of DNAPLs: the case of perchloroethylene in the Sussex aquifer, New Brunswick

    International Nuclear Information System (INIS)

    The controlling factors in DNAPL (dense non-aqueous phase liquids) migration were studied. DNAPLs are anthropogenic hydrocarbon liquids that are denser than water and which persist in the subsurface for long periods of time. DNAPLs move under gravity as blobs through pores and fractures until they settle in depressions. A study at Sussex, New Brunswick, showed that dissolved perchloroethylene (PCE) as high as 28.0 microgram/l was detected within the upper aquifer and in concentrations to 1.6 microgram/l within the lower aquifer which served as the main source of municipal water supply. A dispersal plume was identified by contouring PCE concentrations from 72 samples of subsurface water. The shape of the dispersal plume showed that after an initial spill, PCE migration was influenced by a buried river channel cut into the middle aquitard. The study showed that the stratigraphy, conductivity and topography of the subsurface units were the controlling factors in DNAPL migration

  9. Fate of spinosad in litter and soils of a mixed conifer stand in the Acadian forest region of New Brunswick.

    Science.gov (United States)

    Thompson, Dean G; Harris, Brenda J; Lanteigne, Leonard J; Buscarini, Teresa M; Chartrand, Derek T

    2002-02-13

    Spinosad is a natural insecticide, produced via fermentation culture of the actinomycete Saccharopolyspora spinosa, with potential use against a number of forest pests including spruce budworm (Choristoneura fumiferana [Clem]). Persistence of spinosad was determined in terrestrial fate experiments conducted within a semimature stand of black spruce (Picea mariana [Mill.]) and balsam fir (Abies balsamea [L]) in the Acadian forest region of New Brunswick, Canada. Results of experiments established under full coniferous canopy and in a canopy opening indicated that spinosad dissipated rapidly following hyperbolic kinetics in both litter and soils and was not susceptible to leaching. Time to 50% dissipation estimates for spinosyn A ranged from 2.0 to 12.4 days depending upon matrix and experimental conditions. Spinosyn D dissipated to levels below quantitation limits (0.02 microg/g of dry mass) within 7 days in all cases. Sporadic low-level detection of the demethylated metabolites suggested that parent compounds were degraded in situ. PMID:11829646

  10. Long-term Monitoring Program Optimization for Chlorinated Volatile Organic Compound Plume, Naval Air Station Brunswick, Maine

    Science.gov (United States)

    Calderone, G. M.

    2006-12-01

    A long-term monitoring program was initiated in 1995 at 6 sites at NAS Brunswick, including 3 National Priorities List (Superfund) sites. Primary contaminants of concern include chlorinated volatile organic compounds, including tetrachloroethane, trichloroethene, and vinyl chloride, in addition to metals. More than 80 submersible pumping systems were installed to facilitate sample collection utilizing the low-flow sampling technique. Long-term monitoring of the groundwater is conducted to assess the effectiveness of remedial measures, and monitor changes in contaminant concentrations in the Eastern Plume Operable Unit. Long-term monitoring program activities include quarterly groundwater sampling and analysis at more than 90 wells across 6 sites; surface water, sediment, seep, and leachate sampling and analysis at 3 sites; landfill gas monitoring; well maintenance; engineering inspections of landfill covers and other sites or evidence of stressed vegetation; water level gauging; and treatment plant sampling and analysis. Significant cost savings were achieved by optimizing the sampling network and reducing sampling frequency from quarterly to semi- annual or annual sampling. As part of an ongoing optimization effort, a geostatistical assessment of the Eastern Plume was conducted at the Naval Air Station, Brunswick, Maine. The geostatistical assessment used 40 monitoring points and analytical data collected over 3 years. For this geostatistical assessment, EA developed and utilized a database of analytical results generated during 3 years of long-term monitoring which was linked to a Geographic Information System to enhance data visualization capacity. The Geographic Information System included themes for groundwater volatile organic compound concentration, groundwater flow directions, shallow and deep wells, and immediate access to point-specific analytical results. This statistical analysis has been used by the site decision-maker and its conclusions supported a

  11. Proceedings: Fossil steam turbine disc cracking workshop

    Energy Technology Data Exchange (ETDEWEB)

    1991-04-01

    The objectives of the workshop were to review and consolidate the state of the art of cracking in fossil steam turbine discs; to identify further work needed to assist utilities in evaluating fossil turbine discs subject to SCC. Participants included 18 representatives from utilities, 12 representatives from equipment manufacturing organizations, and 5 consultants. Canadian, European, Japanese, and domestic organizations were represented. Topics included: A Review of GE Fossil Shrunk-On Wheel Stress Corrosion Cracking; Effects on Material and Environmental Factors on SCC of NiCrMoV Rotor Steels; SCC Experience of Shrunk On Discs; Studies on SCC For Steam Turbine Rotor and Disc; Advanced Disc-Type LP Turbine Rotors; Recent Experience of Stress Corrosion Cracking in the LP Discs of Fossil-Fired Reheat Turbines; Stress Corrosion of NiCrMoV LP Disc and Shaft Steels Under Cyclic Loading; NYIT'S Focused Approach for Ultrasonically Scanning Steam Turbine Discs; Probabilistic Assessment of Crack Initiation and Growth in Shrunk-On Discs; Low-Pressure Rotor Disc Cracking and Remaining Life Analysis; Assessment of Probability of Survival of Built Up LP Turbine Rotors With Discs Containing Semi-Circular Keyways; Electric Power Research Institute Turbine Disc Inspection Program; Fossil Turbine Disc Inspections--A Utility Dilemma; In-Service Accumulation of Chemicals in the Keyways and Their Effect on Stress Corrosion Cracking of Turbine Discs; Pitting and Compositional Effects on Stress Corrosion Cracking of Turbine Disc Steels; and TVA's Recent Experience With Inspection and Testing of Shrink-On Discs. Individual papers are processed separately for the data bases.

  12. Centrifugal steam-water separator for steam generators

    International Nuclear Information System (INIS)

    This invention concerns a centrifugal steam-water separator for steam generators, using natural circulation. The turbulence chamber includes a perforated venturi composed of a decreasing cone-shaped convergent duct and a cone-shaped divergent diffuser section increasing from the narrowest part to the turbulence chamber outlet. In this way, the jected liquid phase and any particles of solids it may contain can be discharged through the perforations into the annular space formed between the perforated venturi and the vessel to accumulate at the bottom of this annular space for subsequent removal. The advantages of the invention are that the diffuser of the perforated venturi is used as an additional separation path and with the recovery of pressure in mind, and that the water droplets ejected, as well as any particles contained in these droplets discharged or ejected outside the action area of the rotational flow into the annular space, can flow in a practically free way towards the bottom of the interior edge of the containment wall. Because of this, the pressure drop is reduced and the degree of separation improved. The steam-water separator of the invention is therefore particularly suitable for the high power steam generators of nuclear reactor facilities. For a given steam output, it is possible with the lay-out specified in this invention to reduce the required number of separation units

  13. Development of a nuclear steam generator system for gas-cooled reactors for application in oil sands extraction

    International Nuclear Information System (INIS)

    Canada has vast energy reserves in the Oil Sands regions of Alberta and Saskatchewan. Present extraction technologies, such as strip mining, where oil deposits are close to the surface, and Steam Assisted Gravity Drainage (SAGD) technologies for deeper deposits consume significant amounts of energy to produce the bitumen and upgraded synthetic crude oil. Studies have been performed to assess the feasibility of using nuclear reactors as primary energy sources to produce, in particular the steam required for the SAGD deeper deposit extraction process. Presently available reactors fall short of meeting the requirements, in two areas: the steam produced in a 'standard' reactor is too low in pressure and temperature for the SAGD process. Requirements can be for steam as high as 12MPa pressure with superheat; and, 'standard' reactors are too large in total output. Ideally, reactors of output in the range of 400 to 500 MWth, in modules are better suited to Oil Sands applications. The above two requirements can be met using gas-cooled reactors. Generally, newer generation gas-cooled reactors have been designed for power generation, using Brayton Cycle gas turbines run directly from the heated reactor coolant (helium). Where secondary steam is required, heat recovery steam generators have been used. In this paper, a steam generating system is described which uses the high temperature helium from the reactor directly for steam generation purposes, with sufficient quantities of steam produced to allow for SAGD steam injection, power generation using a steam turbine-generator, and with potential secondary energy supply for other purposes such as hydrogen production for upgrading, and environmental remediation processes. It is assumed that the reactors will be in one central location, run by a utility type organization, providing process steam and electricity to surrounding Oil Sands projects, so steam produced is at very high pressure (12 MPa), with superheat, in order to

  14. Development of a nuclear steam generator system for gas-cooled reactors for application in oil sands extraction

    Energy Technology Data Exchange (ETDEWEB)

    Smith, J.; Hart, R.; Lazic, L. [SNC-Lavlin Nuclear Inc. (Canada)

    2009-07-01

    Canada has vast energy reserves in the Oil Sands regions of Alberta and Saskatchewan. Present extraction technologies, such as strip mining, where oil deposits are close to the surface, and Steam Assisted Gravity Drainage (SAGD) technologies for deeper deposits consume significant amounts of energy to produce the bitumen and upgraded synthetic crude oil. Studies have been performed to assess the feasibility of using nuclear reactors as primary energy sources to produce, in particular the steam required for the SAGD deeper deposit extraction process. Presently available reactors fall short of meeting the requirements, in two areas: the steam produced in a 'standard' reactor is too low in pressure and temperature for the SAGD process. Requirements can be for steam as high as 12MPa pressure with superheat; and, 'standard' reactors are too large in total output. Ideally, reactors of output in the range of 400 to 500 MWth, in modules are better suited to Oil Sands applications. The above two requirements can be met using gas-cooled reactors. Generally, newer generation gas-cooled reactors have been designed for power generation, using Brayton Cycle gas turbines run directly from the heated reactor coolant (helium). Where secondary steam is required, heat recovery steam generators have been used. In this paper, a steam generating system is described which uses the high temperature helium from the reactor directly for steam generation purposes, with sufficient quantities of steam produced to allow for SAGD steam injection, power generation using a steam turbine-generator, and with potential secondary energy supply for other purposes such as hydrogen production for upgrading, and environmental remediation processes. It is assumed that the reactors will be in one central location, run by a utility type organization, providing process steam and electricity to surrounding Oil Sands projects, so steam produced is at very high pressure (12 MPa), with

  15. High-speed 800 MW steam turbine for NPP's

    International Nuclear Information System (INIS)

    The design of the K-750-65/3000 80O MW wet steam turbine intended for the RBMK-1500 reactor is described. This turbine consists of four-double-flow low pressure cylinders situated in pairs on both sides of the high pressure double-flow cylinder. The low pressure cylinders power constitutes 60% of th total power. The wet steam from the reactor drum-separators und r 6.37 MPa pressure comes through four pipes and through two units of shut-off regulating valves to the high pressure cylinder from which under the 0.52 MPa pressure and 0.85 steam dryness factor through four receivers it goes into single-stage separators sfeam superheaters (where the steam bled from the valve units in used as a heating agent); then the steam at 263 deg C and 0.99 dryne s factor goes through four receivers to four low pressure cylinders and than to the steam condensers (the cooling surface of each being 16.560 m2). The condensate at 30 deg C is heated seen-by-step up to 165 deg C in five low pressure heaters by mean of turbine steam bleeding; then it goes to the high-pressure (up to 1.2 MPa) deaerators (for the first time in the home practic ), where it is heated up to 187 deg C and fed to a suction manif ld of feed pumps and from them at 189 deg C to the drum-separat rs, The supply of 175 MWsub((f)) for the needs of the plant proper at the 175/80 deg C temperature schedule of the interme iate circuit is ensured by the three-stage boiler installation fe by the turbine steam bleeding. The high pressure cylinder vessel in the middle, the hoest part is made double-walled. The external casing is steel. The vessel sealing system guarantees preventi n from radioactive steam leaks. Using the K-750-65/3000 tur ine designed on the base of the K-500-65/3000 turbine by improving the low pressure cylinder permits to decrease the specific metal consumption by 10%, to increase power 1.5 time and decrease the heat rate for electric energy production by 2%

  16. Modernization of steam turbines for improved performance

    Energy Technology Data Exchange (ETDEWEB)

    Irwin, A.S. [GEC ALSTHOM, Rugby (United Kingdom)

    1997-12-31

    The high degree of competition in today`s electricity markets has led to increasing interest in cost-effective methods of improving the performance of existing generating plant. For steam turbines, such improvements can lead to a reduction in fuel consumption and/or an increase in generated output. In an industry that is becoming ever more ecologically aware, these benefits can result in reduced emissions. Retrofitting or replanting steam turbines (replacing parts of old turbines with their modern equivalent) has the added attraction of rejuvenating older plant, thereby extending the life of a machine and reducing the need for costly outages to inspect components towards the end of their design life. Increased turbine efficiency through retrofitting is possible in a wide variety of ways, from small modifications to complete cylinder replacement. GEC ALSTHOM has extensive involvement in turbine retrofits, both of their own and competitors` plant. This has led to a wide experience of implementing such schemes and accurately assessing and achieving the potential performance improvements. This paper examines the ways in which turbine design has recently developed and describes several examples of how new technology is being applied to improve the efficiency of older machines. 2 refs., 12 figs., 1 tab.

  17. Flow Characteristics Analysis of Widows' Creek Type Control Valve for Steam Turbine Control

    International Nuclear Information System (INIS)

    The steam turbine converts the kinetic energy of steam to mechanical energy of rotor blades in the power conversion system of fossil and nuclear power plants. The electric output from the generator of which the rotor is coupled with that of the steam turbine depends on the rotation velocity of the steam turbine bucket. The rotation velocity is proportional to the mass flow rate of steam entering the steam turbine through valves and nozzles. Thus, it is very important to control the steam mass flow rate for the load following operation of power plants. Among various valves that control the steam turbine, the control valve is most significant. The steam flow rate is determined by the area formed by the stem disk and the seat of the control valve. While the ideal control valve linearly controls the steam mass flow rate with its stem lift, the real control valve has various flow characteristic curves pursuant to the stem lift type. Thus, flow characteristic curves are needed to precisely design the control valves manufactured for the operating conditions of nuclear power plants. OMEGA (Optimized Multidimensional Experiment Geometric Apparatus) was built to experimentally study the flow characteristics of steam flowing inside the control valve. The Widows' Creek type control valve was selected for reference. Air was selected as the working fluid in the OMEGA loop to exclude the condensation effect in this simplified approach. Flow characteristic curves were plotted by calculating the ratio of the measured mass flow rate versus the theoretical mass flow rate of the air. The flow characteristic curves are expected to be utilized to accurately design and operate the control valve for fossil as well as nuclear plants. (authors)

  18. Microfabricated rankine cycle steam turbine for power generation and methods of making the same

    Science.gov (United States)

    Frechette, Luc (Inventor); Muller, Norbert (Inventor); Lee, Changgu (Inventor)

    2009-01-01

    In accordance with the present invention, an integrated micro steam turbine power plant on-a-chip has been provided. The integrated micro steam turbine power plant on-a-chip of the present invention comprises a miniature electric power generation system fabricated using silicon microfabrication technology and lithographic patterning. The present invention converts heat to electricity by implementing a thermodynamic power cycle on a chip. The steam turbine power plant on-a-chip generally comprises a turbine, a pump, an electric generator, an evaporator, and a condenser. The turbine is formed by a rotatable, disk-shaped rotor having a plurality of rotor blades disposed thereon and a plurality of stator blades. The plurality of stator blades are interdigitated with the plurality of rotor blades to form the turbine. The generator is driven by the turbine and converts mechanical energy into electrical energy.

  19. Quality Assurance for Consumers of Private Training Programs. Findings and Recommendations from the Consultation on the Regulation and Support of Training Providers in New Brunswick = Assurance de la qualite pour les consommateurs de programmes de formation du secteur prive. Resultats et recommandations a la suite des consultations relativement a la reglementation et au soutien des fournisseurs de cours de formation au Nouveau-Brunswick.

    Science.gov (United States)

    New Brunswick Labour Force Development Board, Fredericton.

    Eighteen key individuals from the business, labor, and training sectors and other organizations concerned with the purchase of private training programs were consulted in an effort to determine the role of Canada's federal government and New Brunswick's provincial government in quality assurance for consumers of private training programs. There…

  20. Review of Evaluative Mechanisms in the Departments of Advanced Education and Labour and Human Resources Development--New Brunswick = Examen des mecanismes d'evaluation au ministere de l'Enseignement superieur et du Travail et au ministere du Developpement des Ressources humaines du Nouveau-Brunswick.

    Science.gov (United States)

    New Brunswick Labour Force Development Board, Fredericton.

    The evaluative mechanisms in the Department of Advanced Education and Labour and Department of Human Resources Development in the Canadian province of New Brunswick were reviewed. Data were gathered from the following: meetings with key staff in each department, briefing session for all key informants, 19 personal interviews, brief review of the…

  1. Steam generator hand hole shielding.

    Science.gov (United States)

    Cox, W E

    2000-05-01

    Seabrook Station is an 1198 MWE Pressurized Water Reactor (PWR) that began commercial operation in 1990. Expensive and dose intensive Steam Generator Replacement Projects among PWR operators have led to an increase in steam generator preventative maintenance. Most of this preventative maintenance is performed through access ports in the shell of the steam generator just above the tube sheet known as secondary side hand holes. Secondary side work activities performed through the hand holes are typically performed without the shielding benefit of water in the secondary side of the steam generator. An increase in cleaning and inspection work scope has led to an increase in dose attributed to steam generator secondary side maintenance. This increased work scope and the station goal of maintaining personnel radiation dose ALARA led to the development of the shielding concept described in this article. This shield design saved an estimated 2.5 person-rem (25 person-Smv) the first time it was deployed and is expected to save an additional 50 person-rem (500 person-mSv) over the remaining life of the plant. PMID:10770158

  2. The effect of steam addition on sulphur trioxide formation during the combustion of liquid fuels

    OpenAIRE

    Suthenthiran, Apputhuray

    1989-01-01

    A study of the kinetics of SO₃ formation has been undertaken in a liquid fuel fired, non-catalytic quartz tube combuster. The effects of excess air, residence time, gas temperature, and steam injection on the level of SO₃produced have been investigated. A non-catalytic quartz tube combuster was built with the required safety precautions. Provisions for maintaining near isothermal conditions along the tube and also injecting steam into the combustion chamberweremade. An electrical...

  3. Optimization of thermoelectric topping combined steam turbine cycles for energy economy

    OpenAIRE

    Yazawa, Kazuaki; Koh, Yee Rui; Shakouri, Ali

    2013-01-01

    A mismatch between the fuel combustion temperature similar to 2250 K (adiabatic) and the high pressure steam temperature up to 900 K, results in a large amount of thermodynamic losses in steam turbine (ST) cycles. A solid-state thermoelectric (TE) placed on top of a ST cycle will produce additional electrical power. By selecting the right materials for the TE generator for high temperature operation, the energy production from the same fuel consumption will increase. Recent nano-structured en...

  4. Effect of Low Pressure End Conditions on Steam Power Plant Performance

    OpenAIRE

    Ali Syed Haider; Baheta Aklilu Tesfamichael; Hassan Suhaimi

    2014-01-01

    Most of the electricity produced throughout the world today is from steam power plants and improving the performance of power plants is crucial to minimize the greenhouse gas emissions and fuel consumption. Energy efficiency of a thermal power plant strongly depends on its boiler-condenser operating conditions. The low pressure end conditions of a condenser have influence on the power output, steam consumption and efficiency of a plant. Hence, the objective this paper is to study the effect o...

  5. Diabetes Case Management in Primary Care: The New Brunswick Experience and Expanding the Practice of the Certified Diabetes Educator Nurse into Primary Care.

