WorldWideScience
1

Environmental costs and benefits case study: nuclear power plant. Quantification and economic valuation of selected environmental impacts/effects. Final report  

International Nuclear Information System (INIS)

This case study is an application, to a nuclear power plant, of the methodology for quantifying environmental costs and benefits, contained in the regional energy plan, adopted in April, 1983, by the Northwest Power Planning Council, pursuant to Public Law 96-501.The study is based on plant number 2 of the Washington Public Power Supply System (WNP-2), currently nearing completion on the Hanford Nuclear Reservation in eastern Washington State. This report describes and documents efforts to quantify and estimate monetary values for the following seven areas of environmental effects: radiation/health effects, socioeconomic/infrastructure effects, consumptive use of water, psychological/health effects (fear/stress), waste management, nuclear power plant accidents, and decommissioning costs. 103 ...

2

Strategic Communication Enablers for the Regional ...  

Science.gov (United States)

... Joint Publication (JP) 5-0 (Washington DC: CJCS, 29 September ... and Execution System (JOPES) Volume 1. CJCSM 3122.01A (Washington, DC: 6 ...

2008-04-23

3

Remaining "Semper Paratus" in the 21st Century  

Science.gov (United States)

... Joint Publication (JP) 5 (Washington, DC: CJCS, 26 December 2006 ... Policies and Procedures, (Washington, DC: CJCSM, 3122.01A 29 September ...

2008-04-23

4

Five years operating experience at the Fast Flux Test Facility  

Energy Technology Data Exchange (ETDEWEB)

The Fast Flux Test Facility (FFTF) is a 400 Mw(t), loop-type, sodium-cooled, fast neutron reactor. It is operated by the Westinghouse Hanford Company for the United States Department of Energy at Richland, Washington. The FFTF is a multipurpose test reactor used to irradiate fuels and materials for programs such as Liquid Metal Reactor (LMR) research, fusion research, space power systems, isotope production and international research. FFTF is also used for testing concepts to be used in Advanced Reactors which will be designed to maximize passive safety features and not require complex shutdown systems to assure safe shutdown and heat removal. The FFTF also provides experience in the operation and maintenance of a reactor having prototypic components and systems typical of large LMR (LMFBR) power plants. The 5 year ...

1987-04-01

5

Five years operating experience at the Fast Flux Test Facility  

International Nuclear Information System (INIS)

The Fast Flux Test Facility (FFTF) is a 400 Mw(t), loop-type, sodium-cooled, fast neutron reactor. It is operated by the Westinghouse Hanford Company for the United States Department of Energy at Richland, Washington. The FFTF is a multipurpose test reactor used to irradiate fuels and materials for programs such as Liquid Metal Reactor (LMR) research, fusion research, space power systems, isotope production and international research. FFTF is also used for testing concepts to be used in Advanced Reactors which will be designed to maximize passive safety features and not require complex shutdown systems to assure safe shutdown and heat removal. The FFTF also provides experience in the operation and maintenance of a reactor having prototypic components and systems typical of large LMR (LMFBR) power plants. The 5 year ...

1987-09-13

6

Contingency interim measure for the public water supply at Barnes, Kansas.  

Energy Technology Data Exchange (ETDEWEB)

This document presents a conceptual design for a contingency interim measure (IM) for treatment of the public water supply system at Barnes, Kansas, should this become necessary. The aquifer that serves the public water supply system at Barnes has been affected by trace to low concentrations of carbon tetrachloride and its degradation product, chloroform. Investigations conducted on behalf of the CCC/USDA by Argonne National Laboratory (Argonne 2008a) have demonstrated that groundwater at the Barnes site is contaminated with carbon tetrachloride at concentrations exceeding the Kansas Tier 2 risk-based screening level (RBSL) and the EPA maximum contaminant level (MCL) of 5.0 {micro}g/L for this compound. The Commodity Credit Corporation of the U.S. Department of Agriculture (CCC/USDA) formerly operated a grain storage facility in Barnes, approximately 800 ft east-southeast of the ...

2009-07-09

7

Innovative Design of New Geothermal Generating Plants  

Energy Technology Data Exchange (ETDEWEB)

This very significant and useful report assessed state-of-the-art geothermal technologies. The findings presented in this report are the result of site visits and interviews with plant owners and operators, representatives of major financial institutions, utilities involved with geothermal power purchases and/or wheeling. Information so obtained was supported by literature research and data supplied by engineering firms who have been involved with designing and/or construction of a majority of the plants visited. The interviews were conducted by representatives of the Bonneville Power Administration, the Washington State Energy Office, and the Oregon Department of Energy during the period 1986-1989. [DJE-2005

1989-07-01

8

Biogas supply to the natural gas supply grid. Study; Einspeisung von Biogas in das Erdgasnetz. Studie  

Energy Technology Data Exchange (ETDEWEB)

Biogas supply to the public gas grid is a new option discussed in the most recent publication of Fachagentur Nachwachsende Rohstoffe (FNR) e.V. The biogas is purified, upgraded to natural gas quality and fed into an existing gas grid. Once there, it can be transported across long distances and also used for electric power generation at the consumer side. The study investigates inhowfar and in what instances this method is feasible and promising. It discusses the technical background and the regional potential of biogas. Seven model biogas systems are presented as examples. (orig.)

2006-07-01

9

FFTF: an outstanding engineering achievement  

International Nuclear Information System (INIS)

The Fast Flux Test Facility on the federal reservation at Hanford, Washington, has become a bright star in the universe of nuclear science and engineering technologies. The entire FFTF enterprise is now a success story, and this is particularly significant in these days when good news about nuclear power is scarce. The reactor, its testing capabilities and associated test facilities are described.

10

Liquid metal reactor cover gas purification and analysis in the USA  

International Nuclear Information System (INIS)

Two sodium cooled reactors are currently being operated in the United States of America for the US Department of Energy. These are Experimental Breeder Reactor 11, EBR-11, and the Fast Flux Test Facility, FFTF. EBR-11 is located near Idaho Falls, Idaho, and the FFTF is near Richland, Washington. These reactors are currently engaged in a wide range of testing including fuels and materials tests, and plant system performance and safety development. The US DOE program also includes designs of a next generation sodium cooled power reactor. The FFTF and EBR-11 communities are providing input to these designs. This paper discusses the efforts to develop and operate cover gas systems for the sodium cooled nuclear reactor program in the USA.

1986-09-24

11

Electricity supply in Germany  

Energy Technology Data Exchange (ETDEWEB)

Data on various aspects of the electric power industry in Germany is presented in this article. A map of high voltage transmission lines used by the public utilities is included, which indicates the fuel used at each power station. Data on power generated by fuel used from 1991 to 1996 is given, and additional or new capacity for 1995 to 1999 is also noted. Other tables detail capital investment in public utilities energy input by fuel source, power capacity by utility or private power stations by energy source, utility ownership and electricity demand by consumer. (UK)

1997-09-01

12

Design and operating experience of a 40 MW, highly-stabilized power supply  

Energy Technology Data Exchange (ETDEWEB)

Four 10 MW, highly-stabilized power supply modules have been installed at the National High Magnetic Field Laboratory in Tallahassee, FL, to energize water-cooled, resistive, high-field research magnets. The power supply modules achieve a long term current stability if 10 ppM over a 12 h period with a short term ripple and noise variation of <10 ppM over a time period of one cycle. The power supply modules can operate independently, feeding four separate magnets, or two, three or four modules can operate in parallel. Each power supply module consists of a 12.5 kV vacuum circuit breaker, two three-winding, step-down transformers, a 24-pulse rectifier with interphase reactors, and a passive and an active filter. Two different transformer tap settings allow rated dc supply output ...

1995-07-01

13

Reactor cover gas monitoring at the Fast Flux Test Facility  

International Nuclear Information System (INIS)

The Fast Flux Test Facility (FFTF) is a 400-megawatt (thermal) sodium-cooled reactor designed for irradiation testing of fuels, materials and components for LMRs. It is operated by the Westinghouse Hanford Company for the US Department of Energy on the government-owned Hanford reservation near Richland, Washington. The first 100-day operating cycle began in April 1982 and the eighth operating cycle was completed in July 1986. Argon is used as the cover gas for all sodium systems at the plant. A program for cover gas monitoring has been in effect since the start of sodium fill in 1978. The argon is supplied to the FFTF by a liquid argon Dewar System and used without further purification.