    Science.gov (United States)

    Jones, Shelley L

    2015-08-01

    The role of the outreach diabetes case manager in New Brunswick, Canada, was first developed in the Moncton Area of Horizon Health Network in response to a physician-identified gap between patients' diagnoses of diabetes and their attendance at the local diabetes education centre. This model of collaborative interprofessional practice increases support for primary care providers and people living with diabetes in that they are being provided the services of certified diabetes educators who can address knowledge gaps with respect to evidence-based guidelines and best practice, promote advancement of diabetes and chronic-disease management therapies and support adherence to treatment plans and self-management practices. This report chronicles a review of the implementation, expansion and evaluation of the outreach diabetes case manager model in the province of New Brunswick, Canada, along with the rationale for development of the role for registered nurses in other jurisdictions. PMID:25797113

  6. Simulation of steam-water and binary geothermal power plants

    International Nuclear Information System (INIS)

    The generalized scheme of the geothermal power plant (GeoPP), assuming the possibility of the electric power production in the steam-water turbine or in the turbine on the low-boiling working body, is considered. The GeoPP mathematical model, making it possible to carry out the comparison of the power indices of various GeoPP schemes and analysis of the calculational indices sensitivity of these schemes to the mode parameters change, is presented

  7. Steam generator tube laser sleeving

    International Nuclear Information System (INIS)

    ; Weld inspectability through UT examination; Easy and reliable process; Long lifetime of optical equipment (mirrors, lenses, fibers). Considering these criteria we have chosen: working in pseudo-pulsed mode with 50 hz frequency, using nitrogen as protective gas, a welding power of about 600 W, 30 cm/mn advance speed. The laser welding process brings two main additional advantages if we compare it to the GTAW one: Reproducibility of the penetration and resisting cross-section and this, independently of surrounding conditions (fit up strength, tube/plate hard-rolling tightening,...); Flexibility and performances which enable a remote-controlled work with great output. The process consists of five main operations to which two optional ones can be added. These main operations are: Tube cleaning, Sleeve insertion/expansion, Upper and lower joint welding, Weld televisual inspection, Upper assembly stress-relieving process. The optional operations consist of: Tube inlet rework and Weld UT-inspection. The following three main concerns determined the design and installation of industrial laser sleeving means: the reliability, the most reduced dose rate, the output. Outside reactor building you have three containers for: The control-unit consisting of drive and supervision computers as well as video means; The laser unit itself (connected to the welding equipment in steam generator bunker by an optical fiber spreading the power) and its control cabinet; Auxiliary equipments. Inside reactor building you will find the equipments specific to each process (welding-device, brushing-unit, expansion hydraulic generator,...) as well as the electric cabinets connected to control unit. Data flow from outside to inside reactor and vice-versa through an optical fiber. Investigations about these industrial means are not achieved up to now but will be qualified (with EDF collaboration) in the CETIC afterwards and shall be used on a French power plant at the beginning of year 1992

  8. Hybrid systems to address seasonal mismatches between electricity production and demand in nuclear renewable electrical grids

    International Nuclear Information System (INIS)

    A strategy to enable zero-carbon variable electricity production with full utilization of renewable and nuclear energy sources has been developed. Wind and solar systems send electricity to the grid. Nuclear plants operate at full capacity with variable steam to turbines to match electricity demand with production (renewables and nuclear). Excess steam at times of low electricity prices and electricity demand go to hybrid fuel production and storage systems. The characteristic of these hybrid technologies is that the economic penalties for variable nuclear steam inputs are small. Three hybrid systems were identified that could be deployed at the required scale. The first option is the gigawatt-year hourly-to-seasonal heat storage system where excess steam from the nuclear plant is used to heat rock a kilometer underground to create an artificial geothermal heat source. The heat source produces electricity on demand using geothermal technology. The second option uses steam from the nuclear plant and electricity from the grid with high-temperature electrolysis (HTR) cells to produce hydrogen and oxygen. Hydrogen is primarily for industrial applications; however, the HTE can be operated in reverse using hydrogen for peak electricity production. The third option uses variable steam and electricity for shale oil production. -- Highlights: •A system is proposed to meet variable hourly to seasonal electricity demand. •Variable solar and wind electricity sent to the grid. •Base-load nuclear plants send variable steam for electricity and hybrid systems. •Hybrid energy systems can economically absorb gigawatts of variable steam. •Hybrid systems include geothermal heat storage, hydrogen, and shale-oil production

  9. Nuclear reactor steam depressurization valve

    International Nuclear Information System (INIS)

    This patent describes improvement in a nuclear reactor plant, an improved steam depressurization valve positioned intermediate along a steam discharge pipe for controlling the venting of steam pressure from the reactor through the pipe. The improvement comprises: a housing including a domed cover forming a chamber and having a partition plate dividing the chamber into a fluid pressure activation compartment and a steam flow control compartment, the valve housing being provided with an inlet connection and an outlet connection in the steam flow control compartment, and a fluid duct in communication with a source of fluid pressure for operating the valve; a valve set mounted within the fluid flow control compartment comprising a cylindrical section surrounding the inlet connection with one end adjoining the connection and having a radially projecting flange at the other end with a contoured extended valve sealing flange provided with an annular valve sealing member, and a valve cylinder traversing the partition plate and reciprocally movable within an opening in the partition plate with one terminal and extending into the fluid pressure activation compartment and the other terminal end extending into the steam flow control compartment coaxially aligned with the valve seat surrounding the inlet connection, the valve cylinder being surrounded by two bellow fluid seals and provided with guides to inhibit lateral movement, an end of the valve cylinder extending into the fluid flow control compartment having a radially projecting flange substantially conterminous with the valve seat flange and having a contoured surface facing and complimentary to the contoured valve seating surface whereby the two contoured valve surfaces can meet in matching relationship, thus providing a pressure actuated reciprocatable valve member for making closing contact with the valve seat and withdrawing therefrom for opening fluid flow through the valve

  10. Direct Steam Generation with parabolic trough collectors. The project Direct Solar Steam (DISS); Generacion directa de vapor con colectores solares cilindro parabolicos proyectos directo solar steam (DISS)

    Energy Technology Data Exchange (ETDEWEB)

    Zarza Moya, E.

    2004-07-01

    Steam generation at high pressure and temperature inside the absorber pipes of parabolic trough solar collector, the so-called DSG process, is a very interesting option because it could lead to a significant reduction of the cost of electricity produced with parabolic trough solar power plants. This book includes an overview of the advantages and disadvantages of the DSG process when compared with the current HTF technology, which is based in the use of oil that acts a working fluid in the solar collectors and heat transfer medium between the solar field and the Rankine water/steam cycle where electricity is produced. The book also includes a summary of all the R+D DSG-related projects developed in the world before the project DISS, which was developed at the Plataforma Solar de Almeria (Spain) from 1996 to 2001. After explanation of the plan of work and objectives of the DISS project, an experimental study of the thermal gradients existing in the absorber pipes of parabolic trough collectors with DSG is performed in the book, evaluating the influence of the operation parameters on the thermal gradients that happens in the three sections that compose a typical DSG solar field: water preheating evaporation and steam superheating. Finally, this book includes an study of the influence of the operation parameters on the stratification of the liquid phase inside the absorber pipes within the evaporating section of the solar field. (Author)

  11. Diverse configurations of the boiler feed pump drive for the ultra-supercritical 900-MW steam plant

    Energy Technology Data Exchange (ETDEWEB)

    Stepczynska, Katarzyna; Lukowicz, Henryk; Dykas, Slawomir [Silesian Univ. of Technology, Gliwice (Poland). Inst. of Power Engineering and Turbomachinery

    2012-07-01

    Coal-based electric power generation remains the basic source of obtaining energy. With increasing pressure to reduce CO{sub 2} emissions, improving power unit efficiency has become an issue of utmost significance. Surely, one of the possibilities to improve the efficiency of new power units is raising the steam parameters. With improved power plant efficiency, there is a lower demand for power of almost all auxiliary equipment except the boiler feed pump. The reason for this is that the power needed to drive the feed pump is an almost linear function of the steam pressure. This means that, even though the steam mass flow (and, consequently, the feed water mass flow) is reduced and the efficiency of feed pumps is improved, their power increases. For this reason, it is very important to find the optimum drive of the boiler feed pump. The main aim of the conducted analysis was to compare various drive options of the boiler feed pump for a conceptual ultra-supercritical 900-MW steam power unit. The following drive configurations of the boiler feed pump were presented and compared: - A frequency-controlled electric motor - A condensing turbine fed with steam extraction from the immediate-pressure turbine - An extraction-backpressure turbine fed with steam from a cold reheat steam line with bleeds shifted from the low-pressure turbine - A backpressure turbine fed with steam from a hot reheat steam line operating in parallel with the intermediate-pressure turbine - An extraction-backpressure turbine fed with steam from a cold reheat steam line with bleeds shifted from the intermediate-pressure turbine (the master cycle idea). The analysis of the operation of the 900-MW unit with various configurations of the feed pump drive was carried out for three load levels: for the nominal mass flow of live steam and for the partial mass flow of 75% and 50%. (orig.)

  12. Steam turbines for PWR stations

    International Nuclear Information System (INIS)

    The thermodynamic cycle requirements and mechanical design features applying to modern GEC 3000 rev/min steam turbines for pressurised water reactor power stations are reviewed. The most recent developments include machines of 630 MW and 985 MW output which are currently under construction. The importance of service experience with nuclear wet steam turbines associated with a variety of types of water cooled reactor and its relevance to the design of modern 3000 rev/min turbines for pressurised water reactor applications is emphasised. (author)

  13. Steam generators: learning from experience

    International Nuclear Information System (INIS)

    The North Anna power plant in Virginia, USA, comprises two PWR units. Each employs three Westinghouse series 51 steam generators. New lower steam generator assemblies, with 3592 tubes made of thermally treated Alloy 690, were installed in 1993, replacing the original assemblies which contained 3388 tubes of mild annealed Alloy 600. Since then, the operators have been engaged in planning a similar replacement for unit 2. This article examines how lessons learned in the unit 1 replacement are being taken into account. It is hoped to improve performance by 30% in the unit 2 replacement which is scheduled to start in September 1996. (UK)

  14. Steam pretreatment for coal liquefaction

    Science.gov (United States)

    Ivanenko, Olga

    The objectives of this work are to test the application of steam pretreatment to direct coal liquefaction, to investigate the reaction of model compounds with water, and to explore the use of zeolites in these processes. Previous work demonstrated the effectiveness of steam pretreatment in a subsequent flash pyrolysis. Apparently, subcritical steam ruptures nearly all of the ether cross links, leaving a partially depolymerized structure. It was postulated that very rapid heating of the pretreated coal to liquefaction conditions would be required to preserve the effects of such treatment. Accordingly, a method was adopted in which coal slurry is injected into a hot autoclave containing solvent. Since oxygen is capable of destroying the pretreatment effect, precautions were taken for its rigorous exclusion. Tests were conducted with Illinois No. 6 coal steam treated at 340sp°C, 750 psia for 15 minutes. Both raw and pretreated samples were liquified in deoxygenated tetralin at high severity (400sp°C, 30 min.) and low severity (a: 350sp°C, 30 min., and b: 385sp°C, 15 min.) conditions under 1500 psia hydrogen. Substantial improvement in liquid product quality was obtained and the need for rapid heating and oxygen exclusion demonstrated. Under low severity conditions, the oil yield was more than doubled, going from 12.5 to 29 wt%. Also chemistry of the pretreatment process was studied using aromatic ethers as model compounds. alpha-Benzylnaphthyl ether (alpha-BNE), alpha-naphthylmethyl phenyl (alpha-NMPE), and 9-phenoxyphenanthrene were exposed to steam and inert gas at pretreatment conditions and in some cases to liquid water at 315sp°C. alpha-BNE and alpha-NMPE showed little difference in conversion in inert gas and in steam. Hence, these compounds are poor models for coal in steam pretreatment. Thermally stable 9-phenoxyphenanthrene, however, was completely converted in one hour by liquid water at 315sp°C. At pretreatment conditions mostly rearranged starting

  15. Temperate forest as a carbon-storage reservoir for carbon dioxide emitted by coal-fired generating stations - a case study for New Brunswick, Canada

    International Nuclear Information System (INIS)

    The potential use of a temperature forest to compensate for CO2 emissions from a coal-fired generating station is discussed, with the province of New Brunswick, Canada developed as a case study. Each year a 200 MW generating station would emit a calculated 0.34 x 106t C. To offset this emission with aggrading biomass carbon of typical, unmanaged, mature forest in New Brunswick, the reserve area would have to have an area of about (4.7 x 105) ha, equivalent to 8% of the forested area of that province. Because agricultural sites start from a much smaller base of fixed carbon, a smaller area of reserve would be required if such land were to be reforested, about (0.72 x 105) ha of conifer plantation on high-quality sites or (1.9 x 105)has of unmanaged regeneration. Compensatory forest reserves must be protected from catastrophic disturbance by harvesting, fire, or insect defoliation in order to maintain fixed C in an organic reservoir. Additional C-storage gains could be realized by allowing continued succession towards an old-growth stage of development, and by making silvicultural investments to increase the rate of net carbon fixation in mature stands. Overall, however, the area of land that would have to be reserved to compensate for carbon emissions from a 200 MW coal-fired generating station would be very large, and would require unrealistic changes in existing land use in New Brunswick

  16. Restoring a Classic Electric Car

    Science.gov (United States)

    Kraft, Thomas E.

    2012-01-01

    One hundred years ago, automobiles were powered by steam, electricity, or internal combustion. Female drivers favored electric cars because, unlike early internal-combustion vehicles, they did not require a crank for starting. Nonetheless, internal-combustion vehicles came to dominate the industry and it's only in recent years that the electrics…

  17. Steam Digest 2001: Office of Industrial Technologies

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2002-01-01

    Steam Digest 2001 chronicles Best Practices Program's contributions to the industrial trade press for 2001, and presents articles that cover technical, financial and managerial aspects of steam optimization.

  18. Auxiliary steam supply and process steam extraction at the combined-cycle unit Moerdijk/The Netherlands

    Energy Technology Data Exchange (ETDEWEB)

    Toebes, J.A.; Beker, M.J.W.; Puts, J.J.

    1998-07-01

    The first combined-cycle plant to be operated in combination with a waste-to-energy (WTE) plant has been built by the Dutch electric power utility N.V. Electriciteits-Produktiemaatschappij Zuid-Nederland (N.V. EPZ). Steam generated by the combustion of municipal waste is supplied to the heat recovery steam generators of the combined cycle unit. In addition to generating electric power for the public grid, the plant also supplies process steam to a neighboring chemical plant. The combination results in nearly 70% utilization of the energy contained in the natural gas fuel. The plant has a maximum electrical output of 339 MW and reduces annual natural gas consumption by approximately 40 million cubic meters which corresponds to a CO{sub 2} emission reduction of nearly 100,000 metric tons per year. The combined-cycle plant started operation in mid 1996 and during the first two years of operation showed heat consumption and emission levels in conformity with requirements. This paper presents the integrated concept and the main operating results.

  19. Resilient decision making in steam network investments

    OpenAIRE

    Bungener, Stéphane Laurent; Van Eetvelde, Greta Martha; Descales, Bernard; Maréchal, François

    2015-01-01

    Steam is a key energy vector for industrial sites, used for process heating, direct injection and stripping, tracing and cogeneration of mechanical power. Steam networks transport steam from producers to consumers and across different pressure levels. The steam production equipments (boilers, cogeneration units and heat exchangers) should be dimensioned to always supply key consumers as well as to deal with extreme demand caused by exceptional events such as unit startups or extreme weather. ...

  20. Colour Homogenisation of Hardwood Species by Steaming

    OpenAIRE

    TOLVAJ, László; MOLNÁR, Sándor

    2006-01-01

    For colour homogenisation three hardwood species, black locust (Robinia pseudoacaciaL.), beech (Fagus silvatica L.) and Turkey oak (Quercus cerris L.) were investigated. Steaming wasapplied to change the colour. Steaming parameters (steaming time and temperature) were varied tofind the optimum of treatment. The results are given in the CIE L*, a*, b* colour co-ordinate system.Black locust wood was most sensitive to the steaming temperature. With rising temperature, the colourchange was faster...

  1. FAILED STEAM TRAPS: FIRST STEPS TO REPLACEMENT

    OpenAIRE

    Ian Noble-Jack; Kant E Kanyarusoke

    2012-01-01

    Current Energy, Environmental and Economic concerns are exerting pressure on steam plant managers to re examine their plant maintenance practices.In South Africa, big components of the steam line such as boilers have always received legitimate attention. But, the smaller ones – especially Steam Traps – have tended to be taken for granted. A Literature search revealed lack of adequate Trap knowledge in industry - with the result that up to 55% of steam in some plants is lost through them! In t...

  2. Dynamic simulation analyzes expanded refinery steam system

    Energy Technology Data Exchange (ETDEWEB)

    Gandhi, S.L.; Graham, J.; Duffield, M.A.; Cortes, R.M. [M.W. Kellogg Co., Houston, TX (United States)

    1995-11-01

    There is a rising demand for more-stable process operations with increasing facility modernization and automation. This requires steam system controls that provide effective and stable responses to operational disturbances. Today it is possible to use dynamic simulation analysis for designing steam systems. The main objectives were to: develop a high-fidelity dynamic simulation model of the steam system and its associated controls; develop dynamic system responses to major plant disturbances; and assist in designing new control strategies and modifying existing controls to minimize the impact of plant upsets on system performance. The steam system for this project included two power plant supplying steam and power and a steam pipe network comprising three levels of steam with stream flows to and from process units spread over several square kilometers. Whether the steam system and its controls would respond effectively to major operational upsets, such as boiler, steam turbogenerator or process gas compressor trips, or a steep increase in steam demand, can only be determined from evaluating dynamic responses to these incidents. The model consisted of about 5,000 equations, 1,000 parameters and data items, and was used for evaluating steam system responses to various operational upset scenarios. The responses were used to identify limitations of the as designed control system. The model also proved to be an effective tool for verifying adequacy of the proposed recommendations. These included modifications to control valve letdown stations, steam turbogenerator governor controls and the boiler master-pressure controller.

  3. Parametric study for horizontal steam generator modelling

    Energy Technology Data Exchange (ETDEWEB)

    Ovtcharova, I. [Energoproekt, Sofia (Bulgaria)

    1995-12-31

    In the presentation some of the calculated results of horizontal steam generator PGV - 440 modelling with RELAP5/Mod3 are described. Two nodalization schemes have been used with different components in the steam dome. A study of parameters variation on the steam generator work and calculated results is made in cases with separator and branch.

  4. Containment steam blowdown analysis: experimental and numerical comparisons

    International Nuclear Information System (INIS)

    This paper compares the numerical simulation with the experimental data of a steam blowdown event in a light water reactor containment building. A three step approach was used to analyze the steam jet behavior. First, the temperature and pressure data of a stem blowdown event was measured at the Purdue University Multi-Dimensional Integrated Test Assembly (PUMA), a scaled model of the General Electric Simplified Boiling Water Reactor. Second, a 1-Dimensional, system level RELAP5/Mod3.2 model of the steam blowdown event was created and the results used to set the initial conditions for the PUMA blowdown experiments. Finally, 2-Dimensional and 3-Dimensional CFD models of the discharged steam jets were computed using PHOENICS, a commercially available CFD package. It was found that RELAP5 is reasonably capable in predicting the general temperature and pressure trends in the RPV. However, due to modeling compromises and the code's built-in capabilities, RELAP5 1-Dimensional predictions of containment temperature and pressure did not compare well with measured data. On the other hand, with minor modifications to the k-ε turbulence model, the 2-Dimensional and 3-Dimensional PHOENICS CFD solutions compared extremely well with the measured data. (author)

  5. Burnout in steam-water flow on horizontal tubes

    International Nuclear Information System (INIS)

    The mechanism of the burnout occurrence in a steam-fluid medium flowing about a horizontal steam-generating tube is analysed. The analysis is based on the burnout hydrodynamic nature. A formula for calculation of the critical heat flux is obtained that is correlated with experimental data. The experiments have been performed with horizontal electrically heated tubes, with 6 and 16 mm external diameter. The tube, 6 mm in diameter, was situated in a planar vertical 11 mm wide slit. The experiments have been conducted at the 0.1 MPa pressure, 0.058 and 1.25 m/s steam flow rate and 0.95% void fraction. The 16 mm diameter tube was mounted in the upper row of the horizontal bundle of 32 such tubes arranged at a 40 mm pitch in a vertical slit 37 mm wide. The experiments with this tube have been performed under 7.5 MPa pressure, 0.4 m/s flow rate and 0.65% void fraction. Under operating conditions investigated the suggested formula may be recommended for calculating critical heat fluxes in steam generators and heat exhangers with boiling coolants in the intertube space of horizontal bundles of tubes

  6. Steam-water relative permeability

    Energy Technology Data Exchange (ETDEWEB)

    Ambusso, W.; Satik, C.; Home, R.N. [Stanford Univ., CA (United States)

    1997-12-31

    A set of relative permeability relations for simultaneous flow of steam and water in porous media have been measured in steady state experiments conducted under the conditions that eliminate most errors associated with saturation and pressure measurements. These relations show that the relative permeabilities for steam-water flow in porous media vary approximately linearly with saturation. This departure from the nitrogen/water behavior indicates that there are fundamental differences between steam/water and nitrogen/water flows. The saturations in these experiments were measured by using a high resolution X-ray computer tomography (CT) scanner. In addition the pressure gradients were obtained from the measurements of liquid phase pressure over the portions with flat saturation profiles. These two aspects constitute a major improvement in the experimental method compared to those used in the past. Comparison of the saturation profiles measured by the X-ray CT scanner during the experiments shows a good agreement with those predicted by numerical simulations. To obtain results that are applicable to general flow of steam and water in porous media similar experiments will be conducted at higher temperature and with porous rocks of different wetting characteristics and porosity distribution.