1986-09-24

14

2001 evaluation of juvenile fall chinook stranding on the Hanford Reach of the Columbia River.; TOPICAL  

International Nuclear Information System (INIS)

The Washington Department of Fish and Wildlife (WDFW) has been contracted through the Bonneville Power Administration (BPA) and the Grant County Public Utility District (GCPUD) to perform an evaluation of juvenile fall chinook salmon (Oncorhynchus tshawytscha) stranding on the Hanford Reach of the Columbia River. The evaluation, in the fifth year of a multi-year study, has been developed to assess the impacts of water fluctuations from Priest Rapids Dam on rearing juvenile fall chinook salmon, other fishes, and benthic macroinvertebrates of the Hanford Reach. This document provides the results of the 2001 field season.

15

2000 evaluation of juvenile fall chinook stranding on the Hanford Reach of the Columbia River.; TOPICAL  

International Nuclear Information System (INIS)

The Washington Department of Fish and Wildlife (WDFW) has been contracted through the Bonneville Power Administration (BPA) and the Grant County Public Utility District (GCPUD) to perform an evaluation of juvenile fall chinook salmon (Oncorhynchus tshawytscha) stranding on the Hanford Reach. The evaluation, in the fourth year of a multi-year study, has been developed to assess the impacts of water fluctuations from Priest Rapids Dam on rearing juvenile fall chinook salmon, other fishes, and benthic macroinvertebrates of the Hanford Reach. This document provides the results of the 2000 field season.

16

1999 evaluation of juvenile fall chinook stranding on the Hanford Reach of the Columbia River, annual report 1999.; ANNUAL  

International Nuclear Information System (INIS)

The Washington Department of Fish and Wildlife (WDFW) has been contracted through the Bonneville Power Administration (BPA) and the Grant County Public Utility District (GCPUD) to perform an evaluation of juvenile fall chinook salmon (Oncorhynchus tshawytscha) stranding on the Hanford Reach. The evaluation, in the third year of a multi-year study, has been developed to assess the impacts of water fluctuations from Priest Rapids Dam on rearing juvenile fall chinook salmon, other fishes, and benthic macroinvertebrates of the Hanford Reach. This document provides the results of the 1999 field season.

17

1998 evaluation of juvenile fall chinook salmon stranding on the Hanford Reach of the Columbia River.; TOPICAL  

International Nuclear Information System (INIS)

The Washington Department of Fish and Wildlife (WDFW) has been contracted through the Bonneville Power Administration (BPA) and the Grant County Public Utility District (GCPUD) to perform an evaluation of juvenile fall chinook salmon (Oncorhynchus tshawytscha) stranding on the Hanford Reach. The evaluation, in the second year of a multi-year study, has been developed to assess the impacts of water fluctuations from Priest Rapids Dam on rearing juvenile fall chinook salmon, other fish species, and benthic macroinvertebrates of the Hanford Reach. This document provides the results of the 1998 field season.

18

Research and development on next generation reactor (phase I)  

Energy Technology Data Exchange (ETDEWEB)

The objective of the study is to improve the volume of nuclear power plant which adopts passive safety system concept. The passive safety system reactor is characterized by excellent safety and reliability. But the volume of NSSS (Nuclear Steam Supply System) of the passive safety system reactor is so small that it should be upgraded for commercial operation. For volume upgrade, detailed analyses are performed as follows; core design, hydraulics, design and mechnical structures, and safety analysis. In addition to above analysis, some investigations must be supplied as follows: power density vs. DNB margin decrease, outlet temperature vs. EPRI-URD, additional tests for upgraded reactor, dynamic analysis of mechanical vibration according to expanded reactor vessel and expanded in-core structures, and Merit loss of passive ...

1994-10-01

19

Gas supplies of interstate natural gas pipeline companies, 1987  

Energy Technology Data Exchange (ETDEWEB)

Gas Supplies of Interstate Natural Gas Pipeline Companies 1987 was prepared by the Reserves and Natural Gas Division, Office of Oil and Gas, Energy Information Administration (EIA). The publication provides information on the total reserves, production, and deliverability capabilities of the 87 interstate pipeline companies required to file the Federal Energy Regulatory Commission (FERC) Form 15, ''Interstate Pipeline's Annual Report of Gas Supply.'' This publication is the 25th in a series of annual reports on the total gas supplies of interstate pipeline companies since the inception of individual company reports to the Federal Power Commission (FPC) in 1964 for report year 1963. This publication provides information on the interstate pipeline companies' supply of ...

1988-12-08

20

Waste management considerations for fusion power reactors  

International Nuclear Information System (INIS)

To estimate the waste management needs of a fusion power reactor, a scheme for handling radioactive waste from a fusion plant has been devised. The handling scheme proceeds with radioactive waste, primarily from blanket replacement, being stored on-site; waste in cooled and shielded casks is then isolated off-site; finally, the materials are recycled. Using activities and component lifetimes supplied by designers, several conceptual fusion power reactors have been analyzed and their waste streams compared to fission reactors with regard to total activity, specific activity, and lifetimes of activity.

21

Waste management considerations for fusion power reactors  

Science.gov (United States)

To estimate the waste management needs of a fusion power reactor, a scheme for handling radioactive waste from a fusion plant has been devised. The handling scheme proceeds with radioactive waste, primarily from blanket replacement, being stored on-site; waste in cooled and shielded casks is then isolated off-site; finally, the materials are recycled. Using activities and component lifetimes supplied by designers, several conceptual fusion power reactors have been analyzed and their waste streams compared to fission reactors with regard to total activity, specific activity, and lifetimes of activity.

1978-02-01

22

The Future of Amphibious Operations: Shaping the ...  

Science.gov (United States)

... WHS- Washington Headquarters Service. ... US Military (ie, Army, Navy, Air Force) service publications ... Strike Group to Fight in the Joint Task Force. ...

2010-02-01

23

Reforming Military Command Arrangements: The Case of the ...  

Science.gov (United States)

... WHS- Washington Headquarters Service. ... ie, Army, Navy, Air Force) service publications ... The Case of the Rapid Deployment Joint Task Force. ...

2011-03-01

24

Basic aspects of the concept of reactor compartment (including damaged compartments) management during utilization of nuclear powered submarines -- High priority R and D  

International Nuclear Information System (INIS)

Large-scale decommissioning of Russian nuclear-powered submarines (NPS) and their utilization prospects gave rise to numerous complicated scientific and technical, as well as economic, problems. Problems of handling of radioactive equipment from the reactor compartments (RC) are among the vital ones, arousing a growing concern with the public. Without solution of the problems the processes of NPS utilization can not be considered completed. It involves potential hazard, for the environment both from NPS being paid up (temporal on-float storage) with unloaded spent nuclear fuel (SNF), and RC, cut from submarine hull, containing highly radioactive equipment and materials but no SNF. Diverse variations of the concept of reactor compartment handling of NPS subject to, utilization are possible, but, in principle, there are essentially two variants: (1) RC utilization directly in the course of NPS ...

1996-03-10

25

UK's Sizewell inquiry; funny how time slips away  

Energy Technology Data Exchange (ETDEWEB)

Comments are made on the Public Inquiry into CEGB's proposal to construct a pressurized water reactor (PWR) at Sizewell, UK. Aspects discussed include: time elapsed and its possible effect on the result; economics of nuclear power plants compared with coal-fired power plants; changes in real sterling/dollar exchange rates; effect of mineworkers' strike; the UK electric power generating system; AGR reactors compared with PWR reactors; extension of Magnox reactor life; radioactive waste management; political decisions.

1985-03-01

28

The renaissance of solar homes; Le renouveau des maisons solaires  

Energy Technology Data Exchange (ETDEWEB)

This publication of the Areva Group, a world nuclear industry leader, provides information on the energy in many domains. This issue deals with the nuclear fuel cycle, the biofuels, the everyday geothermal power, the Unites States energy supply and types, the Bertrand Picard solar aircraft, the kyoto protocol and the wind power leaders. A special chapter is devoted to the renaissance of solar homes. (A.L.B.)

2004-07-01

29

Training and information technology issue, 2005  

Science.gov (United States)

The focus of the May-June issue is on training and information technology. Major articles/reports in this issue include: Communicating effectively, by Alain Bucaille, AREVA; Reputation management, by Susan Brisset, Bruce Power; Contol room and HSI modernization guidance, by Joseph Naser, EPRI; How far are we from public acceptance, by Jennifer A. Biedscheid and Murthy Devarakonda, Washington TRU Solutions LLC; Spent fuel management options, by Brent W. Dixon and Steven J. Piet, Idaho National Laboratory; Industry Awards; A secure energy future for America, by George W. Bush, President, United States of America; Vision of the future of nuclear energy, by Anne Lauvergeon, AREVA; and, Plant profile: strategy for transition to digital, TXU Power.

2005-05-15

30

A bibliography of AECL publications on reactor safety  

International Nuclear Information System (INIS)

AECL Publications on Reactor Safety in CANDU Reactors are listed in this bibliography. The listing is chronological and the accompanying index is by subject. The bibliography will be brought up to date annually. (auth).

1995-05-08

31

Wolsung-1 NPP - electrictal systems  

International Nuclear Information System (INIS)

... power reactors pressure tube reactors reactors THERMAL REACTORS.

1980-06-18

32

FFTF operating experience, 1982-1984  

International Nuclear Information System (INIS)

The Fast Flux Test Facility (FFTF) is a 400 Mwt sodium-cooled fast reactor operating at the Hanford Engineering Development Laboratory, Richland, Washington, to conduct fuels and materials testing in support of the US Liquid Metal Fast Breeder Reactor (LMFBR) program. Startup and initial power testing included a comprehensive series of nonnuclear and nuclear tests to verify the thermal, hydraulic, and neutronic characteristics of the plant. A specially designed series of natural circulation tests were then performed to demonstrate the inherent safety features of the plant. Early in 1982, the FFTF began its first 100-day irradiation cycle. Since that time the plant has operated very well, achieving a cycle capacity factor of 94% in the most recent irradiation cycle. Seventy-five specific test assemblies and 25,000 individual fuel pins have been irradiated, some in excess of 80 MWd/Kg.

1984-04-09

33

Public agency partnership: Hanford`s history artifacts as a communications tool  

Energy Technology Data Exchange (ETDEWEB)

The Hanford Site in eastern Washington state currently is engaged in the largest waste cleanup in world history. In order to make informed decisions about remediation options, the public throughout the Pacific Northwest and the nation needs to understand the wastes that are present, their sources of generation, their composition, and their behavior in the environment. The fact that Hanford operations` were conducted in secret for over four decades presents a unique public information challenge to those who currently are responsible for communicating with the public.

1994-02-01

34

Crumbling case for nuclear power  

Energy Technology Data Exchange (ETDEWEB)

In connection with the Public Inquiry into the CEGB proposal to build a pressurised water reactor at Sizewell in Suffolk, the case for nuclear power is examined under the headings: the economics of nuclear power - how they would like them to be; systems analysis - net effective cost; CEGB prejudices the results (comparison with coal-fired plants; forecasting on various assumptions); discounting future costs; back-end costs soar (reprocessing); real reprocessing costs; AGR costs balloon.

1983-01-01

35

Mobile and stationary hydrogen power supply large scale applications - a not acceptable public risk? The technical, physical and chemical events course evaluation from accidents combined with the basics of causalities causing it - a necessity to avoid future ones  

Energy Technology Data Exchange (ETDEWEB)

Use of hydrogen in large scale applications is more usual than public is mentioning normally. Nevertheless reserve against hydrogen can be observed up to highest level decision-makers. Possibly a main reason can be found and eliminated by fixing: Some spectacular accidents happened in the past and found great interest. The publication of impressive accidents and the follow up of the events course was very carefully. The research in finding causalities in former decisions and follow up was not in the interest of some people or institutions. Important facts are even not noticed by insiders, but would have been very important for future decision makings and public acceptance of new applications. It will be demonstrated in three historical examples. Much more examples would be available and each one could help to find new applications for a saver and effective use of hydrogen in power ...

2001-07-01

37

49 CFR 236.206 - Battery or power supply with respect to relay; location.  

Science.gov (United States)

...2010-10-01 2010-10-01 false Battery or power supply with respect to relay...Signal Systems Standards § 236.206 Battery or power supply with respect to relay; location. The battery or power supply for each signal...

2010-10-01

38

Utilization of wastes from coal-fired power plants for soil improvement and plant nutrition  

International Nuclear Information System (INIS)

The reduction of emission from power plants of the public power industry inevitably leads to more and more residual products being obtained which require utilization. Traditionally, the building and building materials industry as well as, for a number of years, the gypsum industry have been the main customers processing these residual materials. To avoid having to tip them at landfills that are in short supply already, further uses are sought; so, for instance, in farming to ameliorate soil and fertilize plants. Relative to this subject, proposals are already available which are presented as lectures at the conference and discussed, together with practical knowledge and new investigation results. (BBR).

1991-10-08

39

Innovative Elektrizit?tsversorgungssysteme f?r IKT  

British Library Electronic Table of Contents (United Kingdom)

Summary Modern society all over the world depends on information and communication technology (ICT); and security of supply with ICT is an important location factor. In times of increasing anonymity, which makes us more and more dependent on public services such as emergency supports (emergency organizations), communication is existential. Communication also plays an important role for a good functioning of economy and industry, in the course of shorter production and storage times. The usage of ICT is taken for granted. However, the modern society's use of ICT is profoundly dependent on the public power supply. Particularly in highly industrialized countries like e.g. Austria, the ICT sector requires about 10% of the total electric energy demand. One third of these 10% is estimated to be ...

2010-01-01

40

Interim remedial measures proposed plan for the 200-ZP-1 Operable Unit, Hanford Site, Washington  

Energy Technology Data Exchange (ETDEWEB)

The purpose of this interim remedial measures (IRM) proposed plan is to present and solicit public comments on the IRM planned for the 200-ZP-1 Operable Unit at the Hanford Site in Washington state. The 200-ZP-1 is one of two operable units that envelop the groundwater beneath the 200 West Area of the Hanford Site.

1993-12-01

41

Electrical grid stability and its impact on nuclear power generating stations  

Energy Technology Data Exchange (ETDEWEB)

Electrical power is generated by steam turbines (steam being produced by coal, oil, gas or nuclear reactors), hydro units, gas turbines, internal combustion engines, jet engines, and pumped storage plants. Nuclear Power Plants generate only 15% of the total electrical power in the US. Nuclear Power Plants being cheaper to run are generally base loaded. The pumped-storage and gas turbine plants have ideal characteristics for peaking duty. In the pumping mode, pumped storage plants are used to provide additional system load and in the generating mode, they supply reactive power during peak load demands. Gas turbine plants have higher running costs, but are used as peaking units with a fast start capability. Fossil power plants need a minimum of 1 hour to stabilize expansion in the boiler and turbine generator. Due to a ...

1997-12-31

44

Learn CPR You Can Do It!  

Science.gov (United States)

Have a question about CPR? Click Here To Ask The Doctor Learn CPR is a free public service supported by the University of Washington School of Medicine . Learn the basics of CPR - cardiopulmonary resuscitation. The American Heart Association issued updated ...

45

Design basis for protection of light water nuclear power plants against effects of postulated pipe rupture  

Energy Technology Data Exchange (ETDEWEB)

This standard addresses the design bases for light water reactor, nuclear power plant structures and components essential for the protection of public health and safety from the potential adverse effects of pipe whip, jet impingement, pressurization of compartments outside containment, environmental conditions and flooding associated with a postulated pipe rupture. The design bases for missile protection and the design bases for containment pressurization are not within this standard.

1981-01-01

46

American National Standard: design basis for protection of light water nuclear power plants against effects of postulated pipe rupture  

Energy Technology Data Exchange (ETDEWEB)

This standard addresses the design bases for light water reactor, nuclear power plant structures and components essential for the protection of public health and safety from the potential adverse effects of pipe whip, jet impingement, pressurization of compartments outside containment, environmental conditions and flooding associated with a postulated pipe rupture. The design bases for missile protection and the design bases for containment pressurization are not within this standard.

1980-12-31

47

Space power systems prelaunch integration  

International Nuclear Information System (INIS)

The sequence of events from the assembly of a space nuclear power system to its integration in the Space Shuttle Transportation System (STS) is considered. First, the sequence followed for SNAP-10A, the only free world space reactor electric power system ever launched and operated in space, is reviewed. Before shipment, the SNAP-10A reactor was raised to operating temperature using electrically supplied heat and operated at low power for control calibration. Next we discuss shipment to the launch site, a phase that is critical because of the potential for various accidents. Once the power system arrives at the launch site, the processing sequence is performed. This sequence includes checkout, mating with the payload or upper stage launch vehicle, and integration into the STS.

48

Safety review of conceptual fusion power plants  

Science.gov (United States)

The potential public safety impacts from accidents in conceptual fusion power plants were investigated. Fusion was found to have some potential for accidents, as does any energy generating system. Functions of fusion power plants were identified that possess sufficient potential for an accidental release of toxic materials to the environment. An assessment was made of the impact of the potential accidents and recommendations are included for R and D that will allow incorporation of safety concerns in fusion power plant design. This work was based on a review of information available in conceptual design documents of fusion reactor systems.