  7. Maintenance of Power Steam Turbine

    OpenAIRE

    Kapelovich, Boris; Khmelnik, Solomon; Kapelovich, David; Benenson, Evgeny

    2008-01-01

    The diagnostics system of the power steam turbine is offered. It can be executed also in the form of telediagnostic system. The system is presented on a site http://turbo.mic34.com/ System engineering can is ordered to authors.

  8. Engineering Analysis of Flow Characteristic Curve for Steam Turbine Control Valve

    International Nuclear Information System (INIS)

    The steam turbine converts the kinetic energy of steam to mechanical energy of rotor blades in the power conversion system of fossil and nuclear power plants. The electric output from the generator of which the rotor is coupled with that of the steam turbine depends on the rotation velocity of the steam turbine bucket. The rotation velocity is proportional to the mass flow rate of steam entering the steam turbine through valves and nozzles. Thus, it is crucial to control the steam mass flow rate for the load following operation of power plants. Among various valves that control the steam flow to the turbine, the control valve is certainly the most significant. The steam flow rate is determined by the area formed by the stem disk and the seat of the control valve. While the ideal control valve linearly controls the steam mass flow rate with its stem lift, the real control valve has various flow characteristic curves pursuant to the stem lift. Thus, flow characteristic curves are needed to precisely design the control valves manufactured for the operating conditions of power plants. It has long been a practice to depend upon experimental means to obtain valve characteristic curves, due mostly to limited computational capability of computational fluid dynamics (CFD) codes. In this paper, a CFD code, FLUENT, was used to obtain the valve characteristic curve, whose results were validated against the data from the OMEGA (Optimized Multidimensional Experiment Geometric Apparatus) tests and operating plants. The Widow's Creek type control valve was the reference model. The computational and experimental results were translated to flow characteristic curve by rectifying the ratio of actual mass flow rate versus the theoretical mass flow rate. It is expected that future control valve design may well benefit from the multidimensional computational results spanning a wide spectrum of thermo hydrodynamic conditions involving the valve size and configuration as well as the inlet

  9. Steam Greenlight for first-time developers : explaining Steam Greenlight from a game developer's perspective

    OpenAIRE

    Eloranta, Minna

    2016-01-01

    The purpose of this thesis is to go through the Steam Greenlight process and clarify misinformation and correct beliefs on the platform. The thesis proposes improvement ideas based on the findings of the research conducted. Steam Greenlight was created in 2012 by Valve Corporation and determines which new games can be available in the Steam Store. Steam users can vote on games which improves the games' chances of getting through Greenlight. Steam Greenlight has been created to enable ...

  10. 76 FR 3587 - Standards of Performance for Fossil-Fuel-Fired, Electric Utility, Industrial-Commercial...

    Science.gov (United States)

    2011-01-20

    ... AGENCY 40 CFR Part 60 RIN 2060-AQ46 Standards of Performance for Fossil-Fuel-Fired, Electric Utility... 221112 Fossil fuel-fired electric utility steam generating units. Federal Government 22112 Fossil fuel... government 22112 Fossil fuel-fired electric utility steam generating units owned by municipalities....

  11. Cycle improvement for nuclear steam power plant

    International Nuclear Information System (INIS)

    A pressure-increasig ejector element is disposed in an extraction line intermediate to a high pressure turbine element and a feedwater heater. The ejector utilizes high pressure fluid from a reheater drain as the motive fluid to increase the pressure at which the extraction steam is introduced into the feedwater heater. The increase in pressure of the extraction steam entering the feedwater heater due to the steam passage through the ejector increases the heat exchange capability of the extraction steam thus increasing the overall steam power plant efficiency

  12. Steam plant for producing drinking water from seawater. Dampfkraftanlage zur Erzeugung von Trinkwasser aus Meerwasser

    Energy Technology Data Exchange (ETDEWEB)

    Kuenstle, K.; Lezuo, A.

    1984-04-05

    In order to be able to match a seawater desalination plant to different conditions of the electrical mains supply while maintaining the overall efficiency of the plant, the vapour compressor is driven by a steam turbine, which is coupled via an electric generator or motor to the electrical mains supply; also heat exchangers for cooling the brine and/or the destillate are situated in the seawater feedpipe to a bypass.

  13. International examples of steam generator replacement

    International Nuclear Information System (INIS)

    Since 1979-1980 a total of twelve nuclear power plants world-wide have had their steam generators replaced. The replacement of the Combustion steam generators in the Millstone-2 plant in the United States was completed very recently. Steam generator replacement activities are going on at present in four plants. In North Anna, the steam generators have been under replacement since January 1990. In Japan, preparations have been started for Genkai-1. Since January 1992, the two projects in Beznau-1, Switzerland, and Doel-3, Belgium, have bee planned and executed in parallel. Why steam generator replacement? There are a number of defect mechanisms which give rise to the need for early steam generator replacement. One of the main reasons is the use of Inconel-600 as material for the heating tubes. Steam generator heating tubes made of Inconel-600 have been known to exhibit their first defects due to stress corrosion cracking after less than one year of operation. (orig.)

  14. Steam generator materials performance in high temperature gas-cooled reactors

    International Nuclear Information System (INIS)

    This paper reviews the materials technology aspects of steam generators for HTGRs which feature a graphite-moderated, uranium-thorium, all-ceramic core and utilizes high-pressure helium as the primary coolant. The steam generators are exposed to gas-side temperatures approaching 7600C and produce superheated steam at 5380C and 16.5 MPa (2400 psi). The prototype Peach Bottom I 40-MW(e) HTGR was operated for 1349 EFPD over 7 years. Examination after decommissioning of the U-tube steam generators and other components showed the steam generators to be in very satisfactory condition. The 330-MW(e) Fort St. Vrain HTGR, now in the final stages of startup, has achieved 70% power and generated more than 1.5 x 106 MWh of electricity. The steam generators in this reactor are once-through units of helical configuration, requiring a number of new materials factors including creep-fatigue and water chemistry control. Current designs of larger HTGRs also feature steam generators of helical once-through design. Materials issues that are important in these designs include detailed consideration of time-dependent behavior of both base metals and welds, as required by current American Society of Mechanical Engineers (ASME) Code rules, evaluation of bimetallic weld behavior, evaluation of the properties of large forgings, etc

  15. Steam generator design and development for a helium-cooled modular HTR

    International Nuclear Information System (INIS)

    A modular helium cooled high temperature reactor system with a thermal output of 200 MW per reactor has been developed by the KWU group for cogeneration of electricity and process steam. For this system a steam generator producing superheated steam of 190 bar, 530 deg. C is under development in cooperation with the component supplying industry. The steam generator is heated by helium of 60 bar pressure and 700 deg. C inlet temperature. The design of the cross-counterflow helical tube bundle steam generator will be described. Thermal hydraulic aspects and helium flow distribution problems are considered. Special attention is paid to the interaction of the tube bundle with the steel pressure vessel which serves as the primary system boundary. The presented design is to a large extend supported by operational experience from a 10 MW steam generator prototype which is in operation in the Interatom test facility KVK at helium temperatures even up to 900 deg. C. Some test results and their application to the 200 MW steam generator will be presented. (author)

  16. Multiple modes of water quality impairment by fecal contamination in a rapidly developing coastal area: southwest Brunswick County, North Carolina.

    Science.gov (United States)

    Cahoon, Lawrence B; Hales, Jason C; Carey, Erin S; Loucaides, Socratis; Rowland, Kevin R; Toothman, Byron R

    2016-02-01

    Fecal contamination of surface waters is a significant problem, particularly in rapidly developing coastal watersheds. Data from a water quality monitoring program in southwest Brunswick County, North Carolina, gathered in support of a regional wastewater and stormwater management program were used to examine likely modes and sources of fecal contamination. Sampling was conducted at 42 locations at 3-4-week intervals between 1996 and 2003, including streams, ponds, and estuarine waters in a variety of land use settings. Expected fecal sources included human wastewater systems (on-site and central), stormwater runoff, and direct deposition by animals. Fecal coliform levels were positively associated with rainfall measures, but frequent high fecal coliform concentrations at times of no rain indicated other modes of contamination as well. Fecal coliform levels were also positively associated with silicate levels, a groundwater source signal, indicating that flux of fecal-contaminated groundwater was a mode of contamination, potentially elevating FC levels in impacted waters independent of stormwater runoff. Fecal contamination by failing septic or sewer systems at many locations was significant and in addition to effects of stormwater runoff. Rainfall was also linked to fecal contamination by central sewage treatment system failures. These results highlight the importance of considering multiple modes of water pollution and different ways in which human activities cause water quality degradation. Management of water quality in coastal regions must therefore recognize diverse drivers of fecal contamination to surface waters. PMID:26769702

  17. Rapid Risk Evaluation (ER2) Using MS Excel Spreadsheet: a Case Study of Fredericton (new Brunswick, Canada)

    Science.gov (United States)

    McGrath, H.; Stefanakis, E.; Nastev, M.

    2016-06-01

    Conventional knowledge of the flood hazard alone (extent and frequency) is not sufficient for informed decision-making. The public safety community needs tools and guidance to adequately undertake flood hazard risk assessment in order to estimate respective damages and social and economic losses. While many complex computer models have been developed for flood risk assessment, they require highly trained personnel to prepare the necessary input (hazard, inventory of the built environment, and vulnerabilities) and analyze model outputs. As such, tools which utilize open-source software or are built within popular desktop software programs are appealing alternatives. The recently developed Rapid Risk Evaluation (ER2) application runs scenario based loss assessment analyses in a Microsoft Excel spreadsheet. User input is limited to a handful of intuitive drop-down menus utilized to describe the building type, age, occupancy and the expected water level. In anticipation of local depth damage curves and other needed vulnerability parameters, those from the U.S. FEMA's Hazus-Flood software have been imported and temporarily accessed in conjunction with user input to display exposure and estimated economic losses related to the structure and the content of the building. Building types and occupancies representative of those most exposed to flooding in Fredericton (New Brunswick) were introduced and test flood scenarios were run. The algorithm was successfully validated against results from the Hazus-Flood model for the same building types and flood depths.

  18. Geographic specificity of Aroclor 1268 in bottlenose dolphins (Tursiops truncatus) frequenting the Turtle/Brunswick River Estuary, Georgia (USA)

    International Nuclear Information System (INIS)

    Coastal marine resources are at risk from anthropogenic contaminants, including legacy persistent organic pollutants (POPs) with half-lives of decades or more. To determine if polychlorinated biphenyl (PCB) signatures can be used to distinguish among local populations of inshore bottlenose dolphins (Tursiops truncatus) along the southeastern U.S. coast, blubber from free-ranging and stranded animals were collected along the Georgia coast in 2004 and analyzed for PCB congeners using gas chromatography with electron capture and negative chemical ionization mass spectrometric detection (GC-ECD and GC-NCI-MS). Mean total PCB concentrations (77 ± 34 μg/g lipid) were more than 10 fold higher and congener distributions were highly enriched in Cl7-Cl10 homologs in free-ranging animals from the Turtle/Brunswick River estuary (TBRE) compared with strandings samples from Savannah area estuaries 90 km to the north. Using principal components analysis (PCA), the Aroclor 1268 signature associated with TBRE animals was distinct from that observed in Savannah area animals, and also from those in animals biopsied in other southeastern U.S estuaries. Moreover, PCB signatures in dolphin blubber closely resembled those in local preferred prey fish species, strengthening the hypothesis that inshore T. truncatus populations exhibit long-term fidelity to specific estuaries and making them excellent sentinels for assessing the impact of stressors on coastal ecosystem health

  19. Geographic specificity of Aroclor 1268 in bottlenose dolphins (Tursiops truncatus) frequenting the Turtle/Brunswick River Estuary, Georgia (USA)

    Energy Technology Data Exchange (ETDEWEB)

    Pulster, Erin L. [Marine Sciences Department, Savannah State University, Savannah, Georgia, 31404 (United States); Skidaway Institute of Oceanography, 10 Ocean Science Circle, Savannah, Georgia, 31411 (United States)], E-mail: epulster@mote.org; Maruya, Keith A. [Skidaway Institute of Oceanography, 10 Ocean Science Circle, Savannah, Georgia, 31411 (United States)

    2008-04-15

    Coastal marine resources are at risk from anthropogenic contaminants, including legacy persistent organic pollutants (POPs) with half-lives of decades or more. To determine if polychlorinated biphenyl (PCB) signatures can be used to distinguish among local populations of inshore bottlenose dolphins (Tursiops truncatus) along the southeastern U.S. coast, blubber from free-ranging and stranded animals were collected along the Georgia coast in 2004 and analyzed for PCB congeners using gas chromatography with electron capture and negative chemical ionization mass spectrometric detection (GC-ECD and GC-NCI-MS). Mean total PCB concentrations (77 {+-} 34 {mu}g/g lipid) were more than 10 fold higher and congener distributions were highly enriched in Cl{sub 7}-Cl{sub 10} homologs in free-ranging animals from the Turtle/Brunswick River estuary (TBRE) compared with strandings samples from Savannah area estuaries 90 km to the north. Using principal components analysis (PCA), the Aroclor 1268 signature associated with TBRE animals was distinct from that observed in Savannah area animals, and also from those in animals biopsied in other southeastern U.S estuaries. Moreover, PCB signatures in dolphin blubber closely resembled those in local preferred prey fish species, strengthening the hypothesis that inshore T. truncatus populations exhibit long-term fidelity to specific estuaries and making them excellent sentinels for assessing the impact of stressors on coastal ecosystem health.

  20. Use of mock-up training to reduce personnel exposure at the North Anna Unit 1 Steam Generator Replacement Project

    International Nuclear Information System (INIS)

    The North Anna Power Station is located on the southern shore of Lake Anna in Louisa County, approximately forty miles northwest of Richmond, Virginia. The two 910 Mw nuclear units located on this site are owned by Virginia Electric and Power Company (Virginia Power) and Old Dominion Electric Cooperative and operated by Virginia Power. Fuel was loaded into Unit 1 in December 1977, and it began commercial operation in June 1978. Fuel was loaded into Unit 2 in April 1980 and began commercial operation in December 1980. Each nuclear unit includes a three-coolant-loop pressurized light water reactor nuclear steam supply system that was furnished by Westinghouse Electric Corporation. Included within each system were three Westinghouse Model 51 steam generators with alloy 600, mill-annealed tubing material. Over the years of operation of Unit 1, various corrosion-related phenomena had occurred that affected the steam generators tubing and degraded their ability to fulfill their heat transfer function. Advanced inspection and repair techniques helped extend the useful life of the steam generators, but projections based on the results of the inspections indicated that the existing steam generators tubing and degraded their ability to fullfill their heat transfer function. Advanced inspection and repair techniques helped extend the useful life of the steam generators, but projections based on the results of the inspections indicated that the existing steam generators would not last their design life and must be repaired. To this end Virginia Power determined that a steam generator replacement (SGR) program was necessary to remove the old steam generator tube bundles and lower shell sections, including the channel heads (collectively called the lower assemblies), and replace them with new lower assemblies incorporating design features that will prevent the degradation problems that the old steam generators had experienced

  1. Use of borehole radar tomography to monitor steam injection in fractured limestone

    Science.gov (United States)

    Gregoire, C.; Joesten, P.K.

    2006-01-01

    Borehole radar tomography was used as part of a pilot study to monitor steam-enhanced remediation of a fractured limestone contaminated with volatile organic compounds at the former Loring Air Force Base, Maine, USA. Radar tomography data were collected using 100-MHz electric-dipole antennae before and during steam injection to evaluate whether cross-hole radar methods could detect changes in medium properties resulting from the steam injection. Cross-hole levelrun profiles, in which transmitting and receiving antennae are positioned at a common depth, were made before and after the collection of each full tomography data set to check the stability of the radar instruments. Before tomographic inversion, the levelrun profiles were used to calibrate the radar tomography data to compensate for changes in traveltime and antenna power caused by instrument drift. Observed changes in cross-hole radar traveltime and attenuation before and during steam injection were small. Slowness- and attenuation-difference tomograms indicate small increases in radar slowness and attenuation at depths greater than about 22 m below the surface, consistent with increases in water temperature observed in the boreholes used for the tomography. Based on theoretical modelling results, increases in slowness and attenuation are interpreted as delineating zones where steam injection heating increased the electrical conductivity of the limestone matrix and fluid. The results of this study show the potential of cross-hole radar tomography methods to monitor the effects of steam-induced heating in fractured rock environments. ?? 2006 European Association of Geoscientists & Engineers.

  2. SO2 pollution of heavy oil-fired steam power plants in Iran

    International Nuclear Information System (INIS)

    Steam power plants using heavy oil provided about 17.4%, equivalent to 35.49 TWh, of electricity in Iran in 2007. However, having 1.55–3.5 weight percentage of sulfur, heavy oil produces SO2 pollutant. Utilization of Flue Gas Desulfurization systems (FGD) in Iran's steam power plants is not common and thereby, this pollutant is dispersed in the atmosphere easily. In 2007, the average emission factor of SO2 pollutant for steam power plants was 15.27 g/kWh, which means regarding the amount of electricity generated by steam power plants using heavy oil, 541,000 Mg of this pollutant was produced. In this study, mass distribution of SO2 in terms of Mg/yr is considered and dispersion of this pollutant in each of the 16 steam power plants under study is modeled using Atmospheric Dispersion Modeling System (ADMS). Details of this study are demonstrated using Geographical Information System (GIS) software, ArcGIS. Finally, the average emission factor of SO2 and the emission of it in Iran's steam power plants as well as SO2 emission reduction programs of this country are compared with their alternatives in Turkey and China.

  3. Steam release into buildings: the modelling of steam condensation

    International Nuclear Information System (INIS)

    A lumped-parameter code, HOTSTM, has been developed to model the thermal transient resulting from a steam jet discharging into a large ventilated building, typical of CEGB power plant installations. The code is designed to deal with high pressure steam jets whose typical dimension is small compared with that of the building, so that there is good good mixing within the building. An important factor in limiting the temperature rise of the air/steam mixture is heat transfer to the internal surfaces of the building, the temperatures of which are significantly affected by condensation. A detailed description is given of the method used in HOTSTM to calculate condensation and evaporation on internal building surfaces. The method exploits the well-known analogy between heat and mass transfer, together with correction factors derived from a simplified analytical solution. The validity of the approximations inherent in the method is estimated to affect predictions of bulk gas temperature by only a few degrees. A complete listing of the code, as used for calculating thermal transients in Bradwell Turbine House, is appended to the Report. This is intended as a record of the calculational route used in that work, not as a user's guide to the program. (author)

  4. Repair welding of cracked steam turbine blades

    International Nuclear Information System (INIS)

    The procedure for repair welding of cracked steam turbine blades made of martensitic stainless steels has been developed using the gas tungsten arc welding process. Weld repair procedures were developed using both ER316L austenitic stainless steel filler wire and ER410 martensitic stainless steel filler wire. The repair welding procedure with austenitic filler wire was developed to avoid preheating of the blade as also hydrogen induced cold cracking, and involved evaluation of three different austenitic filler wires, viz. ER309L, ER316L and ERNiCr-3. The overall development of the repair welding procedure included selection of welding consumables (for austenitic filler metal), optimisation of post weld heat treatment parameters, selection of suitable method for local pre-heating and post-weld heat treatment (PWHT) of the blades, determination of mechanical properties of weldments in as-welded and PWHT conditions, and microstructural examination. After various trials using different procedures, the procedure of local PWHT using electrical resistance heating on the top surface of the weldment and monitoring the temperature by placing a thermocouple at the bottom of the weld, was found to give the most satisfactory results. A similar procedure was used for preheating while using ER410 filler metal. Mechanical testing of weldments before and after PWHT involved tensile tests at room temperature, face and root bend tests, and microhardness measurements across the fusion line and heat affected zone. During procedure qualification, mock-ups and actual repair welding, dye penetrant testing was used at different stages and where ever possible radiography was carried out. These procedures were developed for repair welding of cracked blades in the low-pressure (LP) steam turbines of Indian nuclear power plants. The procedure with ER316 L filler wire has so far been applied for repair welding of 2 cracked blades (made of AISI 410 SS) of LP steam turbines, while the procedure

  5. Repair welding of cracked steam turbine blades

    Energy Technology Data Exchange (ETDEWEB)

    Bhaduri, A.K.; Gill, T.P.S.; Albert, S.K.; Shanmugam, K.; Iyer, D.R. [Indira Gandhi Centre for Atomic Research, Kalpakkam (India)]|[Nuclear Power Corp., Mumbai (India)

    1999-07-01

    The procedure for repair welding of cracked steam turbine blades made of martensitic stainless steels has been developed using the gas tungsten arc welding process. Weld repair procedures were developed using both ER316L austenitic stainless steel filler wire and ER410 martensitic stainless steel filler wire. The repair welding procedure with austenitic filler wire was developed to avoid preheating of the blade as also hydrogen induced cold cracking, and involved evaluation of three different austenitic filler wires, viz. ER309L, ER316L and ERNiCr-3. The overall development of the repair welding procedure included selection of welding consumables (for austenitic filler metal), optimisation of post weld heat treatment parameters, selection of suitable method for local pre-heating and post-weld heat treatment (PWHT) of the blades, determination of mechanical properties of weldments in as-welded and PWHT conditions, and microstructural examination. After various trials using different procedures, the procedure of local PWHT using electrical resistance heating on the top surface of the weldment and monitoring the temperature by placing a thermocouple at the bottom of the weld, was found to give the most satisfactory results. A similar procedure was used for preheating while using ER410 filler metal. Mechanical testing of weldments before and after PWHT involved tensile tests at room temperature, face and root bend tests, and microhardness measurements across the fusion line and heat affected zone. During procedure qualification, mock-ups and actual repair welding, dye penetrant testing was used at different stages and where ever possible radiography was carried out. These procedures were developed for repair welding of cracked blades in the low-pressure (LP) steam turbines of Indian nuclear power plants. The procedure with ER316 L filler wire has so far been applied for repair welding of 2 cracked blades (made of AISI 410 SS) of LP steam turbines, while the procedure

  6. Numerical discretization analysis of a HTR steam generator model for the thermal-hydraulics code trace

    Directory of Open Access Journals (Sweden)

    Esch Markus

    2014-01-01

    Full Text Available For future high temperature reactor projects, e. g., for electricity production or nuclear process heat applications, the steam generator is a crucial component. A typical design is a helical coil steam generator consisting of several tubes connected in parallel forming cylinders of different diameters. This type of steam generator was a significant component used at the thorium high temperature reactor. In the work presented the temperature profile is being analyzed by the nodal thermal hydraulics code TRACE for the thorium high temperature reactor steam generator. The influence of the nodalization is being investigated within the scope of this study and compared to experimental results from the past. The results of the standard TRACE code are compared to results using a modified Nusselt number for the primary side. The implemented heat transfer correlation was developed within the past German HTR program. This study shows that both TRACE versions are stable and provides a discussion of the nodalization requirements.