1976-11-01

49

Safety review of conceptual fusion power plants  

International Nuclear Information System (INIS)

The potential public safety impacts from accidents in conceptual fusion power plants were investigated. Fusion was found to have some potential for accidents, as does any energy generating system. Functions of fusion power plants were identified that possess sufficient potential for an accidental release of toxic materials to the environment. An assessment was made of the impact of the potential accidents and recommendations are included for R and D that will allow incorporation of safety concerns in fusion power plant design. This work was based on a review of information available in conceptual design documents of fusion reactor systems.

50

HYFIRE: a tokamak- high-temperature electrolysis system  

Energy Technology Data Exchange (ETDEWEB)

Brookhaven National Laboratory is involved in a conceptual design study of a commercial nuclear power system which utilizes high-temperature electrolysis to produce synthetic fuels. The system is called HYFIRE. It includes a tokamak fusion power reactor supplying electrical and thermal energy to an array of electrolytes. The electrolytes produce hydrogen which can be used either directly as a fuel or in the production of hydrocarbons. The purpose of the study is to provide a mechanism for DOE to further assess the commercial potential of fusion using a tokamak reactor to produce synthetic fuel. The HYFIRE design is based on the tokamak commercial power reactor, STARFIRE. STARFIRE uses the deuterium/tritium/lithium fuel cycle. The HYFIRE study assumes the plasma shape and characteristics of STARFIRE study but uses a different blanket design. ...

1980-01-01

51

Roof slab cooling device in a FBR type reactor  

International Nuclear Information System (INIS)

Purpose: To obtain a roof slab cooling device capable of retaining cooling performance even in a case of electric power supply stop or failure and effective from economical point of view. Constitution: Atmospheric air is introduced into the cooling chamber of a proof slab and spontaneously passed to a exit pipeway connected to a stack thereby cooling the roof slab. Specifically, atmospheric air entered from the inlet pipeway is introduced to the cooling chamber and absorbs heat generate from the inside of the reactor container. Warmed air is sucked from the exit pipeway and then released into the atmosphere passing through the stack. The air cools the roof slab during circulation due to spontaneous passage and keeps the slab at a low temperature. Since the air is passed spontaneously, no power such as for a blower is required at all and, if the electric power ...

1986-05-16

52

Conference on reformation of regulation in OECD/IEA power sector - Conference on reformation of regulation in USA, Netherlands, Japan  

Energy Technology Data Exchange (ETDEWEB)

Since 1995, OECD started to examine the current situation of government regulation in each member country and discussed to recommend quality improvement of regulation to member countries. The conference on reformation of regulation in power industry was held in October and December 1998. In USA, enhancing competition in supplying electricity was recommended by eliminating differentiation in use of power network, transmission network and incidental facilities. The retail competition is also an important reformation. The reformation in Netherlands can be seen as following EU guide for revealing problems of the existing regulation in the power industry and for opening up a power market. The Dutch government passed the power act for opening up a market to the public between 1999 and 2007. In Japan, the entry of independent ...

1999-01-01

53

Standardization/improvement and technical development of light water reactor power station in Japan(BWR)  

Energy Technology Data Exchange (ETDEWEB)

In order to realize improve of reliability and economy by duplicate production, rapid supply of repair parts from standardized storage, such were expected as to have continuous order of standardized plant, to ignore site condition, to avoid expansion of regulatory requirement. Standardization program was planned to limitedly promote standardization of safety-related design concept, major specification and basic system composition of reactor and primary systems. The area of standardization had been tried to expand to BOP such as general arrangement and rad-waste system.

1985-07-01

54

Isotope Production at the Hanford Site in Richland, Washington  

Energy Technology Data Exchange (ETDEWEB)

This report was prepared in response to a request from the Nuclear Energy Research Advisory Committee (NERAC) subcommittee on ''Long-Term Isotope Research and Production Plans.'' The NERAC subcommittee has asked for a reply to a number of questions regarding (1) ''How well does the Department of Energy (DOE) infrastructure sme the need for commercial and medical isotopes?'' and (2) ''What should be the long-term role of the federal government in providing commercial and medical isotopes?' Our report addresses the questions raised by the NERAC subcommittee, and especially the 10 issues that were raised under the first of the above questions (see Appendix). These issues are related to the isotope products offered by the DOE Isotope Production Sites, the capabilities and condition of the facilities used to produce these products, the management of the isotope production programs at DOE ...

1999-06-01

55

A study on the management of spent fuel storage capacity in South Korea  

International Nuclear Information System (INIS)

The saturation of South Korea's at-reactor (AR) spent fuel storage pools will create a necessity for additional spent fuel storage capacity. Because the South Korean government has the plan to increase the number of nuclear power plants from 20 units (end of 2005) to 27 units by 2015, the increase of spent nuclear fuel generation will be accelerated. Because there is no clear national plan for spent nuclear fuel storage and disposal, the utility company (Korea Hydraulic Nuclear Power company) is planning to construct a spent fuel storage facility with 11 000 tHM capacity for Pressurised Water Reactor (PWR). This study is intended to predict the maximum allowable periods when the storage facility will be fully occupied with respect to the already fixed re-racking plan of spent fuel storage pools and construction of new nuclear power plants. The result from this study will be used as ...

2006-06-19

56

Probability of failure in BWR reactor coolant piping: Guillotine break indirectly induced by earthquakes  

Energy Technology Data Exchange (ETDEWEB)

The requirements to design nuclear power plants for the effects of an instantaneous double-ended guillotine break (DEGB) of the reactor coolant piping have led to excessive design costs, interference with normal plant operation and maintenance, and unnecessary radiation exposure of plant maintenance personnel. This report describes an aspect of the NRC/Lawrence Livermore National laboratory-sponsored research program aimed at investigating whether the probability of DEGB in Reactor Coolant Loop Piping of nuclear power plants is acceptably small such that the requirements to design for the DEGB effects (e.g., provision of pipe whip restraints) may be removed. This study estimates the probability of indirect DEGB in Reactor Coolant piping as a consequence of seismic-induced structural failures within the containment of the GE supplied boiling water ...

1986-12-01

57

Energy threat to valuable land  

Energy Technology Data Exchange (ETDEWEB)

A negative public reaction is expected to oppose plans of the British energy industry to take valuable sites for industrial and commercial projects on the ground that government demand forecasts are too high and that they downplay conservation. The United Kingdom (UK) Department of Energy points out that public inquiry always accompanies energy installations and defends the projections made by producers even though each study emphasizes the demand for its own form of energy. At issue are plans to open 150 opencast coal mines a year to compensate for diminishing oil and gas supplies, onshore drilling by oil and gas exploration teams on nearly 50,000 km/sup 2/, and sites required for onshore pipelines, synthetic natural gas facilities, pumped storage plants, and nuclear power stations and waste management. The sites under discussion raise aesthetic and ecological concerns. (DCK)

1982-03-11

58

Development of High Field Dipole and High Current Pulse Power Supply for Compact Proton Synchrotron  

CERN Document Server

Development of High Field Dipole and High Current Pulse Power Supply for Compact Proton Synchrotron

2003-01-01

59

Proceedings of national conference on operating experience of nuclear reactors and power plants: book of preprints  

International Nuclear Information System (INIS)

The symposium covers papers under different sections namely, (i) Core physics and Fuel management, (ii) Commissioning of facilities and systems, (iii) Operational experience and Human resource development, (iv) Fuel handling, Maintenance management and Surveillance, (v) Instrumentation and Control and Power supply systems, (vi) Analysis, modifications and developments for enhancing operational safety, (vii) Chemistry control and Effluent management, (viii) Radiation and industrial safety and (ix) Steam generators, Turbo-generators and other auxiliaries. Papers relevant to INIS are indexed separately. (author)

2006-11-13

60

RECENT ACTIVITIES AT THE CENTER FOR SPACE NUCLEAR RESEARCH FOR DEVELOPING NUCLEAR THERMAL ROCKETS  

Energy Technology Data Exchange (ETDEWEB)

Nuclear power has been considered for space applications since the 1960s. Between 1955 and 1972 the US built and tested over twenty nuclear reactors/ rocket-engines in the Rover/NERVA programs. However, changes in environmental laws may make the redevelopment of the nuclear rocket more difficult. Recent advances in fuel fabrication and testing options indicate that a nuclear rocket with a fuel form significantly different from NERVA may be needed to ensure public support. The Center for Space Nuclear Research (CSNR) is pursuing development of tungsten based fuels for use in a NTR, for a surface power reactor, and to encapsulate radioisotope power sources. The CSNR Summer Fellows program has investigated the feasibility of several missions enabled by the NTR. The potential mission benefits of a nuclear rocket, historical achievements of the previous programs, and ...