  7. French Regulatory practice and experience feedback on steam generator tube integrity

    Energy Technology Data Exchange (ETDEWEB)

    Sandon, G.

    1997-02-01

    This paper summarizes the way the French Safety Authority applies regulatory rules and practices to the problem of steam generator tube cracking in French PWR reactors. There are 54 reactors providing 80% of French electrical consumption. The Safety Authority closely monitors the performance of tubes in steam generators, and requires application of a program which deals with problems prior to the actual development of leakage. The actual rules regarding such performance are flexible, responding to the overall performance of operating steam generators. In addition there is an inservice inspection service to examine tubes during shutdown, and to monitor steam generators for leakage during operation, with guidelines for when generators must be pulled off line.

  8. Steam producing plant concept of 4S for oil sand extraction

    International Nuclear Information System (INIS)

    Plant concept of small fast reactor '4S' applying to continuous steam production for recovery of crude oil from oil sands was investigated. Assuming typical steam assisted gravity drainage (SAGD) plant whose production scale is 120,000 barrels per day of a crude oil, concept of nuclear steam supply system consisting of eight reactor modules for steam production and three reactor modules for electric generation of the 4S with a thermal rating of 135 MWt was established without any essential or significant design change from the preceding 4S with a thermal rating of 30 MWt. The 4S, provided for an oil sand extraction, will reduce greenhouse gas emission significantly, and has not much burden for development and licensing and has economic competitiveness. (author)

  9. Study on the PWR Steam Generator Behavior with improved steam-driven aux feedwater system under prolonged SBO Accident

    International Nuclear Information System (INIS)

    The only available passive decay heat removal system of current PWRs is a turbine-driven auxiliary steam generator (SG) feedwater (TD-AFW) system. If a SG water level becomes too high, however, turbine blades could be damaged due to a large amount of becomes too high, however, turbine blades could be damaged due to a large amount of moisture in steam and the SG cooling capability would not be maintained any longer. Therefore, the SG water level should be controlled to prevent the turbine from being damaged during a Station Black-Out (SBO) accident. In this paper, an improved design feature is proposed to provide electric power for controlling SG water level when both off-site power and the emergency diesel generators are not available. There are additional SG level gauges and valve controllers to control the steam flow into the auxiliary turbine in an improved TD-AFW system. Electric power for this control system is provided by a small additional generator which is connected to the existing auxiliary turbine shaft. Using this new feature, decay heat cooling is available for 29 hours with only 1 condensate storage tank which is the water source of the AFW. Eventually, it is concluded that the improved TD-AFW system with an additional SG level controller and generator can avoid an early SG full level and continue long term cooling during a prolonged SBO accident

  10. The market for steam turbine generators around the world

    International Nuclear Information System (INIS)

    As a discrete market (in the mathematical meaning of the word) with irregular sales from one year to the next, the market for steam turbine generators in nuclear plants requires working out a strategy adapted to each project. The diversity of the reactors proposed (technology, thermal power, the thermodynamic characteristics of the steam supplied), the variety of the cold sources to be used (ranging from the Baltic Sea to the Indian Ocean) and the different frequencies of electricity grids (50 or 60 Hz) necessitate developing platforms of solutions. Furthermore, the requirement that local businesses have a share in contracts often entails partnerships. After pointing out the diversity of this market, the effort is made to point out its principal characteristics. (authors)

  11. Modeling of eddy current probe response for steam generator tubes

    International Nuclear Information System (INIS)

    Sample calculations were performed with a three-dimensional (3-D) finite-element model analysis that describe the response of an eddy current (EC) probe to steam generator (SG) tubing artifacts. Such calculations could be very helpful in understanding and interpreting of EC probe response to complex tube/defect geometries associated with the inservice inspection (ISI) of steam generator (SG) tubing. The governing field equations are in terms of coupled magnetic vector and electric scalar potentials in conducting media and of total or reduced scalar potentials in nonconducting regions. To establish the validity of the model, comparisons of the theoretical and experimental responses of an absolute bobbin probe are given for two types of calibration standard defects. Preliminary results are also presented from a recent theoretical study of the effect of ligament size in axial cracks on EC indications with conventional ISI bobbin probes

  12. Radiation exposure management for the Point Beach steam generator replacement

    International Nuclear Information System (INIS)

    Replacement of the steam generators at the Point Beach Unit 1 Nuclear Plant was a turnkey project undertaken for Wisconsin Electric Power Company (WEPCO) by Westinghouse. Westinghouse had full responsibility for the program from project management and all steam generator removal/installation activities to health physics implementation. The replacement method associated with the replacement was a pipe cut approach as opposed to the channel head cut method. The replacement work began in early October 1983 and was completed on January 25, 1984 - 31 days ahead of schedule and with a record-low collective radiation exposure of 590 man-rem. The success of the operation, from a radiation exposure management point of view, is attributed primarily to extensive planning and implementation of innovative replacement techniques

  13. Closed loop steam cooled airfoil

    Science.gov (United States)

    Widrig, Scott M.; Rudolph, Ronald J.; Wagner, Gregg P.

    2006-04-18

    An airfoil, a method of manufacturing an airfoil, and a system for cooling an airfoil is provided. The cooling system can be used with an airfoil located in the first stages of a combustion turbine within a combined cycle power generation plant and involves flowing closed loop steam through a pin array set within an airfoil. The airfoil can comprise a cavity having a cooling chamber bounded by an interior wall and an exterior wall so that steam can enter the cavity, pass through the pin array, and then return to the cavity to thereby cool the airfoil. The method of manufacturing an airfoil can include a type of lost wax investment casting process in which a pin array is cast into an airfoil to form a cooling chamber.

  14. Steam generator waterlancing at DNGS

    International Nuclear Information System (INIS)

    Darlington Nuclear Generating Station (DNGS) is a four 900 MW Unit nuclear station forming part of the Ontario Hydro East System. There are four identical steam generators(SGs) per reactor unit. The Darlington SGs are vertical heat exchangers with an inverted U-tube bundle in a cylindrical shell. The DNGS Nuclear Plant Life Assurance Group , a department of DNGS Engineering Services have taken a Proactive Approach to ensure long term SG integrity. Instead of waiting until the tubesheets are covered by a substantial and established hard deposit; DNGS plan to clean each steam generator's tubesheet, first half lattice tube support assembly and bottom of the thermal plate every four years. The ten year business plan provides for cleaning and inspection to be conducted on all four SGs in each unit during maintenance outages (currently scheduled for every four years)

  15. Duplex steam reformer: alternate catalyst

    International Nuclear Information System (INIS)

    The manufacturing feasibility of a duplex steam reformer tube for potential use in a high temperature gas cooled reactor has been successfully demonstrated. This technique consists of explosively expanding the inner tube into the outer tube. To successfully achieve the desired 0 to 3 mil radial gap between the tubes it is necessary to perform the expansion in two steps with an intermediate anneal. A catalyst design that would have replaced the conventional Raschig rings with a metal supported catalyst has been evaluated and it has been concluded that further development and testing are needed before fabrication of a full scale prototype is warranted. Consequently, the immediate efforts are directed towards reevaluating the incentives for developing a catalyst and the probability of successfully developing a catalyst that could be used for steam reforming

  16. Recent operating experiences with steam generators in Japanese NPPs

    Energy Technology Data Exchange (ETDEWEB)

    Yashima, Seiji [Japan Power Engineering and Inspection Corp., Tokyo (Japan)

    1997-02-01

    In 1994, the Genkai-3 of Kyushu Electric Power Co., Inc. and the Ikata-3 of Shikoku Electric Power Co., Inc. started commercial operation, and now 22 PWR plants are being operated in Japan. Since the first PWR plant now 22 PWR plants are being operated in was started to operate, Japanese PWR plants have had an operating experience of approx. 280 reactor-years. During that period, many tube degradations have been experienced in steam generators (SGs). And, in 1991, the steam generator tube rupture (SGTR) occurred in the Mihama-2 of Kansai Electric Power Co., Inc. However, the occurrence of tube degradation of SGs has been decreased by the instructions of the MITI as regulatory authorities, efforts of Electric Utilities, and technical support from the SG manufacturers. Here the author describes the recent SGs in Japan about the following points. (1) Recent Operating Experiences (2) Lessons learned from Mihama-2 SGTR (3) SG replacement (4) Safety Regulations on SG (5) Research and development on SG.

  17. COMPUTATIONAL FLUID DYNAMIC ANALYSIS OF INTERMEDIATE PRESSURE STEAM TURBINE

    OpenAIRE

    C RAJESH BABU

    2013-01-01

    a steam prime mover with rotary motion of the driving element, or rotor, and continuous operation. It converts the thermal energy of steam into mechanical work. The steam flow proceeds through directing devices and impinges on curved blades mounted along the periphery of the rotor. By exerting a force on the blades, the steam flow causes the rotor to rotate. Unlike the reciprocating steam engine, the steam turbine makes use of the kinetic rather than the potential energy of steam. The perform...

  18. Advanced steam cycles for light water reactors. Final report

    International Nuclear Information System (INIS)

    An appraisal of the potential of adding superheat to improve the overall LWR plant cycle performance is presented. The study assesses the economic and technical problems associated with the addition of approximately 5000F of superheat to raise the steam temperature to 10000F. The practicality of adding either nuclear or fossil superheat to LWR's is reviewed. The General Electric Company Boiling Water Reactor (BWR) model 238-732 (BWR/6) is chosen as the LWR starting point for this evaluation. The steam conditions of BWR/6 are representative of LWR's. The results of the fossil superheat portion of the evaluation are considered directly applicable to all LWR's. In spite of the potential of a nuclear superheater to provide a substantial boost to the LWR cycle efficiency, nuclear superheat offers little promise of development at this time. There are difficult technical problems to resolve in the areas of superheat fuel design and emergency core cooling. The absence of a developed high integrity, high temperature fuel for operation in the steam/water environment is fundamental to this conclusion. Fossil superheat offers the potential opportunity to utilize fossil fuel supplies more efficiently than in any other mode of central station power generation presently available. Fossil superheat topping cycles evaluated included atmospheric fluidized beds (AFB), pressurized fluidized beds, pressurized furnaces, conventional furnaces, and combined gas/steam turbine cycles. The use of an AFB is proposed as the preferred superheat furnace. Fossil superheat provides a cycle efficiency improvement for the LWR of two percentage points, reduces heat rejection by 15 percent per kWe generated, increases plant electrical output by 54 percent, and burns coal with an incremental net efficiency of approximately 40 percent. This compares with a net efficiency of 36--37 percent which might be achieved with an all-fluidized bed fossil superheat plant design

  19. Significant Silica Solubility in Geothermal Steam

    Energy Technology Data Exchange (ETDEWEB)

    James, Russell

    1986-01-21

    Although it is widely believed that silica solubility in low pressure (5 to 10 bar) geothermal steam is negligible, when one takes into account steam flows exceeding 10 million tonnes a year--at Wairakei, for instance--it is found that the amount transmitted in the vapor has the potential to give significant deposits on turbine nozzles and blades. A 150 MWe power station, when based on flows from a hot water reservoir at (a) 250 C or (b) 315 C, and with separator pressures of 6 bar, is found to carry about 100 and 200 kg/year respectively in the steam phase. In the case of a similar sized station exploiting a dry steam reservoir such as The Geysers, equivalent silica flows are obtained, dissolved in steam and carried as dust--the latter as solid particles precipitating from the vapor en route from source to turbine, and not preexisting in the formations as is commonly considered. Choking or coating of subterranean rock near such dry steam wells due to exsolving silica, may be the principal cause of declining steam discharge under production. Silica from completely dry or superheated steam can also seal the cap and sides of steam reservoirs when expanding below the criticus temperature (236 C) in a way previously thought possible only by hot water or wet steam.

  20. Solubility of sodium chloride in superheated steam

    International Nuclear Information System (INIS)

    The solubility of sodium chloride in superheated steam was investigated in laboratory-scale experiments up to 20 MPa and 475 C. These experiments were carried out using a dynamic method where deionized steam was passed through a packed bed of salt crystals in a 500 mL Hastelloy autoclave. The residence time of the steam in the salt bed was sufficient to saturate the steam with the salt. The steam samples were cooled and analyzed by ion chromatography. Correlations based on temperature and density were selected to describe the solubility of sodium chloride in superheated steam. The density dependence is much stronger than the temperature dependence. By using these correlations, it is possible to estimate the solubility of salt in steam at lower densities than those used in the experiments. Enthalpy-entropy diagrams are given that show the steam expansion line in turbines, including curves for constant concentration of sodium chloride solubility in steam. These can be used to analyze where in the steam cycle this salt may deposit. (orig.)

  1. Effect of steam-exhaust operation of secondary coolant circuit on ship reactor blackout accident

    International Nuclear Information System (INIS)

    Highlights: • The ship reactor blackout accident (SRBA) is simulated by the RELAP5/MOD3.2 code. • The mitigation effect of steam-exhaust-operation (SEO) on the SRBA is analyzed. • Reasonable SEO scheme can obviously mitigate the accident for several hours. • The SEO scheme without feed water device can hardly mitigate the SRBA. • The failure of intercurrent steam flux control valve will result in the decrease of mitigation time. - Abstract: The ship reactor blackout accident can potentially lead to the severe accident and the radioactive fission product release. In the absence of auxiliary electrical source, the effective mitigation of the accident aftereffect is very important. As the exclusive heat trap in the reactor coolant system, the steam-exhaust operation (SEO) in the secondary coolant circuit (SCC) plays an important role in the accident mitigation. In view of the character of ship nuclear power plant (NPP), the ship reactor blackout accident (SRBA) under the typical operating conditions is simulated by the RELAP5/MOD3.2 code, and the mitigation of SEO on the accident is analyzed. It is found that (1) reasonable SEO can obviously mitigate the accident for several hours, the SEO with 1% rated steam flux of secondary coolant circuit provides about 7 h for the mitigation of accident, (2) a less steam flux of SCC during the SEO means a slower pressure drop of steam generation (SG) and a more time we can mitigate the accident, there are 1.5 h between the SEO with 1% rated steam flux and that with 3% rated steam flux, (3) the SEO without the feed water device can hardly mitigate the accident, and (4) during the blackout accident, the SEO with intercurrent steam flux control valve failure will result in the decrease of mitigation time because of the quick decrease of SG pressure, but the mitigation effect is also obvious

  2. Steam electrolysis cell system and electrolyzing method

    International Nuclear Information System (INIS)

    The present invention concerns a method effective to the electrolysis of tritium water in a tritium recovering system of a thermonuclear fuel system. Namely, in a steam electrolysis cell system including integrally constituted multistage type cells and independently disposed single stage type cell, steams are supplied from upstream to the multistage type cell. A voltage is applied at such a level that the concentration of the steams in the vicinity of the single stage type cell situated at the downmost stream among the cells is not decreased to 0 to electrolyze steams. Then, not yet decomposed steams are introduced to the single stage cell to complete the electrolysis. The device can be simplified and steams can be electrolyzed efficiently. (N.H.)

  3. Biomass-gasifier steam-injected gas turbine cogeneration for the cane sugar industry

    International Nuclear Information System (INIS)

    Steam injection for power and efficiency augmentation in aeroderivative gas turbines has been commercially established for natural gas-fired cogeneration since 1980. Steam-injected gas turbines fired with coal and biomass are being developed. A performance and economic assessment of biomass integrated-gasifier steam-injected gas turbine (BIG/STIG) cogeneration systems is carried out here. A detailed economic case study is presented for the second largest sugar factory in Jamaica, with cane residues as the fuel. BIG/STIG cogeneration units would be attractive investments for sugar producers, who could sell large quantities of excess electricity to the utility, or for the utility, as a low-cost generating option. Worldwide, the cane sugar industry could support some 50,000 MW of BIG/STIG electric generation capacity. The relatively modest development effort required to commercialize the BIG/STIG technology is discussed in a companion paper prepared for this conference

  4. Thermal-hydraulics in recirculating steam generators

    International Nuclear Information System (INIS)

    This manual describes the THIRST code and its use in computing three-dimensional two-phase flow and heat transfer in a steam generator under steady state operation. The manual is intended primarily to facilitate the application of the code to the analysis of steam generators typical of CANDU nuclear stations. Application to other steam generator designs is also discussed. Details of the assumptions used to formulate the model and to implement the numerical solution are also included

  5. Analysis of TROI-13 Steam Explosion Experiment

    OpenAIRE

    Mitja Uršič; Matjaž Leskovar

    2008-01-01

    The prediction of steam explosion inducing loads in nuclear power plants must be based on results of experimental research programmes and on simulations using validated fuel-coolant interaction codes. In this work, the TROI-13 steam explosion experiment was analysed with the fuel-coolant interaction MC3D computer code. The TROI-13 experiment is one of several experiments performed in the TROI research program and resulted in a spontaneous steam explosion using corium melt. First, the TROI-13 ...

  6. Pilot Plant for Solar Process Steam Supply

    OpenAIRE

    Hennecke, Klaus; Hirsch, Tobias; Krüger, Dirk; Lokurlu, Ahmet; Walder, Markus

    2008-01-01

    An aluminium upgrading process will be supplied by steam directly generated in parabolic trough collectors. In this first of it’s kind installation in an industrial environment, steam at 4 bar will be fed into the existing distribution lines of the production to heat anodizing baths and storage tanks. The integration of the solar steam through separate heat exchangers in parallel to the existing system was also considered. In principle, due to the low temperatures of the baths, solar hot wate...

  7. Petrogenetic evolution of Late Paleozoic rhyolites of the Harvey Group, southwestern New Brunswick (Canada) hosting uranium mineralization

    Science.gov (United States)

    Dostal, J.; van Hengstum, T. R.; Shellnutt, J. G.; Hanley, J. J.

    2016-06-01

    The 360 Ma subaerial felsic volcanic and volcaniclastic rocks of the Harvey Group form a belt about 15 km long and 3 km wide in southwestern New Brunswick (Canada) that has been correlated with parts of the Mount Pleasant caldera complex, the site of a significant polymetallic (tin, tungsten, molybdenum, indium and bismuth) deposit. The Harvey volcanic rocks are highly fractionated peraluminous within-plate F-rich rhyolites, which host uranium mineralization. The rocks were modified by late-magmatic and post-magmatic processes. A comparison of the composition of whole rocks and melt inclusions in the quartz phenocrysts shows that some trace elements, including U, were affected by the post-magmatic processes. Their flat REE patterns accompanied by distinct negative Eu anomalies are typical of highly evolved F-rich leucogranites and rhyolites. Nd isotopic ratios (ɛNd(360) = +0.6 to -1.0) are similar to those of the felsic rocks of the Mount Pleasant complex. The Harvey rhyolites were generated by extensive fractional crystallization of andesites of the Mount Pleasant caldera. The melt evolved at the apex of the magma chamber where volatile elements become concentrated. The Harvey rhyolite (with melt inclusions containing ~20 ppm U) had the potential to develop a significant U mineralization. The erupted glassy rhyolite is a favorable U source rock amendable to leaching by post-magmatic hydrothermal and meteoric water. The high Th/U ratios in the Harvey volcanic rocks compared to the low ratios in the U-rich melt inclusions is indicative of such a process.