2001-09-01

61

Status of non-electric nuclear heat applications: Technology and safety  

International Nuclear Information System (INIS)

Nuclear energy plays an important role in electricity generation, producing 16% of the world's electricity at the beginning of 1999. It has proven to be safe, reliable, economical and has only a minimal impact on the environment. Most of the world's energy consumption, however, is in the form of heat. The market potential for nuclear heat was recognized early. Some of the first reactors were used for heat supply, e.g. Calder Hall (United Kingdom), Obninsk (Russian Federation), and Agesta (Sweden). Now, over 60 reactors are supplying heat for district heating, industrial processes and seawater desalination. But the nuclear option could be better deployed if it would provide a larger share of the heat market. In particular, seawater desalination using nuclear heat is of increasing interest to some IAEA Member States. In consideration of the growing experience being accumulated, the IAEA periodically ...

62

The state of public power  

Energy Technology Data Exchange (ETDEWEB)

Opinions on factors affecting public power systems are presented. Social, economic, and political factors are discussed in terms of their impact on public power. Competition with investor-owned utilities is the primary focus of the paper. Privatization and regulations are other issues discussed.

1995-12-31

63

Chalon/Saint-Marcel manufacturing plant; L'usine de Chalon/Saint-Marcel  

Energy Technology Data Exchange (ETDEWEB)

AREVA is the world leader in the design and construction of nuclear power plants, the manufacture of heavy components, and the supply of nuclear fuel and nuclear services such as maintenance and inspection. The Equipment Division provides the widest range of nuclear components and equipment, manufactured at its two facilities in Jeumont, northern France, and St. Marcel, in Burgundy. The St. Marcel plant, set on 35 ha (87.5 acres) near Chalon-sur-Saone, was established in 1973 in a region with a long history of specialized metalworking and mechanical activities to meet the demand for non-military nuclear requirements in France. The site offers two advantages: - excellent facilities for loading and transporting heavy components on the Saone river, - it's proximity to other group sites. Since its completion in 1975, the Chalon/St. Marcel facility has manufactured all the heavy components for French pressurized water ...

2008-07-01

64

Bonneville Power Administration, Office of Engineering 10-Year Plan, 1992-2001 : Draft.  

Energy Technology Data Exchange (ETDEWEB)

For over 50 years, the Bonneville Power Administration (BPA) has evolved to supply electric power to more than 170 customer utilities and direct service industries across 14,800 miles of high voltage transmission lines. BPA's Office of Engineering provides the planning, development, and engineering for the required expansion, upgrade, and replacement of the transmission system. The purpose of this 10-Year Plan is to present strategies to maintain a reliable energy delivery system within changing public, business, technological, and environmental climates. The issues and trends discussed in this document and our strategies for addressing them provide the background for the Office of Engineering programs and projects. With a budget in the hundreds of millions annually and increasing public concern, we welcome the opportunity to communicate with our customers. In addition to ...

1992-05-01

65

Bonneville Power Administration, Office of Engineering 10-Year Plan, 1992-2001 : Draft.  

Energy Technology Data Exchange (ETDEWEB)

For over 50 years, the Bonneville Power Administration (BPA) has evolved to supply electric power to more than 170 customer utilities and direct service industries across 14,800 miles of high voltage transmission lines. BPA`s Office of Engineering provides the planning, development, and engineering for the required expansion, upgrade, and replacement of the transmission system. The purpose of this 10-Year Plan is to present strategies to maintain a reliable energy delivery system within changing public, business, technological, and environmental climates. The issues and trends discussed in this document and our strategies for addressing them provide the background for the Office of Engineering programs and projects. With a budget in the hundreds of millions annually and increasing public concern, we welcome the opportunity to communicate with our customers. In addition to the ...

1992-05-01

66

IGC'97: highlights  

International Nuclear Information System (INIS)

The IGC Highlights briefly outlines some of the the significant progresses made by Indira Gandhi Centre for Atomic Research, Kalpakkam during the period 1996-1997. The Fast Breeder Test Reactor (FBTR) was operated at the maximum power level possible with the available partial core. The first generation of electricity from FBTR and its synchronization with the grid in 1997 marked a significant step in the nuclear programme of the Centre. Another important event was the commissioning of the "2"3"3U - fuelled Kamini reactor.The mission-oriented programmes in fast reactor technology was supported by a host of research and development programmes, in closely related areas namely materials technology, welding metallurgy, sodium technology, manufacturing technology, non-destructive testing, quality engineering, in-service inspection, electronics and instrumentation and safety research. The Highlights also ...

69

47 CFR 80.917 - Reserve power supply.  

Science.gov (United States)

...2010-10-01 false Reserve power supply. 80.917 Section 80.917 Telecommunication...Passenger Boats § 80.917 Reserve power supply. (a) The requirements of this section...March 1, 1957, must have a reserve power supply located on the same deck as the...

2010-10-01

70

Klickitat Cogeneration Project : Final Environmental Assessment.  

Energy Technology Data Exchange (ETDEWEB)

To meet BPA`s contractual obligation to supply electrical power to its customers, BPA proposes to acquire power generated by Klickitat Cogeneration Project. BPA has prepared an environmental assessment evaluating the proposed project. Based on the EA analysis, BPA`s 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 of 1969 for the following reasons: (1)it will not have a significant impact land use, upland vegetation, wetlands, water quality, geology, soils, public health and safety, visual quality, historical and cultural resources, recreation and socioeconomics, and (2) impacts to fisheries, wildlife resources, air quality, and noise will be temporary, minor, or sufficiently offset by mitigation. Therefore, the preparation of an environmental impact statement is not required and BPA is ...

1994-09-01

72

Recent developments: Washington focus  

International Nuclear Information System (INIS)

November was a quiet month in Washington. Although Congress has recessed until 1991, the Senate filled vacancies in party leadership positions created by November's elections. The House is expected to proceed with its changes in early December. The Nuclear Energy Forum was held in Washington, DC on November 11-14 to discuss the status of the nuclear industry in the USA. The Forum, held in conjunction with the American Nuclear Society's annual meeting, assembled a large number of CEO's from US, European, and Far Eastern utilities and vendors. The meeting concluded with an announcement by Philip Bayne, President of NYPA and chairman of the Nuclear Power Oversight Committee (NPOC), of the results of a year-long NPOC study entitled a open-quotes Strategic Plan for Building New Nuclear Power Plants.close quotes.

73

AP1000 plant construction in China: Ansaldo Nucleare contribution  

International Nuclear Information System (INIS)

On 24th of July 2007 Westinghouse Electric Co. signed landmark contracts with China's State Nuclear Power Technology Corporation (SNPTC), to provide four AP1000 nuclear power plants in China. The AP1000 is a two-loop 1117 MWe Pressurized Water Reactor (PWR). It is based on proven technology, but with an emphasis on safety features that rely on natural driving forces, such as pressurized gas, gravity flow, natural circulation flow and convection. Ansaldo Nucleare has provided a significant support to the passive plant technology development and, starting from 2000, is cooperating with Westinghouse to development of the AP1000 Plant. In the frame of the AP1000 Chinese agreement, Ansaldo Nucleare, in Joint Venture with Mangiarotti Nuclear, has signed a contract with Westinghouse for the design and the supply of innovative components to be installed in the first AP1000 unit to be constructed at the Sanmen ...

2009-10-12

74

Behaviour of steam turbine power control of large power plant units in case of network short-circuits  

International Nuclear Information System (INIS)

In order to investigate the behaviour of the turbine control system during strong pendulum motions, an analysis is carried out using a digital computer program by which the reactor, the turbine, the generator and, in a simplified way, the network can be simulated to the necessary degree. Plotter pictures can show the main physical quantities. In all cases, the turbine control system should be able to distinguish between strong pendulum amplitude with acceleration of the rotational angles and sudden release criteria. This demand can be satisfied by a simple adjustment in the Kraftwerk Union turbine control system. Only a few seconds after shut-off of a severe network failure, the turbines are back to their rated power, thus contributing to reliability of supply in this critical network situation. (orig.).

1978-11-24

75

Power spectral density measurements with "2"5"2Cf for a mockup of the FFTF  

International Nuclear Information System (INIS)

... californium 252 fftf reactor mockup power density reactor cores reactor noise

1975-06-08

76

Past and future upgrades of the gyrotron high voltage cathode power supplies at the Forschungszentrum Karlsruhe  

Energy Technology Data Exchange (ETDEWEB)

The high voltage/high power DC-cathode power supply for the Gyrotron Test Facility at the Forschungszentrum in Karlsruhe consists of a 12-pulse thyristor star-point-controller, a 130 kV capacitor-bank followed by a tetrode regulator. Originally designed for 80 kV/30 A CW (continous-wave) operation, its operating regime has been extended in line with gyrotron development to pulses of 65 kV/45 A/3 min and more recently to 65 kV/80 A/10 s without any changes to the main load bearing components (thyristors, transformers or power tetrode). This allows testing of gyrotrons in the 0.5 MW (CW), 1 MW (3 min) and 2 MW (10 s) output power range. The paper describes the system, its operation and some critical aspects of the last upgrade, such as the issue of harmonics in the 20 kV distribution mains-grid, the dynamic response of the thyristor-controller and the avoidance of microwave parasitic ...

2009-06-15

77

Computer control of fuel handling activities at FFTF  

International Nuclear Information System (INIS)

The Fast Flux Test Facility near Richland, Washington, utilizes computer control for reactor refueling and other related core component handling and processing tasks. The computer controlled tasks described in this paper include core component transfers within the reactor vessel, core component transfers into and out of the reactor vessel, remote duct measurements of irradiated core components, remote duct cutting, and finally, transferring irradiated components out of the reactor containment building for off-site shipments or to long term storage. 3 refs., 16 figs.

1985-09-08

78

Biomass energy utilization - potentials, techniques and cost. Energetische Nutzung von Biomasse - Potentiale, Technik, Kosten  

Energy Technology Data Exchange (ETDEWEB)

Renewable energy sources have been attracting the attention of a sensitized public since general pollution abatement measures have been taken, since efforts have been going into the protection of the earth atmosphere, the preservation of the vital ozone layer, and the conservation of fossil energy sources, and since nuclear power risks have been recognized and discussed. In addition to wind power and solar energy solid biomass, e.g. wood, wood wastes, vegetable residues and plants cultivated for the purpose of energy production, is among the topical alternatives. Agriculture and silviculture are important end-users of potential decentralized energy supplies and are cut out for supplying biomass for energy utilization. Additional income sources will open up for farmers. Based on these facts this KTBL working paper describes the biomass energy potential and feasible harvesting and ...

1994-01-01

79

FFTF operational results: startup to 100 MWd/kg  

International Nuclear Information System (INIS)

The Fast Flux Test Facility (FFTF) is a 400-MW(t) sodium-cooled fast reactor operating at the Hanford Engineering Development Laboratory in Richland, Washington, to conduct fuels and materials testing in support of the US liquid-metal fast breeder reactor program. Startup and initial power testing included a comprehensive series of nuclear and nonnuclear tests to verify the thermal and neutronic characteristics of the plant and to demonstrate its inherent safety features. Extensive reactor core characterization measurements were completed to provide the neutron and gamma spectra, fission rates, and other physics data needed to design and evaluate tests irradiated in the FFTF. A specially designed series of natural-circulation tests was performed to demonstrate the inherent safety features of the plant. Early in 1982 the FFTF began its first 100-d irradiation cycle. Since that time ...

80

Safety evaluation report related to the operation of Grand Gulf Nuclear Station, Units 1 and 2. Dockets Nos. 50-416 and 50-417, Mississippi Power and Light Company; Middle South Energy, Inc. , South Mississippi Electric Power Association  

Energy Technology Data Exchange (ETDEWEB)

Supplement 2 to the Safety Evaluation Report for Mississippi Power and Light Company, et. al, joint application for licenses to operate the Grand Gulf Nuclear Station, Units 1 and 2, located on the east bank of the Mississippi River near Port Gibson, in Claiborne County, Mississippi, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report.

1982-06-01

81

The development of fast breeder reactors  

International Nuclear Information System (INIS)

Modern civilisation is based on substantial utilisation of energy. Rapid industrial development and improvement of living standards in India require energy planners to adequately forecast the energy demand and take appropriate measures in advance. However, the development and establishment of new technology is a slow process, sometimes extending over decades. Hence, energy options based on new technologies need to be planned for much in advance making allowance for uncertainties and delays. Fast Breeder Reactor (FBR) technology is an advanced energy option promising abundant and economic supply of power. Research and development work on FBRs has been conducted at the Indira Gandhi Centre of Atomic Research (IGC) since 1971. The international trends in FBR development are highlighted in this discussion and an overview of some of the research activities at IGC is presented. (author). 8 refs., 7 tab s.

82

Fuel cycle options and sustainability for new nuclear build in the UK  

International Nuclear Information System (INIS)

After a long period of stagnation in the UK, Europe and the USA, there is now a real expectation that new nuclear plants will be under construction shortly. Several factors have contributed to this change of position in the UK: the growing realisation that effective action is needed to offset greenhouse gas emissions; higher prices for fossil fuels; increasing reliance on overseas supplies of oil and gas; the limitations of wind and wave power and distribution; security of supply; the gradual realisation in the deregulated electricity generation market that nuclear power is competitive and the pending closure of most of the UK's nuclear fleet within less than 15 years. All these factors have led to a reversal of the UK Government's attitude to nuclear power, which has now ruled in favour of allowing a new generation of nuclear plants being built. This paper summarises some of the ...

2008-09-14

83

The safety concept of public gas supply in Germany  

Energy Technology Data Exchange (ETDEWEB)

The risk perception of the public consists of two components: the objectively factual component and the subjectively irrational component. The two strategies adopted by the German gas supply industry are the internal and the external communication strategy. Concepts and measures of accident precaution, registration and analysis of accident data (installation and operating errors, defects on flue systems, pipelines and valves, subsequent installation of gas appliances) are discussed. (R.P.)

1997-09-01

84

Device for controlling water supply to nuclear reactor  

International Nuclear Information System (INIS)

Object: To smoothly control automatic water supply for realizing stable operation of a nuclear reactor by providing a flow rate limiting signal selection circuit and a preferential circuit in a water supply control device for a nuclear reactor wherein the speed of a recirculation pump may be changed in two-steps. Structure: Opening angle signals for a water supply regulating valve are controlled by a nuclear reactor water level signal, a vapor flow rate signal and a supplied water flow rate signal through an adder and an adjuster in response to a predetermined water level setting signal. When the water in the reactor is maintained at a predetermined level, a selection circuit receives a water pump condition signal for selecting one of the signals from a supplied water rate limiting signal generator ...

85

The development of the high-temperature reactor. In memoriam Prof. Dr. rer.nat. Dr.-Ing. e.h. Rudolf Schulten  

International Nuclear Information System (INIS)

In the future even more than in the past, nuclear power will be indispensable in the present industrialized countries and in those still under development. The safe, nonpolluting, and economic supply of energy to mankind in the future includes so many different problems that the technology of the high-temperature reactor at its present level of development, and with the possibilities is offers above and beyond those provided by other, established, technologies, does not have to mark the end of some old line of development, but rather should be seen as the starting point of a development offering promise for the future. It is for this very reason that the extensive, valuable knowledge and experience accumulated in the construction, operation, and decommissioning of the AVR and THTR plants, the development of the HTR module and other variants and, last, but not least, the valuable results of projects such as PNP, NFE, and ...

86

United States Department of Energy breeder reactor staff training domestic program  

Energy Technology Data Exchange (ETDEWEB)

Two US DOE projects in the Pacific Northwest offer unique on-the-scene training opportunities at sodium-cooled fast-reactor plants: the Fast Flux Test Facility (FFTF) near Richland, Washington, which has operated successfully in a wide range of irradiation test programs since 1980; and the Experimental Breeder Reactor II (EBR-II) near Idaho Falls, Idaho, which has been in operation for approximately 20 years. Training programs have been especially designed to take advantage of this plant experience. Available courses are described.

1984-01-01

87

An integrated nuclear electro-thermal engine concept for geostationary missions  

International Nuclear Information System (INIS)

A preliminary design for a nuclear electric 'Space Tug' is proposed for use in conjunction with the American Space Shuttle for high energy missions. The vehicle would employ a SNAP 10A/2 or SNAP 8 nuclear reactor derivative for its power supply and slush hydrogen as the working fluid for the electrothermal thrusters. A thermodynamic conversion cycle would be employed for electrical power generation, for which the hydrogen working fluid would perform the duty of the heat sink. The cycle would eliminate the need for heavy waste radiators and improve the overall thermal efficiency. The vehicle promises a considerable payload advantage over a chemical recoverable Tug for geostationary missions. (orig.).