  8. Public forest policy development in New Brunswick, Canada: multiple streams approach, advocacy coalition framework, and the role of science

    Directory of Open Access Journals (Sweden)

    William F. A. Anderson

    2015-12-01

    Full Text Available In a 15-year case study, we used the multiple streams approach (MSA and the advocacy coalition framework (ACF to examine a controversial industry-led proposal for increased harvest of Crown forests in New Brunswick, Canada, in an adversarial policy subsystem. Study participants were queried on their perceptions of policy problems and reasons for community attention, the relationship between science and policy, and whether policy decisions were consistent with scientific understanding. Thematic analysis was used to examine interview data for evidence of Kingdon's MSA and Sabatier's ACF. During public hearings of a Legislative Select Committee on Wood Supply, two competing policy alternatives emerged. The first, put forward by the forest industry coalition, advocated an intensive forest management approach in support of a competitive industry. The second, supported by the conservation coalition, largely made up of scientists and environmental groups, focused on adaptive management, an ecosystem approach, and greater public input. This counterproposal forestalled the industry from placing its proposal on the government 2005 decision agenda. However, in 2014, the government unexpectedly adopted essentially the same industry proposal. Although the MSA provided a better explanation of the factors critical to the 2014 policy change, i.e., a declining provincial economy and a change of key government personnel, the ACF offered a nuanced perspective on the need for a professional forum to facilitate policy-oriented learning across competing coalitions. In 2014, the lack of such a forum and a closed process limited policy alternatives considered by elected officials. Results also emphasize the importance of how legislators choose to interact with experts and scientists, particularly within an adversarial subsystem, especially when a powerful coalition develops ways to limit the access to decision makers by competing coalitions.

  9. Effects of forest harvesting on summer stream temperatures in New Brunswick, Canada: an inter-catchment, multiple-year comparison

    Directory of Open Access Journals (Sweden)

    C. P.-A. Bourque

    2001-01-01

    Full Text Available This paper presents a pre- and post-harvest comparison of stream temperatures collected in five neighbouring streams (sub-catchments over a period of five years (1994-1998. The aim of the study was to determine whether land cover changes from clear cutting in areas outside forest buffer zones (applied to streams >0.5 m wide might contribute to an increase in summer mean stream temperatures in buffered streams downslope by infusion of warmed surface and sub-surface water into the streams. Specific relationships were observed in all five forest streams investigated. To assist in the analysis, several spatially-relevant variables, such as land cover change, mid-summer potential solar radiation, flow accumulation, stream location and slope of the land were determined, in part, from existing aerial photographs, GIS-archived forest inventory data and a digital terrain model of the study area. Spatial calculations of insolation levels for July 15th were used as an index of mid-summer solar heating across sub-catchments. Analysis indicated that prior to the 1995 harvest, differences in stream temperature could be attributed to (i topographic position and catchment-to-sun orientation, (ii the level of cutting that occurred in the upper catchment prior to the start of the study, and (iii the average slope within harvested areas. Compared to the pre-harvest mean stream temperatures in 1994, mean temperatures in the three streams downslope from the 1995 harvest areas increased by 0.3 to 0.7°C (representing a 4-8% increase; p-value of normalised temperatures Keywords: terrain attributes, solar radiation, land cover, forest buffers, New Brunswick regulations, spatial modelling, DEM, forest covertypes

  10. Steam injection experiments in a microturbine – A thermodynamic performance analysis

    International Nuclear Information System (INIS)

    Highlights: ► Externally produced steam was injected in a T100 microgasturbine. ► Perturbation analysis model was made for accurate determination of efficiency rise. ► What-if analysis was performed for error determination. ► Decreasing rotation speed and increasing efficiency were noticed during steam injection. ► Increasing efficiency was however lower than expected. -- Abstract: This paper reports on a series of steam injection experiments on a Turbec T100 microturbine. Combined Heat and Power (CHP) systems, such as the considered T100 microturbine, use one single primary fuel to simultaneously produce electric and thermal power. In doing so, they realize significant energy savings compared to conventional schemes of separated production. However, a reduction in the demand for heat (e.g. in summertime) will force this type of units to shutdown. This significantly reduces the amount of operating hours and has a severe negative impact on the net present value of such CHP investment projects. The aim of this paper is to investigate and demonstrate the effects of steam injection in the compressor outlet of a microturbine operating under reduced heat demand conditions, in order to keep the unit running. The necessary steam can be auto-raised with heat available in the turbine exhaust downstream of the recuperator. Such an injection will keep the unit running and thus avoid a forced shutdown. Furthermore, it is expected that the electric efficiency will rise and that the power production will become more economically viable as a result of the increasing operating hours. This paper reports on the influence of steam injection on the electrical efficiency and shaft speed of a T100 unit. ASPEN® simulations of the behavior of the CHP unit are also presented. These simulations predicted a 2.2% rise in electric efficiency at nominal electrical output when 5% of the mass flow rate of air is replaced by steam. The steam injection experiments resulted in stable runs

  11. Loss of feed flow, steam generator tube rupture and steam line break thermohydraulic experiments

    International Nuclear Information System (INIS)

    The Westinghouse Model Boiler No. 2 (MB-2) steam generator test model at the Engineering Test Facility in Tampa, Florida, was reinstrumented and modified for performing a series of tests simulating steam generator accident transients. The transients simulated were: loss of feed flow, steam generator tube rupture, and steam line break events. This document presents a description of (1) the model boiler and the associated test facility, (2) the tests performed, and (3) the analyses of the test results

  12. Loss of feed flow, steam generator tube rupture and steam line break thermohydraulic experiments

    Energy Technology Data Exchange (ETDEWEB)

    Mendler, O J; Takeuchi, K; Young, M Y

    1986-10-01

    The Westinghouse Model Boiler No. 2 (MB-2) steam generator test model at the Engineering Test Facility in Tampa, Florida, was reinstrumented and modified for performing a series of tests simulating steam generator accident transients. The transients simulated were: loss of feed flow, steam generator tube rupture, and steam line break events. This document presents a description of (1) the model boiler and the associated test facility, (2) the tests performed, and (3) the analyses of the test results.

  13. Analysis of TROI-13 Steam Explosion Experiment

    Directory of Open Access Journals (Sweden)

    Mitja Uršič

    2008-01-01

    Full Text Available The prediction of steam explosion inducing loads in nuclear power plants must be based on results of experimental research programmes and on simulations using validated fuel-coolant interaction codes. In this work, the TROI-13 steam explosion experiment was analysed with the fuel-coolant interaction MC3D computer code. The TROI-13 experiment is one of several experiments performed in the TROI research program and resulted in a spontaneous steam explosion using corium melt. First, the TROI-13 premixing simulations were performed to determine the initial conditions for the steam explosion simulations and to evaluate the melt droplets hydrodynamic fragmentation model. Next, a number of steam explosion simulations were performed, varying the steam explosion triggering position and the melt droplets mass participating in the steam explosion. The simulation results revealed that there is an important influence of the participating melt droplets mass on the calculated pressure loads, whereas the influence of the steam explosion triggering position on the steam explosion development was less expressive.

  14. CAREM-25 Steam Generator Stability Analysis

    International Nuclear Information System (INIS)

    In this work the stability of a once-through CAREM-25 steam generator is analyzed.A fix nodes numerical model, that allows the modelling of the liquid, two-phase and superheated steam zones, is implemented.This model was checked against a mobile finite elements model under saturated steam conditions at the channel exit and a good agreement was obtained.Finally the stability of a CAREM steam generator is studied and the range of in let restrictions that a assure the system stability is analyzed

  15. Gas-steam turbine plant for cogenerative process at 'Toplifikacija' - Skopje (Joint-Stock Co. for district heating - Macedonia)

    International Nuclear Information System (INIS)

    The gas-steam power plant for combined heat and electric power production at A.D. 'Toplifikacija' Skopje - TO 'Zapad' is analyzed and determined. The analyzed plant is consisted of gas turbine, heat recovery steam generator (HRSG) and condensate steam turbine with controlled steam extraction. It operates on natural gas as a main fuel source. The heating of the water for the district heating is dine in the heat exchanger, with // heat of controlled extraction from condensate turbine. The advantages of the both binary plant and centralized co generative production compared with the individual are analyzed. The natural gas consumption of for both specific heating and electrical capacity in join production as well as fuel savings compared to the separate production of the same quantity of energy is also analyzed. (Original)

  16. Exergy and exergoeconomic analysis of sustainable direct steam generation solar power plants

    International Nuclear Information System (INIS)

    Highlights: • Exergy and exergoeconomic analyses are presented for direct steam generation plant. • Both non-reheating and reheating by steam–steam heat exchanger are considered. • The contribution of each component to the total exergy destruction is determined. • The cost associated with exergy destruction and production cost are evaluated. • The effect of degree of reheating on the performance is presented. - Abstract: Solar direct steam generation is considered as a promising technology for steam production in thermal power generation due to high temperature levels that can be achieved compared to other technologies that use indirect steam generation. This paper demonstrates exergy and exergoeconomic analysis of commercial-size direct steam generation parabolic trough solar thermal power plant. For steam power cycles, reheating might be necessary to avoid great wetness of steam which shortens the lifetime of the turbines. Therefore, two configurations have been considered in this study; the non-reheating configuration as well as reheating by steam–steam heat exchanger. For each component, exergy and exergy-costing balance equations have been formulated based on a proper definition of fuel–product–loss. Exergy results show that particular attention should be paid to solar field, condenser, low pressure turbine and high pressure turbine (in a descendant order) as they constitute the major sources of exergy destruction. Results from exergoeconomic analysis, however, show that the condenser should be the fourth component in the order of importance after the solar field and low/high pressure turbines. Increasing the temperature at the inlet of the low pressure turbine by 100 K using steam–steam reheating is shown to result in 9.1% increase in the vapor fraction at the exit of turbine. This increase in steam quality, however, would be achieved by drop less than 1.5% in thermal and exergetic efficiencies, and about 2% increase in cost of electricity

  17. Experimental research regarding the corrosion of incoloy-800 and SA 508 cl.2 in the CANDU steam generator

    International Nuclear Information System (INIS)

    Steam generators (SGs) are crucial components of pressurized water reactors. The failure of the steam generator as a result of tube degradation by corrosion has been a major cause of Pressurized Water Reactor (PWR) plant unavailability. Steam generator problems have caused major economic losses in terms of lost electricity production through forced unit outages and, in cases of extreme damage, as additional direct cost for large-scale repair or replacement of steam generators. Steam generator tubes are susceptible to failure by a variety of mechanisms, the vast majority of which are related a corrosion. The feedwater that enters into the steam generators under normal operating conditions is extremely pure, but nevertheless contains low levels (generally in the μg/l concentration range) of impurities such as iron, chloride, sulphate, silicate, etc. When water is converted to steam and exits the steam generator, the non-volatile impurities are left behind. As a result, their concentration in the bulk steam generator water is considerably higher than those in the feedwater. Nevertheless, the concentrations of corrosive impurities are still generally sufficiently low that the bulk water is not significantly aggressive towards steam generator materials. The excellent performance to date of CANDU steam generators can be attributed, in part, to their design and performance characteristics, which typically involve higher recirculation ratios and lower heat fluxes and temperatures. The purpose of this paper consists in assessment of generalized corrosion behaviour of the tubes materials (Incoloy-800) and tubesheet material (carbon steel SA 508 cl.2) at the normal secondary circuit parameters (temperature-260 deg C, pressure-5.1MPa). The testing environment was the demineralized water without impurities, at pH=9.5 regulated with morpholine and ciclohexilamine (all volatile treatment - AVT). The results are presented like micrographies and graphics representing loss of metal

  18. To the application of steam-gas circuits for saturated-steam turbine plants

    International Nuclear Information System (INIS)

    Different thermal schemes of duel-circuit NPPs with saturated-steam turbine plants, operating in steam-gas cycle were analyzed. Analytical dependences for evaluating change of NPP efficiency in result of steam-gas circuit introduction were obtained. It was concluded that energy indices of plants grew in result of using circuits with higher initial temperature and decreasing temperature of external air

  19. Linearization of valve flow characteristics for steam turbine control

    International Nuclear Information System (INIS)

    The control valve for a large steam turbine in a power plant has the characteristic of nonlinearity. It is found that the flow increase is much greater for a given valve position change near the closed end of travel than it is near the open end. The steam flow in the system being proportional to the ultimate desired quantity of the turbine, it is preferable to have linear operation. Thus, the automatic control can be applied to this nonlinear system and it is possible to keep the frequency of electricity constant by adjusting the control valve opening to the desired valve position. If the valve is opened less near the closed end of travel and greater near the open end, the desired linearization will be achieved. It is known that one way of linearization is to produce the nonlinear electric compensation to the nonlinear system of control valves, viz. the electro hydraulic control (EHC). There are two transfer functions of the valve-position loop obtained from the different locations to nonlinear signal produced at the valve-position loop input or in the feedback. Based on the linearization principle, the nonlinear electric signal can be generated from an electric circuit which operates as a function generator and consists of resistors and a diode with a high gain operational amplifier (Op Amp). The diode is positioned at the Op Amp input to create the feedback compensation signal, even though it is located in the feedback network of the Op Amp for the feedforward compensation. Methods are presented to create the electric compensation signals for EHC, and are simulated with PSpice, an electric circuit CAD software. (author)

  20. Operating experience with steam generators

    International Nuclear Information System (INIS)

    The Belgian utilities operate 7 PWR units, the steam generators of which suffer from different corrosion attacks. While PWSCC at the roll transition has long been the major difficulty, degradations of the external surface of the tubes were recently observed in different units, at the level of the top of tubesheet, at the tube support plates and in the sludge piles. Many of the observed cracks are through wall but do not reduce excessively the tube strength, what led to the development of specific plugging criteria, thus allowing most of the affected tubes to be kept in service. The Belgian utilities have thus learned to operate imperfectly tight steam generators. They have improved the procedures for in-service leak monitoring and for detection of leaking tubes during outages, as well as the accuracy and efficiency of NDE tools. Many repair interventions were carried out, several of which were tests essentially aimed at assessing new techniques. In spite of the corrosion defects affecting the Belgian steam generators, good operating records in safe conditions have been achieved thanks to extensive R and D in NDE, innovative plugging criteria and large in-situ tests of repair techniques. The major past concern was PWSCC at roll transition. In Doel 3 this has led to a replacement scheduled for 1993 because the expected repair costs, added to the production losses exceed the replacement costs. Recently, OD corrosion appeared to be another major threat. The future of the affected units will depend on the progression rate of these new defects, presently under assessment

  1. RPV steam generator pressure boundary

    Energy Technology Data Exchange (ETDEWEB)

    Strosnider, J.

    1996-03-01

    As the types of SG tube degradation affecting PWR SGs has changed, and improvements in tube inspection and repair technology have occurred, current SG regulatory requirements and guidance have become increasingly out of date. This regulatory situation has been dealt with on a plant-specific basis, however to resolve this problem in the long term, the NRC has begun development of a performance-based rule. As currently structured, the proposed steam generator rule would require licensees to implement SG programs that monitor the condition of the steam generator tubes against accepted performance criteria to provide reasonable assurance that the steam generator tubes remain capable of performing their intended safety functions. Currently the staff is developing three performance criteria that will ensure the tubes can continue to perform their safety function and therefore satisfy the SG rule requirements. The staff, in developing the criteria, is striving to ensure that the performance criteria have the two key attributes of being (1) measurable (enabling the tube condition to be {open_quotes}measured{close_quotes} against the criteria) and (2) tolerable (ensuring that failures to meet the criteria do not result in unacceptable consequences). A general description of the criteria are: (1) Structural integrity criteria: Ensures that the structural integrity of the SG tubes is maintained for the operating cycle consistent with the margins intended by the ASME Code. (2) Leakage integrity criteria: Ensures that postulated accident leakages and the associated dose releases are limited relative to 10 CFR Part 50 guidelines and 10 CFR Part 50 Appendix A GDC 19. (3) Operational leakage criteria: Ensures that the operating unit will be shut down as a defense-in depth measure when operational SG tube leakage exceeds established leakage limits.

  2. Steam Turbine Materials and Corrosion

    Energy Technology Data Exchange (ETDEWEB)

    Holcomb, G.H.; Hsu, D.H.

    2008-07-01

    Ultra-supercritical (USC) power plants offer the promise of higher efficiencies and lower emissions. Current goals of the U.S. Department of Energy’s Advanced Power Systems Initiatives include coal generation at 60% efficiency, which would require steam temperatures of up to 760 °C. In prior years this project examined the steamside oxidation of alloys for use in high- and intermediate-pressure USC turbines. This steamside oxidation research is continuing and progress is presented, with emphasis on chromia evaporation.

  3. Steam microturbines in distributed cogeneration

    CERN Document Server

    Kicinski, Jan

    2014-01-01

    This book presents the most recent trends and concepts in power engineering, especially with regard to prosumer and civic energy generation. In so doing, it draws widely on his experience gained during the development of steam microturbines for use in small combined heat and power stations based on the organic Rankine cycle (CHP-ORC). Major issues concerning the dynamic properties of mechanical systems, in particular rotating systems, are discussed, and the results obtained when using unconventional bearing systems, presented. Modeling and analysis of radial-flow and axial-flow microturbines a

  4. 220Rn in geothermal steam

    International Nuclear Information System (INIS)

    The isotope 220Rn (half-life 56 seconds) occurs in fumaroles in Japan and Taiwan, in amounts as high as 1000 times the 222Rn content. The authors report its presence in geothermal steam at Wairakei, New Zealand, in amounts as high as 130 times those of 222Rn. It is detected by a radiochemical separation of Pb, and gamma spectrometry. Some of the 220Rn/222Rn ratios are higher than theoretically expected, but have frequently been reported from similar locations. Theories of possible origins will be discussed. 22 refs., 1 tab

  5. Steam turbine materials and corrosion

    Energy Technology Data Exchange (ETDEWEB)

    Holcomb, G.R.; Alman, D.E.; Dogan, O.N.; Rawers, J.C.; Schrems, K.K.; Ziomek-Moroz, M.

    2007-12-01

    Ultra-supercritical (USC) power plants offer the promise of higher efficiencies and lower emissions. Current goals of the U.S. Department of Energy’s Advanced Power Systems Initiatives include power generation from coal at 60% efficiency, which would require steam temperatures of up to 760°C. This project examines the steamside oxidation of candidate alloys for use in USC systems, with emphasis placed on applications in high- and intermediate-pressure turbines. As part of this research a concern has arisen about the possibility of high chromia evaporation rates of protective scales in the turbine. A model to calculate chromia evaporation rates is presented.

  6. Strategic management of steam generators

    International Nuclear Information System (INIS)

    This paper addresses the general approach followed in Belgium for managing any kind of generic defect affecting a Steam Generator tubebundle. This involves the successive steps of: problem detection, dedicated sample monitoring, implementation of preventive methods, development of specific plugging criteria, dedicated 100% inspection, implementation of repair methods, adjusted sample monitoring and repair versus replacement strategy. These steps are illustrated by the particular case of Primary Water Stress Corrosion Cracking in tube roll transitions, which is presently the main problem for two Belgian units Doele-3 and Tihange-2. (author)

  7. Steam and Stirling vs. gasoline engine. Wood-fuelled boiler for heat and power generation; Dampf und Stirling kontra Otto. Holzkessel als stromerzeugende Heizung

    Energy Technology Data Exchange (ETDEWEB)

    Genath, B.

    2007-06-15

    The contribution describes new systems presented at the ISH, e.g. compact cogeneration systems with a stirling motor or steam engine for its electric section. An outline is given of what to expect in the future. (orig.)