1974-10-14

88

Providing online access to historic films at the Washington State University libraries  

British Library Electronic Table of Contents (United Kingdom)

Purpose - This paper aims to discuss the procedures and methods developed at Washington State University to digitize and make accessible historic moving images. Design/methodology/approach - The paper describes the selection and the use of low-cost technologies to transfer analog film to digital formats. Issues related to the conversion, description, and online hosting of digital films are also addressed. Findings - Though the steps involved in digitizing film are not trivial, the benefits of access both for the public and archives staff outweigh the expense and labor involved. The procedures described in this paper involve low upfront costs and are sustained through cost recovery fees. Research limitations/implications - The focus of this paper is on managing, describing, and providing on...

2011-01-01

89

Operational safety experience and passive safety testing at the FFTF  

International Nuclear Information System (INIS)

The FFTF is a 400-MWt sodium-cooled fast neutron flux test reactor located on the US government-owned Hanford Site in southeastern Washington state. The reactor is operated for the US Department of Energy by the Westinghouse Hanford Company. Since FFTF started routine operation in 1982, the commercially fabricated driver fuel has performed flawlessly to well beyond the design goal peak burnup of 80 MWd/kgM. The core average discharge exposure is now some 60% beyond the original design expectations and attests to the ruggedness and reliability of the mixed oxide fuel system. In Cycle 9 sixteen long-life assemblies were installed to begin the irradiation of mixed oxides in the advanced low-swelling alloy HT-9 as the Core Demonstration Experiment (CDE). Operation of the plant from initial startup testing to ten cycles of operation has confirmed that the nuclear characteristics are well within the design predictions, and all ...

1987-10-21

90

Time/motion observations of reactor loading, transportation, and dry unloading of an oversized truck spent-fuel shipment  

International Nuclear Information System (INIS)

This paper presents actual time/motion data for an oversize truck spent-fuel shipment from its origin, Surry, Virginia to its destination, Idaho National Engineering Laboratory (INEL). These data include the receipt of the empty cask at the reactor, wet-loading the cask, over-the-road or in-transit data, and receipt and dry unloading of the shipping cask at the receiving facility. Occupational doses were recorded at the Surry Power Plant as well as at INEL, and public doses were calculated for the in-transit dose analysis. This shipment was one of a series performed in support of a demonstration and evaluation of dry storage at INEL. The oversized shipment consisted of a TN-8L shipping cask loaded with three 10-yr-old pressurized water reactor assemblies. The total distance traveled was #approx#2800 miles, requiring 62 h including stops. The time required to receive and inspect the empty shipping cask ...

1988-11-04

91

Safety gas management system utilizing telephone cable  

Energy Technology Data Exchange (ETDEWEB)

This paper describes the safety gas management system utilizing public telephone cables. Buyo Gas Co., Ltd. has installed about 100 governors for exclusive-use or use in the districts to control the gas supply to the consumers. A gas safety management system has been developed. This system consists of a pressure sensor, the terminals of gas leak alarms, and their masters. The features lie in that the system can utilize public cables, is operative at interruption of power service, can correspond to emergency situations, serves to save the cost, and can display the data constantly. For electric facilities in a governor room and the NTT cable service work, sufficient agreement with the possessor is required. In the case of non-utility electric facilities, some restrictions are imposed on the cable work for laying from privately-owned transformers, etc. Insurance for the facilities is necessary to prepare ...

1988-02-10

92

Evaluation of containment P/T relating feedwater flow rate analysis following main steam line break accident for nuclear power plant  

Energy Technology Data Exchange (ETDEWEB)

The Feedwater System supplies feedwater to the steam generator at the required pressure, temperature and flow rate during the plant start-up, normal power operation, shutdown. When the Feedwater System is inoperable or unavailable, the Auxiliary Feedwater System supplies emergency feedwater to the steam generator. If main steam line break occurs, the increase of feedwater flow rate of the faulted steam generator due to decrease of the pressure in the faulted steam generator results in adverse effects in aspect of overcooling the Reactor Coolant System and increased containment pressure/temperature. To optimize the containment mass/energy analysis, this paper evaluates the maximum feedwater and auxiliary feedwater flow rate delivered to the faulted steam generator at each stage of pressure decrease in the faulted steam generator after a main steam line break accident. Calculated Feedwater flows are ...

2001-05-01

93

The development of PHWR fuel fabrication in Korea  

International Nuclear Information System (INIS)

Korea Advanced Energy Research Institute (KAERI) started a research project to develop the PHWR (CANDU) nuclear fuel fabrication technology in 1981. Based on the results of the intensive developmental work, several prototype fuel bundles were fabricated and tested in the Hot Test Loop at KAERI continuously in 1983 and 1984. After that, irradiation test and post-irrradiation examination were carried out for two KAERI-made fuel bundles at Chalk River Nuclear Laboratories in Canada in 1984. Since the results of in-pile and out-of-pile tests with prototype fuel bundles proved to be satisfactory, 48 additional fuel bundles were loaded in Wolsung reactor (CANDU) in 1984 and 1985, and all of them were discharged without a defect after excellent performance in the power reactor. In 1985, the Korean government decided that KAERI supplies all the fuel necessary for the Wolsung reactor. For ...

1987-09-07

94

Procedure for operating reactors  

International Nuclear Information System (INIS)

The invention concerns a procedure for operating reactors in nuclear power plants. It aims at utilizing power reserves in nuclear power plants. This can be achieved by a steam-side connection of the steam generators of two reactors. The amount of steam exchanged between the units is chosen in such a way that power changes at the steam turbines feedback mainly to the corresponding reactor. In order to realize a high power transfer it is necessary to return the amount of condensate produced in the steam receiving unit and corresponding to the power transferred to the feedwater system of the steam donating unit.

1985-11-11

95

Advanced applications of water cooled nuclear power plants  

International Nuclear Information System (INIS)

By August 2007, there were 438 nuclear power plants (NPPs) in operation worldwide, with a total capacity of 371.7 GW(e). Further, 31 units, totaling 24.1 GW(e), were under construction. During 2006 nuclear power produced 2659.7 billion kWh of electricity, which was 15.2% of the world's total. The vast majority of these plants use water-cooled reactors. Based on information provided by its Member States, the IAEA projects that nuclear power will grow significantly, producing between 2760 and 2810 billion kWh annually by 2010, between 3120 and 3840 billion kWh annually by 2020, and between 3325 and 5040 billion kWh annually by 2030. There are several reasons for these rising expectations for nuclear power: - Nuclear power's lengthening experience and good performance: The industry now has more than 12 000 reactor years of experience, and the ...

2007-07-01

96

Advanced applications of water cooled nuclear power plants  

International Nuclear Information System (INIS)

By August 2007, there were 438 nuclear power plants (NPPs) in operation worldwide, with a total capacity of 371.7 GW(e). Further, 31 units, totaling 24.1 GW(e), were under construction. During 2006 nuclear power produced 2659.7 billion kWh of electricity, which was 15.2% of the world's total. The vast majority of these plants use water-cooled reactors. Based on information provided by its Member States, the IAEA projects that nuclear power will grow significantly, producing between 2760 and 2810 billion kWh annually by 2010, between 3120 and 3840 billion kWh annually by 2020, and between 3325 and 5040 billion kWh annually by 2030. There are several reasons for these rising expectations for nuclear power: - Nuclear power's lengthening experience and good performance: The industry now has more than 12 000 reactor years of experience, and the ...

1996-07-21

97

Advanced applications of water cooled nuclear power plants  

International Nuclear Information System (INIS)

By August 2007, there were 438 nuclear power plants (NPPs) in operation worldwide, with a total capacity of 371.7 GW(e). Further, 31 units, totaling 24.1 GW(e), were under construction. During 2006 nuclear power produced 2659.7 billion kWh of electricity, which was 15.2% of the world's total. The vast majority of these plants use water-cooled reactors. Based on information provided by its Member States, the IAEA projects that nuclear power will grow significantly, producing between 2760 and 2810 billion kWh annually by 2010, between 3120 and 3840 billion kWh annually by 2020, and between 3325 and 5040 billion kWh annually by 2030. There are several reasons for these rising expectations for nuclear power: - Nuclear power's lengthening experience and good performance: The industry now has more than 12 000 reactor years of experience, and the ...

2007-11-23

98

Navy Nuclear-Powered Surface Ships: Background, Issues ...  

Science.gov (United States)

... and support cost, and post-retirement disposal cost) of ... from reactors, and the reactors and other ... the ship's hull and reactor compartment enough to ...