  8. Development and test evaluation of duplex steam reformer tube

    International Nuclear Information System (INIS)

    For HTR applications involving a steam reformer (SR), it is uncertain whether an intermediate heat exchanger (IHX) is required. There are several system configurations that could be developed for the application of nuclear heat using the steam reformer reaction. The considerations (advantages vs. disadvantages) for each of the system configurations are summarized. The approach that technically and economically appears to be the most attractive, in studies conducted by General Electric, combines the SR process heat exchanger and the IHX in a single component using a duplex tube. A central question concerning the duplex tube concept is whether the design would provide adequate leak monitoring capability and significant reduction in tritium and hydrogen diffusion, while introducing only a small increase in overall temperature difference from the helium to the process gas. A cooperative GE-KFA effort was undertaken to develop, fabricate, test, and evaluate a duplex steam reformer tube. GE was responsible for the development and fabrication of the tube, and KFA was responsible for testing the tube in the EVA I facility at Juelich. Both GE and KFA are evaluating the thermochemical and metallurgical test data. Actual fabrication of the tube was performed by Foster-Wheeler in accordance with the GE design. This paper reviews the highlights of the fabrication development and preliminary evaluation of the test data

  9. Design and construction of a steam generator with feedback; Projeto e construcao de um gerador de vapor com realimentacao

    Energy Technology Data Exchange (ETDEWEB)

    Camargo, Camila C., E-mail: camilacamargo@outlook.com [Universidade Federal de Sao Paulo (UNIFESP), Sao Jose dos Campos, SP (Brazil); Placco, Guilherme M., E-mail: placco@ieav.cta.br [Instituto de Tecnologia Aeronautica (ITA/CTA), Sao Jose dos Campos, SP (Brazil); Guimaraes, Lamartine N.F., E-mail: guimarae@ieav.cta.br [Instituto de Estudos Avancado (IEAv/DCTA), Sao Jose dos Campos, SP (Brazil). Departamento ENU

    2013-07-01

    The EARTH project aims to develop technologies to design and build systems that generate electricity in space, using microreactors. One of the activities within the TERRA project aims to build a closed thermal cycle Rankine type in order to test a Tesla turbine type. The objective of this work is to design and build a steam generator with feedback, which should ensure a satisfactory range of steam supply, security system, feedback system and heating system.

  10. Syngas production by high temperature steam/CO2 coelectrolysis using solid oxide electrolysis cells.

    Science.gov (United States)

    Chen, Xinbing; Guan, Chengzhi; Xiao, Guoping; Du, Xianlong; Wang, Jian-Qiang

    2015-01-01

    High temperature (HT) steam/CO2 coelectrolysis with solid oxide electrolysis cells (SOECs) using the electricity and heat generated from clean energies is an important alternative for syngas production without fossil fuel consumption and greenhouse gas emissions. Herein, reaction characteristics and the outlet syngas composition of HT steam/CO2 coelectrolysis under different operating conditions, including distinct inlet gas compositions and electrolysis current densities, are systematically studied at 800 °C using commercially available SOECs. The HT coelectrolysis process, which has comparable performance to HT steam electrolysis, is more active than the HT CO2 electrolysis process, indicating the important contribution of the reverse water-gas shift reaction in the formation of CO. The outlet syngas composition from HT steam/CO2 coelectrolysis is very sensitive to the operating conditions, indicating the feasibility of controlling the syngas composition by varying these conditions. Maximum steam and CO2 utilizations of 77% and 76% are achieved at 1.0 A cm(-2) with an inlet gas composition of 20% H2/40% steam/40% CO2. PMID:26204849

  11. Replacement steam dryer design and analysis for the Monticello nuclear plant

    International Nuclear Information System (INIS)

    Boiling Water Reactor (BWR) steam dryers are utilized as the final stage of moisture removal to provide high quality steam to the turbine. The Monticello Nuclear Generating Plant has begun a generating capacity expansion project that will increase electrical output by 13% or 71 MW. A replacement steam dryer has been designed for Monticello to meet performance requirements at the current and increased power levels. The robust design is based on many years of successful operating history in the Nordic region of Europe, including operation at up-rated conditions. Advanced analytical techniques and test results used in the design and qualification of the replacement dryer will be presented, including techniques to determine the moisture carryover. The design analysis incorporates techniques to assess the structural integrity of the steam dryer, including evaluation of high cycle fatigue loads due to acoustic resonance. The Westinghouse acoustic load definition methodology, which consists of a combination of analytical methods, sub-scale model testing, and plant measurements, provides an accurate prediction of the three-dimensional acoustic pressure field on the steam dryer surfaces. These loads are used to perform a comprehensive steam dryer structural analysis. (authors)

  12. Wetness measurements in a model multistage low pressure steam turbine

    International Nuclear Information System (INIS)

    Comprehensive measurement of wetness losses, exhaust fog droplet diameters, wetness and coarse water content have been taken in a model multistage LP steam turbine over a wide range of flow conditions. It was found that for conventional condensing turbine exhaust wetness fractions of approximately 0.10, the measured wetness loss factor was in reasonable agreement with the Baumann value. Comparison of exhaust wetness fractions derived from dynamometer power and five-hole probe radial traverse measurements, with those found independently from the Central Electricity Research Laboratories optical probe traverses, generally showed agreement to within approximately ±0.01. (author)

  13. Fever of undetermined etiology after cleaning of steam turbine condensers.

    Science.gov (United States)

    Deubner, D C; Gilliam, D K

    1977-01-01

    Two outbreaks of a febrile syndrome marked by chills, headaches, myalgia, nausea, and malaise occurred in workers who had cleaned the steam condensers of electric power turbines. Mean incubation period was 38 hours. Twenty-two of twenty-three exposed men became ill. Clinical and environmental investigation failed to reveal the etiology of the outbreaks. The circumstances and clinical syndrome have points of similarity to fever following inhalation of metal fumes and low-grade, stained cotton dust, and to Pontiac fever. PMID:869594

  14. Thermo-economic study on the implementation of steam turbine concepts for flexible operation on a direct steam generation solar tower power plant

    Science.gov (United States)

    Topel, Monika; Ellakany, Farid; Guédez, Rafael; Genrup, Magnus; Laumert, Björn

    2016-05-01

    Among concentrating solar power technologies, direct steam generation solar tower power plants represent a promising option. These systems eliminate the usage of heat transfer fluids allowing for the power block to be run at greater operating temperatures and therefore further increasing the thermal efficiency of the power cycle. On the other hand, the current state of the art of these systems does not comprise thermal energy storage as there are no currently available and techno-economically feasible storage integration options. This situation makes direct steam generation configurations even more susceptible to the already existing variability of operating conditions due to the fluctuation of the solar supply. In the interest of improving the annual performance and competitiveness of direct steam generation solar tower systems, the present study examines the influence of implementing two flexibility enhancing concepts which control the steam flow to the turbine as a function of the incoming solar irradiation. The proposed concepts were implemented in a reference plant model previously developed by the authors. Then, a multi-objective optimization was carried out in order to understand which configurations of the steam turbine concepts yield reductions of the levelized cost of electricity at a lower investment costs when compared to the reference model. Results show that the implementation of the proposed strategies can enhance the thermo-economic performance of direct steam generation systems by yielding a reduction of up to 9.2% on the levelized cost of electricity, mainly due to allowing 20% increase in the capacity factor, while increasing the investment costs by 7.8%.

  15. Simulation study on dynamic characteristic of steam condenser for steam discharge system

    International Nuclear Information System (INIS)

    A two-phase flow simulation model for steam condenser was established, according to the structure and work characteristics of high pressure and specified pressure of the steam condenser. By means of the model, steady-state calculation and dynamic characteristic simulation of the steam condenser were performed. The steady-state simulation results were verified with the steam condenser test results. The results show that the developed model can be used to simulate the steam condenser of the marine nuclear power plant dynamics in real-time. The research results can be meaningful to the design of the operation and control system for secondary system startup and shutdown. (authors)

  16. Modelling 3D Steam Turbine Flow Using Thermodynamic Properties of Steam Iapws-95

    Directory of Open Access Journals (Sweden)

    Rusanow A.V.

    2016-01-01

    Full Text Available An approach to approximate equations of state for water and steam (IAPWS-95 for the calculation of three-dimensional flows of steam in turbomachinery in a range of operation of the present and future steam turbines is described. Test calculations of three-dimensional viscous flow in an LP steam turbine using various equations of state (perfect gas, Van der Waals equation, equation of state for water and steam IAPWS-95 are made. The comparison of numerical results with experimental data is also presented.

  17. Steam generator tubing NDE performance

    Energy Technology Data Exchange (ETDEWEB)

    Henry, G. [Electric Power Research Institute, Charlotte, NC (United States); Welty, C.S. Jr. [Electric Power Research Institute, Palo Alto, CA (United States)

    1997-02-01

    Steam generator (SG) non-destructive examination (NDE) is a fundamental element in the broader SG in-service inspection (ISI) process, a cornerstone in the management of PWR steam generators. Based on objective performance measures (tube leak forced outages and SG-related capacity factor loss), ISI performance has shown a continually improving trend over the years. Performance of the NDE element is a function of the fundamental capability of the technique, and the ability of the analysis portion of the process in field implementation of the technique. The technology continues to improve in several areas, e.g. system sensitivity, data collection rates, probe/coil design, and data analysis software. With these improvements comes the attendant requirement for qualification of the technique on the damage form(s) to which it will be applied, and for training and qualification of the data analysis element of the ISI process on the field implementation of the technique. The introduction of data transfer via fiber optic line allows for remote data acquisition and analysis, thus improving the efficiency of analysis for a limited pool of data analysts. This paper provides an overview of the current status of SG NDE, and identifies several important issues to be addressed.

  18. Innovations relative to steam generators

    International Nuclear Information System (INIS)

    In the last decade the main object of attention in nuclear engineering has been that of safety; safety understood fundamentally as a study and examination of the possible consequences of accidents and of the devices for and phases of automatic protective intervention. Another problem of safety, that which concerns the criteria aimed at a less complex construction with advantages for transport, setting up, management, maintenance and decomissioning, seems, instead, to be ignored. The use of less specialised workshops for construction, easier control of the state of the structures and the possibility of substituing components during the life of the plant are factors with a direct influence on safety. These aspects, mainly of a creative engineering nature, are the concern of the MARS (Multipurpose Advanced Reactor inherently Safe) project. This memo concerns the innovations introduced by the project relative to the steam generator which is being realised by means of the assembly in situ of 5 sub-components of considerably reduced dimensions and weight with respect to traditional methods of uni-block construction. The economic-management benefits appear significant. Added to the proposal is a brief study for the removal and substitution of the tubing of the steam generator inside the reactor building

  19. Steam turbine materials and corrosion

    Energy Technology Data Exchange (ETDEWEB)

    Holcomb, G.R.; Ziomek-Moroz, M.

    2007-01-01

    Ultra supercritical (USC) power plants offer the promise of higher efficiencies and lower emissions. Current goals of the U.S. Department of Energy’s Advanced Power Systems Initiatives include coal generation at 60% efficiency, which would require steam temperatures of up to 760°C. This research examines the steamside oxidation of alloys for use in USC systems, with emphasis placed on applications in high- and intermediate-pressure turbines. The list of alloys being examined is discussed, including the addition of new alloys to the study. These include alloy 625, selected because of its use as one of the two alloys used for turbine rotors, valves, casings, blading and bolts in the European AD700 full-scale demonstration plant (Scholven Unit F). The other alloy, alloy 617, is already one of the alloys currently being examined by this project. Other new alloys to the study are the three round robin alloys in the UK-US collaboration: alloys 740, TP347HFG, and T92. Progress on the project is presented on cyclic oxidation in 50% air – 50% water vapor, furnace exposures in moist air, and thermogravimetric analysis in argon with oxygen saturated steam. An update on the progress towards obtaining an apparatus for high pressure exposures is given.

  20. BWR steam separator swirler optimization

    International Nuclear Information System (INIS)

    The initial phase of a steam separator swirler optimization project has been completed. A half-scale cast acrylic steam separator and four different swirlers were designed and constructed. The four swirlers were fabricated by stereolithography techniques to reduce the time and expense of fabrication using traditional manufacturing methods. This test apparatus was used to experimentally measure the pressure drop across the swirlers utilizing a two-phase mixture of air and water. Two of the swirlers were designed to reduce pressure losses, one longer to reduce secondary flows and flow separation, and the other with extra vanes to reduce secondary flows. A third swirler with a low vane exit angle was used to determine the effect of swirl energy on pressure drop, and the fourth is a reference swirler developed in the 1960's, was used as a benchmark. An experimental method was developed and tested to provide correlations for measuring the pressure drop. Preliminary results suggest that the longer swirler has a lower pressure drop than the low vane exit angle swirler, and a lower pressure drop than the extra vane swirler. Results are not available for the benchmark swirler because the vanes were damaged during shakedown testing

  1. Steam generator tubing NDE performance

    International Nuclear Information System (INIS)

    Steam generator (SG) non-destructive examination (NDE) is a fundamental element in the broader SG in-service inspection (ISI) process, a cornerstone in the management of PWR steam generators. Based on objective performance measures (tube leak forced outages and SG-related capacity factor loss), ISI performance has shown a continually improving trend over the years. Performance of the NDE element is a function of the fundamental capability of the technique, and the ability of the analysis portion of the process in field implementation of the technique. The technology continues to improve in several areas, e.g. system sensitivity, data collection rates, probe/coil design, and data analysis software. With these improvements comes the attendant requirement for qualification of the technique on the damage form(s) to which it will be applied, and for training and qualification of the data analysis element of the ISI process on the field implementation of the technique. The introduction of data transfer via fiber optic line allows for remote data acquisition and analysis, thus improving the efficiency of analysis for a limited pool of data analysts. This paper provides an overview of the current status of SG NDE, and identifies several important issues to be addressed

  2. Behaviour of the steam generator tubing in water with different pH values

    International Nuclear Information System (INIS)

    Steam generators are crucial components of pressurized water reactors. The failure of the steam generator as a result of tube degradation by corrosion has been a major cause of Pressurized Heavy Water Reactor (PHWR) plant unavailability. Steam generator problems have caused major economic losses in terms of lost electricity production through forced unit outages and, in cases of extreme damage, as additional direct cost for large-scale repair or replacement of steam generators. The excellent performance to date of CANDU steam generators can be attributed, in part, to their design and performance characteristics, which typically involve higher recirculation ratios and lower heat fluxes and temperatures. However, the steam generator tubes are susceptible to failure by a variety of mechanisms, the vast majority of which are related to corrosion. The generalized corrosion is an undesirable process because it is accompanied by deposition of the corrosion products which affect the steam generator performances. It is very important to understand the generalized corrosion mechanism with the purpose of evaluating the quantities of corrosion products which exist in the steam generator after a determined period of operation. The purpose of the experimental research consists in the assessment of corrosion behaviour of the tubes material, Incoloy-800, at normal secondary circuit parameters (temperature-260 oC, pressure-5.1 MPa). The testing environment was the demineralised water without impurities, at different pH values regulated with morpholine and cyclohexylamine (all volatile treatment-AVT). The results are presented like micrographics and graphics representing weight loss of metal due to corrosion, corrosion rate, total corrosion products formed, the adherent corrosion products, released corrosion products, release rate of corrosion products and release rate of the metal.

  3. Behaviour of the steam generator tubing in water with different pH values

    Energy Technology Data Exchange (ETDEWEB)

    Lucan, Dumitra, E-mail: dumitra.lucan@nuclear.r [Department of Corrosion and Circuits Chemistry, Institute for Nuclear Research, POB 78, Pitesti (Romania)

    2011-04-15

    Steam generators are crucial components of pressurized water reactors. The failure of the steam generator as a result of tube degradation by corrosion has been a major cause of Pressurized Heavy Water Reactor (PHWR) plant unavailability. Steam generator problems have caused major economic losses in terms of lost electricity production through forced unit outages and, in cases of extreme damage, as additional direct cost for large-scale repair or replacement of steam generators. The excellent performance to date of CANDU steam generators can be attributed, in part, to their design and performance characteristics, which typically involve higher recirculation ratios and lower heat fluxes and temperatures. However, the steam generator tubes are susceptible to failure by a variety of mechanisms, the vast majority of which are related to corrosion. The generalized corrosion is an undesirable process because it is accompanied by deposition of the corrosion products which affect the steam generator performances. It is very important to understand the generalized corrosion mechanism with the purpose of evaluating the quantities of corrosion products which exist in the steam generator after a determined period of operation. The purpose of the experimental research consists in the assessment of corrosion behaviour of the tubes material, Incoloy-800, at normal secondary circuit parameters (temperature-260 {sup o}C, pressure-5.1 MPa). The testing environment was the demineralised water without impurities, at different pH values regulated with morpholine and cyclohexylamine (all volatile treatment-AVT). The results are presented like micrographics and graphics representing weight loss of metal due to corrosion, corrosion rate, total corrosion products formed, the adherent corrosion products, released corrosion products, release rate of corrosion products and release rate of the metal.

  4. Enhanced tubes for steam condensers. Volume 1, Summary of condensation and fouling; Volume 2, Detailed study of steam condensation

    Energy Technology Data Exchange (ETDEWEB)

    Webb, R.L.; Chamra, L.; Jaber, H.

    1992-02-01

    Electric utility steam condensers typically use plain tubes made of titanium, stainless steel, or copper alloys. Approximately two-thirds of the total thermal resistance is on the water side of the plain tube. This program seeks to conceive and develop a tube geometry that has special enhancement geometries on the tube (water) side and the steam (shell) side. This ``enhanced`` tube geometry, will provide increased heat transfer coefficients. The enhanced tubes will allow the steam to condense at a lower temperature. The reduced condensing temperature will reduce the turbine heat rate, and increase the plant peak load capability. Water side fouling and fouling control is a very important consideration affecting the choice of the tube side enhancement. Hence, we have consciously considered fouling potential in our selection of the tube side surface geometry. Using appropriate correlations and theoretical models, we have designed condensation and water side surface geometries that will provide high performance and be cleanable using sponge ball cleaning. Commercial tube manufacturers have made the required tube geometries for test purposes. The heat transfer test program includes measurement of the condensation and water side heat transfer coefficients. Fouling tests are being run to measure the waterside fouling resistance, and to the test the ability of the sponge ball cleaning system to clean the tubes.

  5. A comparison between exergetic and economic criteria for optimizing the heat recovery steam generators of gas-steam power plants

    International Nuclear Information System (INIS)

    CCGT (Combined-cycle gas turbines) are gaining an increasingly important role in power generation thanks to their high thermal efficiency, low installed cost and ready availability. Increasing natural gas prices, the optimization of CCGT operating parameters is becoming a topic of growing interest. In this paper two different methodologies for optimizing CCGTs are compared. The first aims to minimize the cost per unit of electricity generated, the second to minimize an objective function based on exergoeconomic principles accounting for the costs related with thermodynamic inefficiencies. Optimization results have been obtained considering different CCGT configurations, with single or multi-pressure HRSG (heat recovery steam generators), and varying the gas turbine technology, fuel price and plant capacity factor. A modular approach has been adopted to design a highly effective and flexible HRSG layout, in terms of number of pressure levels and arrangement of heat exchange sections along the flue gas path, together with the corresponding energy, exergy and cost balances, using an “interaction matrix”, with nodes between elementary components and towards the surrounding environment. - Highlights: • Two methods for optimizing the HRSG of gas-steam power plants are compared. • Decision variables are HRSG operating parameters and heat exchange sections layout. • Gas-steam power plants with single or multi-pressure HRSG are optimized. • Results of exergoeconomic optimization differ from those of COE minimization. • COE minimization allows to establish a proper ranking of CCGT configurations

  6. CHARACTERIZATION OF FRACTURED BEDROCK FOR STEAM INJECTION

    Science.gov (United States)

    The most difficult setting in which to conduct groundwater remediation is that where chlorinated solvents have penetrated fractured bedrock. To demonstrate the potential viability of steam injection as a means of groundwater clean-up in this type of environment, steam will be in...

  7. Replacement steam generators for pressurized water reactors

    International Nuclear Information System (INIS)

    Babcock and Wilcox Canada has developed an Advanced Series steam generator for PWR Systems. This design incorporates all of the features that have contributed to the successful CANDU steam generator performance. This paper presents an overview of the design features and how the overall design relates to the requirements of a PWR reactor system

  8. Third international seminar on horizontal steam generators

    International Nuclear Information System (INIS)

    The Third International Seminar on Horizontal Steam Generators held on October 18-20, 1994 in Lappeenranta, consisted of six sessions dealing with the topics: thermal hydraulic experiments and analyses, primary collector integrity, management of primary-to-secondary leakage accidents, feedwater collector replacement and discussion of VVER-440 steam generator safety issues

  9. Steam-frothing of milk for coffee

    DEFF Research Database (Denmark)

    Münchow, Morten; Jørgensen, Leif; Amigo Rubio, Jose Manuel;

    2015-01-01

    A method for evaluation of the foaming properties of steam-frothed milk, based on image analysis (feature extraction) carried out on a video taken immediately after foam formation, was developed. The method was shown to be able to analyse steam-frothed milk made using a conventional espresso mach...

  10. Third international seminar on horizontal steam generators

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

    The Third International Seminar on Horizontal Steam Generators held on October 18-20, 1994 in Lappeenranta, consisted of six sessions dealing with the topics: thermal hydraulic experiments and analyses, primary collector integrity, management of primary-to-secondary leakage accidents, feedwater collector replacement and discussion of VVER-440 steam generator safety issues.

  11. Process steam production from cotton gin trash

    Energy Technology Data Exchange (ETDEWEB)

    LePori, W.A.; Carney, D.B.; Lalk, T.R.; Anthony, R.G.

    1981-01-01

    A steam producing system based on fluidized-bed gasification of biomass materials is discussed. Limited experimental results are discussed and show that steam has been produced at rates of 334.3 kg/hr. (737 lbs/hr.) with 2.8 kg of stream produced for each kilogram of cotton gin trash (2.8 lb/lb.). ref.

  12. Effect of change of reheat steam temperature on operation economy of nuclear steam turbine

    International Nuclear Information System (INIS)

    Firstly, the reasons for the decreasing of the reheat steam temperature are analyzed. Secondly, the methods to calculate the effect of the changing of reheat steam temperature on the relative internal efficiency and ideal cycle thermal efficiency of the nuclear steam turbine are given, and the independence of relative internal efficiency and ideal cycle thermal efficiency of nuclear steam turbine is analyzed. Finally, the method to calculate the effect of the change of reheat steam temperature on the heat rate is given. The calculation results, by taking a 900 MW nuclear steam turbine as an example, show that when the reheat steam temperature decreases per 10 centigrade, the ideal cycle thermal efficiency decreases 0.0423%, the relative internal efficiency decreases 0.078%, and the heat rate of the turbine increases 0.1203%. (authors)

  13. Strategic maintenance plan for Cernavoda steam generators

    International Nuclear Information System (INIS)

    Steam generators are among the most important pieces of equipment in a nuclear power plant. They are required full time during the plant operation and obviously no redundancy exists. Past experience has shown that those utilities which implemented comprehensive steam generator inspection and maintenance programs and strict water chemistry controls, have had good steam generator performance that supports good overall plant performance. The purpose of this paper is to discuss a strategic Life Management and Operational-monitoring program for the Cernavoda steam generators. The program is first of all to develop a base of expertise for the management of the steam generator condition; and that is to be supported by a program of actions to be accomplished over time to assess their condition, to take measures to avoid degradation and to provide for inspections, cleaning and modifications as necessary. (author)

  14. Circumferential cracking of steam generator tubes

    Energy Technology Data Exchange (ETDEWEB)

    Karwoski, K.J.

    1997-04-01

    On April 28, 1995, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 95-03, {open_quote}Circumferential Cracking of Steam Generator Tubes.{close_quote} GL 95-03 was issued to obtain information needed to verify licensee compliance with existing regulatory requirements regarding the integrity of steam generator tubes in domestic pressurized-water reactors (PWRs). This report briefly describes the design and function of domestic steam generators and summarizes the staff`s assessment of the responses to GL 95-03. The report concludes with several observations related to steam generator operating experience. This report is intended to be representative of significant operating experience pertaining to circumferential cracking of steam generator tubes from April 1995 through December 1996. Operating experience prior to April 1995 is discussed throughout the report, as necessary, for completeness.

  15. Testing installation for a steam generator

    International Nuclear Information System (INIS)

    The invention proposes a testing installation for a steam generator associated to a boiler, comprising a testing exchanger connected to a feeding circuit in secondary fluid and to a circuit to release the steam produced, and comprising a heating-tube bundle connected to a closed circuit of circulation of a primary coolant at the same temperature and at the pressure than the primary fluid. The heating-tube bundle of the testing exchanger has the same height than the primary bundle of the steam generator and the testing exchanger is at the same level and near the steam generator and is fed by the same secondary fluid such as it is subject to the same operation phases during a long period. The in - vention applies, more particularly, to the steam generators of pressurized water nuclear power plants

  16. Operating experiences with 1 MW steam generator

    International Nuclear Information System (INIS)

    1 MW steam generator, which was planned as the first stage of steam generator development in Power Reactor and Nuclear Fuel Corp. (PNC) in Japan, is a single-unit, once-through, integrated shell and tube type with multi-helical coil tubes. It was completed in Oarai Engineering Center of PNC in March of 1971, and the various performance tests were carried out up to April, 1972. After the dismantle of the steam generator for structural inspection and material test, it was restored with some improvements. In this second 1 MW steam generator, small leak occurred twice during normal operation. After repairing the failure, the same kind of performance tests as the first steam generator were conducted in order to verify the thermal insulation effect of argon gas in downcomer zone from March to June, 1974. In this paper the above operating experiences were presented including the outline of some performance test results. (author)

  17. A drier unit for steam separators

    International Nuclear Information System (INIS)

    Description is given of a drier unit adapted to equip a water separator mounted in a unit for treating a wet steam fed from a high pressure enclosure, so as to dry and contingently superheat said steam prior to injecting same into a turbine low pressure stage. This drier unit is constituted by at least a stack of separating sheets maintained in parallel relationship and at a slight angle with respect to the horizontal so as to allow the water provided by wet steam to flow toward a channel communicating with a manifold, and by means for guiding the steam between the sheets and evenly distributing it. This can be applied to steam turbines in nuclear power stations

  18. Hockey-stick steam generator for LMFBR

    International Nuclear Information System (INIS)

    This paper presents the criteria and evaluation leading to the selection of the Hockey Stick Steam Generator Concept and subsequent development of that concept for LMFBR application. The selection process and development of the Modular Steam Generator (MSG) is discussed, including the extensive test programs that culminated in the manufacture and test of a 35 MW(t) Steam Generator. The design of the CRBRP Steam Generator is described, emphasizing the current status and a review of the critical structural areas. CRBRP steam generator development tests are evaluated, with a discussion of test objectives and rating of the usefulness of test results to the CRBRP prototype design. Manufacturing experience and status of the CRBRP prototype and plant units is covered. The scaleup of the Hockey Stick concept to large commercial plant application is presented, with an evaluation of scaleup limitations, transient effects, and system design implications

  19. Cleanliness criteria to improve steam generator performance

    International Nuclear Information System (INIS)

    High steam generator performance is a prerequisite for high plant availability and possible life time extension. The major opponent to that is corrosion and fouling of the heating tubes. Such steam generator degradation problems arise from the continuous ingress of non-volatile contaminants, i.e. corrosion products and salt impurities may accumulate in the steam generators. These impurities have their origin in the secondary side systems. The corrosion products generally accumulate in the steam generators and form deposits not only in the flow restricted areas, such as on top of tube sheet and tube support structure, but also build scales on the steam generator heating tubes. In addition, the tube scales in general affect the steam generator thermal performance, which ultimately causes a reduction of power output. The most effective ways of counteracting all these degradation problems, and thus of improving the steam generator performance is to keep them in clean conditions or, if judged necessary, to plan cleaning measures such as mechanical tube sheet lancing or chemical cleaning. This paper presents a methodology how to assess the cleanliness condition of a steam generator by bringing together all available operational and inspection data such as thermal performance and water chemistry data. By means of this all-inclusive approach the cleanliness condition is quantified in terms of a fouling index. The fouling index allows to monitor the condition of a specific steam generator, compare it to other plants and, finally, to serve as criterion for cleaning measures such as chemical cleaning. The application of the cleanliness criteria and the achieved field results with respect to improvements of steam generator performance will be presented. (author)

  20. Comprehensive investigation of process characteristics for oxy-steam combustion power plants

    International Nuclear Information System (INIS)

    Highlights: • Oxy-steam combustion exhibits better performance than oxy-CO2 combustion. • Cost of electricity in oxy-steam combustion is 6.62% less than oxy-CO2 combustion. • The increase of oxygen concentration in oxidant can improve its system performance. • The decrease of excess oxygen coefficient can be helpful for its system performance. • Integration with solar technology can enhance its thermodynamic performance. - Abstract: Oxy-steam combustion, as an alternative option of oxy-fuel combustion technology, is considered as a promising CO2 capture technology for restraining CO2 emissions from power plants. To attain its comprehensive process characteristics, process simulation, thermodynamic assessment, and sensitivity analysis for oxy-steam combustion pulverized-coal-fired power plants are investigated whilst its corresponding CO2/O2 recycled combustion (oxy-CO2 combustion) power plant is served as the base case for comparison. Techno-economic evaluation and integration with solar parabolic trough collectors are also discussed to justify its economic feasibility and improve its thermodynamic performance further, respectively. It is found that oxy-steam combustion exhibits better performance than oxy-CO2 combustion on both thermodynamic and economic aspects, in which the cost of electricity decreases about 6.62% whilst the net efficiency and exergy efficiency increase about 0.90 and 1.01 percentage points, respectively. The increment of oxygen concentration in oxidant (20–45 mol.%) and decrease of excess oxygen coefficient (1.01–1.09) in a certain range are favorable for improving oxy-steam combustion system performance. Moreover, its thermodynamic performance can be improved when considering solar parabolic trough collectors for heating recycled water, even though its cost of electricity increases about 2 $/(MW h)

  1. The series of siemens SST-200 to SST-900 steam turbines in Russia

    Science.gov (United States)

    Kasilov, V. F.

    2015-04-01

    The chronology of cooperation between the transnational German concern Siemens and Russia is given. The designs of the SST-200-SST-900 series of industrial steam turbines for electrical capacities ranging from 10 to 180 MW that were installed at thermal power plants and industrial facilities of Russia in the period 2004-2014 are reviewed. The design features of the SST-600 steam turbine used as part of the PGU-200 combined-cycle plant installed at the Southwest cogeneration station are considered.

  2. Monitoring of large steam turbines, as seen by the constructor and the operator

    International Nuclear Information System (INIS)

    The electricity in France is produced by large steam turbines in the range of 125 000 kW to 1 300 000 kW in nuclear power plants. Some operation problems are encountered on these large machines. The aim of this study is to justify and to describe the monitoring process implemented on the large steam turbines. This short study is divided into three parts: the monitoring justification during the start-up period, one example of a monitoring system, the turbine monitoring during the operation period

  3. Design of PFBR steam generator

    International Nuclear Information System (INIS)

    Vertical straight tube with an expansion bend in sodium path is the design selected for the steam generators of 500 MWe Prototype Fast Breeder Reactor (PFBR). There are 4 secondary loops with each loop consisting of 3 modules. With sodium reheat incorporated each module comprises of one evaporator, superheater and reheater. Material of construction is 2.25Cr-1Mo for evaporator and 9Cr-1Mo for superheater and reheater. The tube to tubesheet weld is internal bore butt weld with tubesheet having raised spigot. Aim is to have reliable design with higher plant availability. Design considerations leading to the choice of design features selected are discussed in the paper and a ''reference'' design has been described. (author). 2 figs, 1 tab

  4. Phenomenological modelling of steam explosions

    International Nuclear Information System (INIS)

    During a hypothetical core meltdown accident, an important safety issue to be addressed is the potential for steam explosions. This paper presents analysis and modelling of experimental results. There are four observations that can be drawn from the analysis: (1) vapor explosions are suppressed by noncondensible gases generated by fuel oxidation, by high ambient pressure, and by high water temperatures; (2) these effects appear to be trigger-related in that an explosion can again be induced in some cases by increasing the trigger magnitude; (3) direct fuel liquid-coolant liquid contact can explain small scale fuel fragmentation; (4) heat transfer during the expansion phase of the explosion can reduce the work potential

  5. Steels for large steam pipes

    International Nuclear Information System (INIS)

    Presented are the results of pilot-scale operation and scientific investigation of metal of pipes 500 to 1100 mm in diameter manufactured by various techniques from 15Kh1M1F steel. The structure and the properties of the metal of ten meltings were investigated for homogeneity in the following zones: base metal, near-weld zone and weld metal. It was found that the macrostructure of pipes cast by a centrifugal method has a fairly dense structure; there is homogeneity across and lengthwise of the pipe. After a heat treatment, the metal of centrifugally cast pipes has both high short-time and long-time properties. Introduction of centrifugally cast pipe manufacture opens possibilities for using larger pipes in steam conduits of hot intermediate superheating devices

  6. The effect of steam separataor efficiency on transient following a steam line break

    International Nuclear Information System (INIS)

    Detailed thermalhydraulic simulations for CANDU 6 steam line break inside containment are performed to predict the response of the primary and secondary circuits. The analysis is performed using the thermalhydraulic computer code, CATHENA, with a coupled primary and secondary circuit model. A two-loop representation of the primary and secondary circuits is modelled. The secondary circuit model includes the feedwater line from the deaerator storage tank, multi-node steam generators and the steam line up to the turbine. Two cases were carried out using different assumptions for the efficiency of the steam separators. Case 1 assumes the efficiency of the steam separators becomes zero when the water level in the steam drum increases to the elevation of primary cyclones, or the outlet flow from the steam generator becomes higher than 150 % of normal flow. Case 2 assumes the efficiency becomes zero only when the water level in the steam drum reaches the elevation of primary cyclones. The simulation results show that system responses are sensitive to the assumption for the efficiency of the steam separators and case 1 gives higher discharge energy. Fuel cooling is assured, since primary circuit is cooled down sufficiently by the steam generators for both cases. (author)

  7. Design improvement and test verification of steam flow limiter of steam generator

    International Nuclear Information System (INIS)

    Background: Steam flow limiter is an important device of steam generator in nuclear power plant. It limits the steam flow during the event of steam line break. However, it is required that the steam flow limiter has low pressure loss during normal operation of steam generator. Purpose: The aim is to design a steam flow limiter with lower pressure loss. Methods: An improved design of steam flow limiter is developed by increasing the number of Venturies from 7 to 19. Two test models of steam flow limiters of traditional design and improved design are tested. Results: The pressure loss factor of the traditional design test model is 6.9. The pressure loss factor of the improved design test model is 4.4. Conclusion: Based on the same total throat flow area, it is verified by tests that the pressure loss of steam flow limiter containing 19 Venturis is significantly lower than that containing 7 Venturis. The pressure loss calculation method is verified simultaneously. (authors)

  8. Linearization of valve flow nonlinearities for large steam turbines

    International Nuclear Information System (INIS)

    The control valve for a large steam turbine in a power plant has the characteristic of nonlinearity. It is found that the flow increase is much greater for a given valve position change near the closed end of travel than it is near the open end. The steam flow in the system being proportional to the ultimate desired quantity of the turbine, it is preferable to have linear operation. Thus the automatic control can be applied to this nonlinear system and it is possible to keep the frequency of electricity constant by adjusting the control valve opening to the desired valve position. If the valve is opened less near the closed end of travel and greater near the open end, the desired linearization will be achieved. The way for linearization is producing the nonlinear electric compensation to the nonlinear system of control valves, viz. the electro hydraulic control (EHC). Transfer functions of the valve-position loop are obtained according to the different locations of nonlinear signal produced at the input to valve-position loop or in the feedback. (author)

  9. An expert system for steam generator maintenance

    International Nuclear Information System (INIS)

    The tube bundles in PWR steam generators are, by far, the major source of problems whether they are due to primary and secondary side corrosion mechanisms or to tube vibration-induced wear at tube support locations. Because of differences in SG operating, materials, and fabrication processes, the damage may differ from steam generator to steam generator. MPGV, an expert system for steam generator maintenance uses all steam generator data containing data on materials, fabrication processes, inservice inspection, and water chemistry. It has access to operational data for individual steam generators and contains models of possible degradation mechanisms. The objectives of the system are: · Diagnosing the most probable degradation mechanism or mechanisms by reviewing the entire steam generator history. · Identifying the tubes most exposed to future damage and evaluating the urgency of repair by simulating the probable development of the problem in time. · Establishing the appropriate preventive actions such as repair, inspection or other measures and establishing an action schedule. The system is intended for utilities either for individual plants before each inspection outage or any time an incident occurs or for a set of plants through a central MPGV center. (author)

  10. Steam generating system in LMFBR type reactors

    International Nuclear Information System (INIS)

    Purpose: To suppress the thermal shock loads to the structures of reactor system and secondary coolant system, for instance, upon plant trip accompanying turbine trip in the steam generation system of LMFBR type reactors. Constitution: Additional feedwater heater is disposed to the pipeway at the inlet of a steam generator in a steam generation system equipped with a closed loop extended from a steam generator by way of a gas-liquid separator, a turbine and a condensator to the steam generator. The separated water at high temperature and high pressure from a gas-liquid separator is heat exchanged with coolants flowing through the closed loop of the steam generation system in non-contact manner and, thereafter, introduced to a water reservoir tank. This can avoid the water to be fed at low temperature as it is to the steam generator, whereby the thermal shock loads to the structures of the reactor system and the secondary coolant system can be suppressed. (Moriyama, K.)

  11. Future development of large steam turbines

    International Nuclear Information System (INIS)

    An attempt is made to forecast the future of the large steam turbines till 1985. Three parameters affect the development of large turbines: 1) unit output; and a 2000 to 2500MW output may be scheduled; 2) steam quality: and two steam qualities may be considered: medium pressure saturated or slightly overheated steam (light water, heavy water); light enthalpie drop, high pressure steam, high temperature; high enthalpic drop; and 3) the quality of cooling supply. The largest range to be considered might be: open system cooling for sea-sites; humid tower cooling and dry tower cooling. Bi-fluid cooling cycles should be also mentioned. From the study of these influencing factors, it appears that the constructor, for an output of about 2500MW should have at his disposal the followings: two construction technologies for inlet parts and for high and intermediate pressure parts corresponding to both steam qualities; exhaust sections suitable for the different qualities of cooling supply. The two construction technologies with the two steam qualities already exist and involve no major developments. But, the exhaust section sets the question of rotational speed

  12. Failure analysis of retired steam generator tubings

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hong Pyo; Kim, J. S.; Hwang, S. S. and others

    2005-04-15

    Degradation of steam generator leads to forced outage and extension of outage, which causes increase in repair cost, cost of purchasing replacement power and radiation exposure of workers. Steam generator tube rupture incident occurred in Uljin 4 in 2002, which made public sensitive to nuclear power plant. To keep nuclear energy as a main energy source, integrity of steam generator should be demonstrated. Quantitative relationship between ECT(eddy current test) signal and crack size is needed in assesment of integrity of steam generator in pressurized water reactor. However, it is not fully established for application in industry. Retired steam generator of Kori 1 has many kinds of crack such as circumferential and axial primary water stress corrosion crack and outer diameter stress corrosion crack(ODSCC). So, it can be used in qualifying and improving ECT technology and in condition monitoring assesment for crack detected in ISI(in service inspection). In addition, examination of pulled tube of Kori 1 retired steam generator will give information about effectiveness of non welded sleeving technology which was employed to repair defect tubes and remedial action which was applied to mitigate ODSCC. In this project, hardware such as semi hot lab. for pulled tube examination and modification transportation cask for pulled tube and software such as procedure of transportation of radioactive steam generator tube and non-destructive and destructive examination of pulled tube were established. Non-destructive and destructive examination of pulled tubes from Kori 1 retired steam generator were performed in semi hot lab. Remedial actions applied to Kori 1 retired steam generator, PWSCC trend and bulk water chemistry and crevice chemistry in Kori 1 were evaluated. Electrochemical decontamination technology for pulled tube was developed to reduce radiation exposure and enhance effectiveness of pulled tube examination. Multiparameter algorithm developed at ANL, USA was

  13. Failure analysis of retired steam generator tubings

    International Nuclear Information System (INIS)

    Degradation of steam generator leads to forced outage and extension of outage, which causes increase in repair cost, cost of purchasing replacement power and radiation exposure of workers. Steam generator tube rupture incident occurred in Uljin 4 in 2002, which made public sensitive to nuclear power plant. To keep nuclear energy as a main energy source, integrity of steam generator should be demonstrated. Quantitative relationship between ECT(eddy current test) signal and crack size is needed in assesment of integrity of steam generator in pressurized water reactor. However, it is not fully established for application in industry. Retired steam generator of Kori 1 has many kinds of crack such as circumferential and axial primary water stress corrosion crack and outer diameter stress corrosion crack(ODSCC). So, it can be used in qualifying and improving ECT technology and in condition monitoring assesment for crack detected in ISI(in service inspection). In addition, examination of pulled tube of Kori 1 retired steam generator will give information about effectiveness of non welded sleeving technology which was employed to repair defect tubes and remedial action which was applied to mitigate ODSCC. In this project, hardware such as semi hot lab. for pulled tube examination and modification transportation cask for pulled tube and software such as procedure of transportation of radioactive steam generator tube and non-destructive and destructive examination of pulled tube were established. Non-destructive and destructive examination of pulled tubes from Kori 1 retired steam generator were performed in semi hot lab. Remedial actions applied to Kori 1 retired steam generator, PWSCC trend and bulk water chemistry and crevice chemistry in Kori 1 were evaluated. Electrochemical decontamination technology for pulled tube was developed to reduce radiation exposure and enhance effectiveness of pulled tube examination. Multiparameter algorithm developed at ANL, USA was

  14. Commercial Nuclear Steam-Electric Power Plants, Part II

    Science.gov (United States)

    Shore, Ferdinand J.

    1974-01-01

    Presents the pros and cons of nuclear power systems. Includes a discussion of the institutional status of the AEC, AEC regulatory record, routine low-level radiation hazards, transport of radioactive materials, storage of wastes, and uranium resources and economics of supply. (GS)

  15. Final MTI Data Report: Comanche Peak Steam Electric Station

    International Nuclear Information System (INIS)

    During the periods from May 2000 to September 2001 and March 5 to April 10, 2002, cooling-lake surface water temperature data was collected at the Comanche Peak Nuclear Power Station near Granbury, Texas. This effort was led by the Savannah River Technology Center (SRTC) with the assistance of plant personnel. Permission for setting up these monitoring sites was granted by TXU Energy, which owns the plant site and surrounding property including Squaw Creek reservoir where the measurements were taken. This work was done in support of SRTC's ground truth mission for the U.S. Department of Energy's Multispectral Thermal Imager (MTI) satellite

  16. Steam Generator Inspection Planning Expert System

    International Nuclear Information System (INIS)

    Applying Artificial Intelligence technology to steam generator non-destructive examination (NDE) can help identify high risk locations in steam generators and can aid in preparing technical specification compliant eddy current test (ECT) programs. A steam Generator Inspection Planning Expert System has been developed which can assist NDE or utility personnel in planning ECT programs. This system represents and processes its information using an object oriented declarative knowledge base, heuristic rules, and symbolic information processing, three artificial intelligence based techniques incorporated in the design. The output of the system is an automated generation of ECT programs. Used in an outage inspection, this system significantly reduced planning time

  17. High speed drying of saturated steam

    International Nuclear Information System (INIS)

    This paper describes the development of the drying process for the saturated steam used in the PWR nuclear plant turbines in order to prevent negative effects of water on turbine efficiency, maintenance costs and equipment lifetime. The high speed drying concept is based on rotating the incoming saturated steam in order to separate water which is more denser than the steam; the water film is then extracted through an annular slot. A multicellular modular equipment has been tested. Applications on high and low pressure extraction of various PWR plants are described (Bugey, Loviisa)

  18. Modernization and life time extension on steam power plants in Eastern Europe and Russia

    Science.gov (United States)

    Kupetz, M.; Jenikejew, E.; Hiss, F.

    2014-06-01

    The Eastern European electricity markets with focus on Russia and Ukraine are suffering severe aging of the existing LMZ, UTZ and Turboatom steam turbine fleets after more than 25 years of operation. Energy efficient modernizations along with life time extension beyond the designed life time of existing old power plants is an economical option to address the increasing power demand. Steam Turbine modernizations are using latest state of the art materials and technology-enhanced turbine components such as blades, sealing, guide blade carriers, inner casings and rotors as well as components for auxiliary systems e.g. lube and lifting oil thus providing increased efficiency and optimized maintainability. This paper outlines unique design features and pre-engineered modules of the Siemens steam turbine modernization applications for thermal power stations, emphasizing the solutions for Turboatom 300 MW and LMZ 200 MW turbine-generators. The paper concludes with references and operational experience.

  19. Sizing techniques for crack indications od eddy current data in steam generator tubes

    International Nuclear Information System (INIS)

    This paper describes the sizing methodology for stress corrosion cracking which lies in steam generator tubes. It is not easy to analyze exactly the depth and length of the crack from the eddy current data. The crack-sizing for the steam generator tube during the in-service inspection was not performed until July 2005 in Korea. However it is necessary to evaluate the depth and length of the crack in order to complete the condition monitoring and operational assessment of the Steam Generator Management Program. The currently available crack-sizing techniques were introduced from Electric Power Research Institute. Prior to applying to the field analysis, the round robin tests for those techniques were carried out by the domestic analysts. The results suggest that it is necessary to develop new techniques since the deviations for some types of crack are relatively large.

  20. Proceedings of the third international steam generator and heat exchanger conference

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    The Third International Steam Generator and Heat Exchanger conference had the objective to present the state of knowledge of steam generator performance and life management, and also heat exchanger technology. As this conference followed on from the previous conferences held in Toronto in 1990 and 1994, the emphasis was on recent developments, particularly those of the last 4 years. The conference provided an opportunity to operators, designers and researchers in the field of steam generation associated with electricity generation by nuclear energy to present their findings and exchange ideas. The conference endeavoured to do this over the widest possible range of subject areas,including: general operating experience, life management and fitness for service strategies, maintenance and inspection, thermalhydraulics, vibration, fretting and fatigue, materials, chemistry and corrosion and the regulatory issues.

  1. Study of advanced radial outflow turbine for solar steam Rankine engines

    Science.gov (United States)

    Martin, C.; Kolenc, T.

    1979-01-01

    The performance characteristics of various steam Rankine engine configurations for solar electric power generation were investigated. A radial outflow steam turbine was investigated to determine: (1) a method for predicting performance from experimental data; (2) the flexibility of a single design with regard to power output and pressure ratio; and (3) the effect of varying the number of turbine stages. All turbine designs were restricted to be compatible with commercially available gearboxes and generators. A study of several operating methods and control schemes for the steam Rankine engine shows that from an efficiency and control simplicity standpoint, the best approach is to hold turbine inlet temperature constant, vary turbine inlet pressure to match load, and allow condenser temperature to float maintaining constant heat rejection load.

  2. Proceedings of the third international steam generator and heat exchanger conference

    International Nuclear Information System (INIS)

    The Third International Steam Generator and Heat Exchanger conference had the objective to present the state of knowledge of steam generator performance and life management, and also heat exchanger technology. As this conference followed on from the previous conferences held in Toronto in 1990 and 1994, the emphasis was on recent developments, particularly those of the last 4 years. The conference provided an opportunity to operators, designers and researchers in the field of steam generation associated with electricity generation by nuclear energy to present their findings and exchange ideas. The conference endeavoured to do this over the widest possible range of subject areas, including: general operating experience, life management and fitness for service strategies, maintenance and inspection, thermalhydraulics, vibration, fretting and fatigue, materials, chemistry and corrosion and the regulatory issues

  3. Coal lumps vs. electrons: How do Chinese bulk energy transport decisions affect the global steam coal market?

    International Nuclear Information System (INIS)

    This paper demonstrates the ways in which different Chinese bulk energy transport strategies affect the future steam coal market in China and in the rest of the world. An increase in Chinese demand for steam coal will lead to a growing need for additional domestic infrastructure as production hubs and demand centers are spatially separated, and domestic transport costs could influence the future Chinese steam coal supply mix. If domestic transport capacity is available only at elevated costs, Chinese power generators could turn to the global trade markets and further increase steam coal imports. Increased Chinese imports could then yield significant changes in steam coal market economics on a global scale. This effect is analyzed in China, where coal is mainly transported by railway, and in another setting where coal energy is transported as electricity. For this purpose, a spatial equilibrium model for the global steam coal market has been developed. One major finding is that if coal is converted into electricity early in the supply chain, worldwide marginal costs of supply are lower than if coal is transported via railway. Furthermore, China's dependence on international imports is significantly reduced in this context. Allocation of welfare changes particularly in favor of Chinese consumers while rents of international producers decrease.

  4. 49 CFR 229.105 - Steam generator number.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Steam generator number. 229.105 Section 229.105..., DEPARTMENT OF TRANSPORTATION RAILROAD LOCOMOTIVE SAFETY STANDARDS Safety Requirements Steam Generators § 229.105 Steam generator number. An identification number shall be marked on the steam...

  5. 7 CFR 160.8 - Steam distilled wood turpentine.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 3 2010-01-01 2010-01-01 false Steam distilled wood turpentine. 160.8 Section 160.8... STANDARDS FOR NAVAL STORES General § 160.8 Steam distilled wood turpentine. The designation “steam distilled... wood, and commonly known prior to the passage of the act as wood turpentine, steam distilled...

  6. Numerical simulation and experimental investigation of structural optimization of capacitance sensors for measuring steam wetness with different coaxial cylinders

    International Nuclear Information System (INIS)

    Highlights: • A simulation on capacitance sensors with different coaxial cylinders is performed. • An experimental system is designed to measure steam wetness. • A sensor performance depends on the plate thickness, plate length and plate separation. • The max discrepancy of the experimental and numerical simulation result is 19.8%. -- Abstract: Steam wetness is an important parameter, which is difficult to measure accurately. A simulation study is performed based on the theories of electrodynamics and hydrodynamics to investigate the characteristics of wetness capacitance sensors with different coaxial cylinders, and an experimental system and two capacitance probes were designed to measure steam wetness. Using a FLUENT user defined function (UDF) code, a program to compute the electric field was compiled which can transmit the data between the electric field and the flow field. The coupling of the steam flow field and the electric field within the sensors is investigated through numerical simulation. The results show that the electric field intensity decreases from the inner electrode plate to the outer electrode plate. The electric field intensity near the inner plate increases with increasing plate thickness while the sensor length has no effect on the electric field intensity distribution in the radial direction, but the peak electric field intensity decreases with increasing sensor length. The peak electric field intensity weakens with increasing electrode separation. Comparison of the numerical simulation results and the experimental results shows that the results of the simulation are similar to those of the experiments, with the output capacitance fluctuating around a fixed value as the steam flow rate changes and increasing linearly with increasing wetness. The maximum difference between the experimental data and the numerical simulation data is 0.78 nF, which is a discrepancy of 19.8%

  7. Study of Scaling Development on Tube Surfaces of Water Steam Loop in Steam Generator of CEFR

    Institute of Scientific and Technical Information of China (English)

    ZHANG; Lu; LIU; Fu-chen; LUO; De-kang; WU; Qiang; ZHANG; Huan-qi

    2012-01-01

    <正>The steam generator worked as pressure boundary of Na-H2O loop in China Experimental FastReactor (CEFR), which was quite important for nuclear reactor safety. Once the tubes separating the water from steam leak because of corrosion by scaling, Na-H2O reaction would lead to severe accident. So it’s critically important to study how the scaling develops on the water-steam sides.

  8. Natural circulation steam generator model for optimal steam generator water level control

    International Nuclear Information System (INIS)

    Several authors have cited the control of steam generator water level as an important problem in the operation of pressurized water reactor plants. In this paper problems associated with steam generator water level control are identified, and advantages of modern estimation and control theory in dealing with these problems are discussed. A new state variable steam generator model and preliminary verification results using data from the loss of fluid test (LOFT) plant are also presented

  9. Supercritical steam cycles and biomass integrated gasification combined cycles for sugarcane mills

    Energy Technology Data Exchange (ETDEWEB)

    Pellegrini, Luiz Felipe; Burbano, Juan Carlos [Laboratory of Environmental and Thermal Engineering, Polytechnic School - University of Sao Paulo, Av. Prof. Luciano Gualberto, 1289 Cidade Universitaria, CEP: 05508-900, Sao Paulo, SP (Brazil); de Oliveira Junior, Silvio [Mechanical Engineering Faculty, Technological University of Pereira, Pereira (Colombia)

    2010-02-15

    Back in 1970s and 1980s, cogeneration plants in sugarcane mills were primarily designed to consume all bagasse, and produce steam and electricity to the process. The plants used medium pressure steam boilers (21 bar and 300 C) and backpressure steam turbines. Some plants needed also an additional fuel, as the boilers were very inefficient. In those times, sugarcane bagasse did not have an economic value, and it was considered a problem by most mills. During the 1990s and the beginning of the 2000s, sugarcane industry faced an open market perspective, thus, there was a great necessity to reduce costs in the production processes. In addition, the economic value of by-products (bagasse, molasses, etc.) increased, and there was a possibility of selling electricity to the grid. This new scenario led to a search for more advanced cogeneration systems, based mainly on higher steam parameters (40-80 bar and 400-500 C). In the future, some authors suggest that biomass integrated gasification combined cycles are the best alternative to cogeneration plants in sugarcane mills. These systems might attain 35-40% efficiency for the power conversion. However, supercritical steam cycles might also attain these efficiency values, what makes them an alternative to gasification-based systems. This paper presents a comparative thermoeconomic study of these systems for sugarcane mills. The configurations studied are based on real systems that could be adapted to biomass use. Different steam consumptions in the process are considered, in order to better integrate these configurations in the mill. (author)

  10. A high-temperature gas-and-steam turbine plant operating on combined fuel

    Science.gov (United States)

    Klimenko, A. V.; Milman, O. O.; Shifrin, B. A.

    2015-11-01

    A high-temperature gas-steam turbine plant (GSTP) for ultrasupercritical steam conditions is proposed based on an analysis of prospects for the development of power engineering around the world and in Russia up to 2040. The performance indicators of a GSTP using steam from a coal-fired boiler with a temperature of 560-620°C with its superheating to 1000-1500°C by firing natural gas with oxygen in a mixingtype steam superheater are analyzed. The thermal process circuit and design of a GSTP for a capacity of 25 MW with the high- and intermediate-pressure high-temperature parts with the total efficiency equal to 51.7% and the natural gas utilization efficiency equal to 64-68% are developed. The principles of designing and the design arrangement of a 300 MW GSTP are developed. The effect of economic parameters (the level and ratio of prices for solid fuel and gas, and capital investments) on the net cost of electric energy is determined. The net cost of electric energy produced by the GSTP is lower than that produced by modern combined-cycle power plants in a wide variation range of these parameters. The components of a high-temperature GSTP the development of which determines the main features of such installations are pointed out: a chamber for combusting natural gas and oxygen in a mixture with steam, a vacuum device for condensing steam with a high content of nondensables, and a control system. The possibility of using domestically available gas turbine technologies for developing the GSTP's intermediate-pressure high-temperature part is pointed out. In regard of its environmental characteristics, the GSTP is more advantageous as compared with modern condensing power plants: it allows a flow of concentrated carbon dioxide to be obtained at its outlet, which can be reclaimed; in addition, this plant requires half as much consumption of fresh water.

  11. Steam Turbine Materials for Ultrasupercritical Coal Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Viswanathan, R.; Hawk, J.; Schwant, R.; Saha, D.; Totemeier, T.; Goodstine, S.; McNally, M.; Allen, D. B.; Purgert, Robert

    2009-06-30

    The Ultrasupercritical (USC) Steam Turbine Materials Development Program is sponsored and funded by the U.S. Department of Energy and the Ohio Coal Development Office, through grants to Energy Industries of Ohio (EIO), a non-profit organization contracted to manage and direct the project. The program is co-funded by the General Electric Company, Alstom Power, Siemens Power Generation (formerly Siemens Westinghouse), and the Electric Power Research Institute, each organization having subcontracted with EIO and contributing teams of personnel to perform the requisite research. The program is focused on identifying, evaluating, and qualifying advanced alloys for utilization in coal-fired power plants that need to withstand steam turbine operating conditions up to 760°C (1400°F) and 35 MPa (5000 psi). For these conditions, components exposed to the highest temperatures and stresses will need to be constructed from nickel-based alloys with higher elevated temperature strength than the highchromium ferritic steels currently used in today's high-temperature steam turbines. In addition to the strength requirements, these alloys must also be weldable and resistant to environmental effects such as steam oxidation and solid particle erosion. In the present project, candidate materials with the required creep strength at desired temperatures have been identified. Coatings that can resist oxidation and solid particle erosion have also been identified. The ability to perform dissimilar welds between nickel base alloys and ferritic steels have been demonstrated, and the properties of the welds have been evaluated. Results of this three-year study that was completed in 2009 are described in this final report. Additional work is being planned and will commence in 2009. The specific objectives of the future studies will include conducting more detailed evaluations of the weld-ability, mechanical properties and repair-ability of the selected candidate alloys for rotors

  12. Air/steam flow and steam wetness dependence on acoustic resonance in safety relief valves

    International Nuclear Information System (INIS)

    Many experimental studies related to the flow-induced acoustic resonance closed side branches have been reported. However, few studies have reported on the effects of air/steam flow and steam wetness dependence on fluctuating pressure amplitude. Therefore, we investigated the effect of air/steam flow and steam wetness dependence on fluctuating pressure amplitude by conducting a high temperature and high pressure tests at the Hitachi Utility Steam Test Leading Facility (HUSTLE). The test section consisted of a main pipe and a side branch. The side branch was mounted on the long straight main pipe. Fluctuating pressures at the end face of the side branches were measured. The following two results were obtained; the first is that the air/steam flow had little effect on the fluctuating pressure amplitude normalized by dynamic pressure and frequency normalized by the resonance frequency; the second is that under the acoustic resonance (St = 0.41) and non-resonance (St = 0.55) conditions, fluctuating pressure and frequency changed little with steam wetness. The steam wetness during the boiling water reactor operation was less than 0.1%; thus, there was no effect of steam wetness on the acoustic pressure amplitude and the frequency under this operating condition. (author)

  13. Study of steam condensation on laminar fluid jets for WWER steam generator operation in condensation mode

    International Nuclear Information System (INIS)

    The short review of experimental investigations on the steam and steam-gas mixture condensation on fluid jets is given. The experimental unit for steam and steam-gas mixture condensation on solid fluid jets applied to WWER passive safety systems operation is described. The technique developed for experiment performance permits study the peculiarities of heat transfer in given mode. For improving characteristics of experimental unit and investigation program optimization preliminary calculational simulation of the processes on the bench has been carried out using the RELAP5/mod 3,2 code

  14. LABORATORY SCALE STEAM INJECTION TREATABILITY STUDIES

    Science.gov (United States)

    Laboratory scale steam injection treatability studies were first developed at The University of California-Berkeley. A comparable testing facility has been developed at USEPA's Robert S. Kerr Environmental Research Center. Experience has already shown that many volatile organic...

  15. Steam condensation systems in reactor isolation

    International Nuclear Information System (INIS)

    Purpose: To enable stabilized operation of the steam condensating system in a BWR type nuclear power plant by the control of the water level in a residual heat removing heat exchanger. Constitution: In a steam condensating system comprising a residual heat removing heat exchanger (RHRHX) for receiving steams upon rapid stop of a main turbine, a cooling turbine in reactor isolation (RCIC turbine), and a cooling pump sucking condensated water from RHRHX and condensates from the RCIC turbine and recycling them to a reactor container, the water level in RHRHX is controlled by the pressure signal from a suction pipeway of the cooling pump and the water from the condensator that condensates steams from the gland of the RCIC turbine is fed to the locations other than the suction pipe, for example, to a pressure suppression chamber by a drain pump. (Furukawa, Y.)

  16. US PWR steam generator management: An overview

    Energy Technology Data Exchange (ETDEWEB)

    Welty, C.S. Jr. [Electric Power Research Institute, Palo Alto, CA (United States)

    1997-02-01

    This paper provides an overview on the status of steam generator management activities in US PWRs, and includes: (1) an overview of the impact of steam generator problems; (2) a brief discussion of historical damage trends and the current damage mechanism of most concern; (3) a discussion of the elements of {open_quotes}steam generator management{close_quotes}; and (4) a description of the approach being followed to implement a degradation-specific protocol for tubing inspection and repair. This paper was prepared in conjunction with another paper presented during the Plenary Session of this Conference, {open_quotes}Steam Generator Degradation: Current Mitigation Strategies for Controlling Corrosion{close_quotes}, and is provided as a supplement to that material.

  17. Accoustic background of BN-600 steam generator

    International Nuclear Information System (INIS)

    In this paper the results of accoustic background for BN-600 steam generator in nominal operating conditions are presented. The 1-200 kHz accoustic background of evaporator and reheater modules are given

  18. Ultrasonic testing of steam generator tubes

    International Nuclear Information System (INIS)

    A system is developed for inspection of steam generator tube, especially near the tube plate. Imaging, thickness measurement, radial profilometry, longitudinal and circonferential crack detection and welded joints testing are reviewed

  19. US PWR steam generator management: An overview

    International Nuclear Information System (INIS)

    This paper provides an overview on the status of steam generator management activities in US PWRs, and includes: (1) an overview of the impact of steam generator problems; (2) a brief discussion of historical damage trends and the current damage mechanism of most concern; (3) a discussion of the elements of open-quotes steam generator managementclose quotes; and (4) a description of the approach being followed to implement a degradation-specific protocol for tubing inspection and repair. This paper was prepared in conjunction with another paper presented during the Plenary Session of this Conference, open-quotes Steam Generator Degradation: Current Mitigation Strategies for Controlling Corrosionclose quotes, and is provided as a supplement to that material

  20. Significant observations from a PWR steam generator chemical cleaning qualification test program

    International Nuclear Information System (INIS)

    A qualification test program for the chemical cleaning of the secondary side of steam generators was conducted in anticipation of a potential application at Indian Point 2 (IP-2). The sludge removal effectiveness was evaluated using a large-scale test facility and both simulated consolidated sludge samples and sludge removed from IP-2 steam generators during prior sludge lancing. The test also mocked up the weld geometries and locations for an accurate galvanic corrosion assessment. This large-scale test and other preliminary tests had the following three aims: (1) optimize and demonstrate the sludge removal effectiveness of the Electric Power Research Institute/Steam Generator Owners Group (EPRI/SGOG) generic cleaning process for the Westinghouse Model 44 steam generators, (2) determine the corrosion effects of the process on Westinghouse Model 44 steam generator materials that would be exposed to the process, and (3) identify technical issues that should be addressed prior to field implementation of the process. The qualification test program also included the evaluation of an eddy current technique that measures sludge height in the presence of copper (IP-2 sludge contains more than 30 percent copper)