2010-06-10

99

Loss of flow incident - Simulation and measurements in the MPR  

International Nuclear Information System (INIS)

As part of the Probabilistic Safety Analysis of the Multi Purpose Reactor, MPR, the list of Postulated Initiating Events was analyzed and one of these PIEs corresponds to the Loss of Coolant Flow. It is well known that during the operation life of a research reactor a LOFA could eventually occur and, once this event takes place, in time detection and automatic actions, thanks to the engineering safety features of the system, will mitigate the incident evolution. The postulated event corresponds to a loss of flow due to a total loss of power supply. The goal of the present work is to provide a general description and the engineering safety features of the MPR, as well as describe the sequence of scenarios during a LOFA. Temporal evolution of main parameters is presented, also. During Stage A of the Commissioning Program measurements of the core cooling system pump coast-down were performed in order to ...

1999-10-26

100

Development of PHWR fuel fabrication in Korea  

Energy Technology Data Exchange (ETDEWEB)

Korea Advanced Energy Research Institute (KAERI) started a research project to develop the PHWR (CANDU) nuclear fuel fabrication technology in 1981. Based on the results of the intensive developmental work, several prototype fuel bundles were fabricated and tested in the Hot Test Loop at KAERI continuously in 1983 and 1984. After that, irradiation test and post-irradiation examination were carried out for two KAERI-made fuel bundles at Chalk River Nuclear Laboratories in Canada in 1984. Since the results of in-pile and out-of-pile tests with prototype fuel bundles proved to be satisfactory, 48 additional fuel bundles were loaded in Wolsung reactor (CANDU) in 1984 and 1985, and all of them were discharged without a defect after excellent performance in the power reactor. In 1985, the Korean government decided that KAERI supplies all the fuel necessary for the Wolsung reactor. For the ...

1988-01-01

103

Full autonomous monitoring tools inside nuclear reactor building  

Energy Technology Data Exchange (ETDEWEB)

In this paper, we define, design and test a radiation tolerant autonomous monitoring tool for nuclear embedded applications. The goal of the instrumentation system was to record the values of some parameters such as dose, temperature or vibrations appearing inside the containment building of nuclear power plants. The knowledge of these parameters will be a good help for predictive maintenance of the power plant components. For the design of the monitoring tool, we rely on commercial-off-the-shelf (COTS) low power electronic components to use battery-supplied power. A large amount of components starting from discrete transistors or logic units to memories and micro-controllers was associated to define and design a prototype. We then confirm the environment conditions tolerance estimated to up to 2 kGy of total dose and 80 C for temperature by on-line irradiation experiments for ...

2009-07-01

104

A model for calculation of RCS pressure during reflux boiling under reduced inventory conditions and its assessment against PKL data  

International Nuclear Information System (INIS)

Based on the occurrence of a number of plant incidents during low power and shutdown operating conditions, the Nuclear Regulatory Commission (NRC) has initiated several programs to better quantify risk during these periods. One specific issue of interest is the loss of residual heat removal (RHR) under reduced coolant inventory conditions. This issue is also of interest in the Federal Republic of Germany and an experiment was performed in the integral PKL-3 experimental facility at Siemens-KWU to supply applicable data. Recently, an effort has been undertaken at the Idaho National Engineering Laboratory (INEL) to identify and analyze the important thermal-hydraulic phenomena in pressurized water reactors following loss of vital AC power and consequent loss of the RHR system during reduced inventory operation. The thermal-hydraulic response of a nuclear steam supply system (NSSS) ...

1991-10-01

105

Nuclear Power Reactors in the World. 2009 Ed  

International Nuclear Information System (INIS)

This is the twenty-ninth edition of Reference Data Series No. 2, Nuclear Power Reactors in the World, which is published once per year, and presents the most recent reactor data available to the IAEA. It contains the following summarized information: - General information as of the end of 2008 on power reactors operating or under construction, and shut down; - Performance data on reactors operating in the Agency's Member States, as reported to the IAEA. The IAEA's Power Reactor Information System (PRIS) is a comprehensive data source on nuclear power reactors in the world. It includes specification and performance history data of operating reactors as well as reactors under construction or reactors being ...

106

Summary of comments received from workshops on radiological criteria for decommissioning  

Energy Technology Data Exchange (ETDEWEB)

The Nuclear Regulatory Commission (NRC) is conducting an enhanced participatory rulemaking to establish radiological criteria for site cleanup and decommissioning of NRC-licensed facilities. Open public meetings were held during 1993 in Chicago, IL, San Francisco, CA, Boston, MA, Dallas, TX, Philadelphia, PA, Atlanta, GA, and Washington, DC. Interested parties were invited to provide input on the rulemaking issues before the NRC staff develops a draft proposed rule. This report summarizes 3,635 comments categorized from transcripts of the seven workshops and 1,677 comments from 100 NRC docketed letters from individuals and organizations. No analysis or response to the comments is included. The comments reflect a broad spectrum of viewpoints on the issues related to radiological criteria for site cleanup and decommissioning. The NRC also held public meetings on the scope of the Generic Environmental Impact Statement (GEIS) ...

1994-01-01

107

Instrumentation and Controls Division progress report, September 1, 1980-July 1, 1982  

Energy Technology Data Exchange (ETDEWEB)

Activities are reported by the Reactor Systems Section, Research Instrument Section, and the Measurement and Controls Engineering Section. Reactor system activities include dynamic analysis, survillanc and diagnostic methods, design and evaluation, detectors, facilities support, process instrumentation development, and special assignments. Activities in the Research Instrument Section include the Navy-ORNL RADIAC development program, advanced ..gamma.. and x ray detector systems, neutron detection and subcriticality measurements, circuit development, position-sensitive detectors, stand-alone computers, environmental monitoring-detectors and systems, plant security, engineering support for fusion energy division, engineering support for accelerator physics, and communications: radio, closed-circuit tv, and computer. Activities in the Measurement and Controls Engineering Section include the AVLIS program; gas centrifuge enrichment technology ...

1982-12-01

108

Fusion power and the environment  

Science.gov (United States)

Environmental characteristics of conceptual fusion-reactor systems based on magnetic confinement are examined quantitatively, and some comparisons with fission systems are made. Fusion, like all other energy sources, will not be completely free of environmental liabilities, but the most obvious of these-- tritium leakage and activation of structural materials by neutron bombardment-- are susceptible to significant reduction by ingenuity in choice of materials and design. Large fusion reactors can probably be designed so that worst-case releases of radioactivity owing to accident or sabotage would produce no prompt fatalities in the public. A world energy economy relying heavily on fusion could make heavy demands on scarce nonfuel materials, a topic deserving further attention. Fusion's potential environmental advantages are not entirely ''automatic'', ...

1975-06-01

109

The world's hydro resources  

Energy Technology Data Exchange (ETDEWEB)

Our latest survey of hydro resources demonstrates the significant role that hydroelectric power continues to play in world energy supply. Our statistics have been revised, updated and expanded this year (1992) on the basis of a detailed questionnaire sent to power authorities around the world. For cases where data could not be obtained in this way we have collaborated with the World Energy Council, the United Nations and OLADE. The four tables this year give data by country and geographical region for the following: 1. Hydropower potential: a detailed breakdown of gross theoretical, technically feasible and economically feasible hydro potential, as well as the dates when the figures were last evaluated. 2. Hydro capacity in operation, under construction and planned (pure hydro only excluding contributions derived from pumped storage). 3. Hydropower ownership: data on public versus independent producers. ...

1992-08-01

110

Carmanah Technologies Corporation 2004 annual report  

International Nuclear Information System (INIS)

British Columbia-based Carmanah Technologies is a world leader in the design, manufacture and supply of patented solar-powered light emitting diode (LED) lighting solutions. As a leading alternative energy manufacturer, it was the first company to integrate LEDs with solar chargers and battery power storage. Carmanah products have high-end assembly, minimal size, maximized performance and field-proven reliability. The products have been used in public transit applications, roadway lighting, and for general aviation lighting solutions. In 2004, their products saved the equivalent of 6,705 metric tonnes of carbon dioxide. This annual report includes information on the company's net earnings and investor profiles. The company has large markets for its products with little competition. It has a strong management team and its funding places it in a position to capitalize on current and emerging technologies. ...

2005-01-01

111

Network Security: Concepts  

Science.gov (United States)

Prepared and presented by Professor Raj Jain at Washington University in St. Louis, this series of presentations is designed to introduce computer science students to the fundamentals of network security. Visitors have the option of choosing to download or view the presentations with audio, as individual slides only, or as a single PDF document. Topics here include: security requirements, public key encryption, digital signatures, and confidentiality. This is an excellent site for educators to use in the classroom or as a supplementary resource to introduce students to computer network security. Students may also wish to view or download the presentations to learn the basic concepts of network security.

2008-01-30

112

Informational Element of Power: The Role of Public Diplomacy ...  

Science.gov (United States)

... 26 Department of National Security and Strategy, Elements of National Power Model or MID-LIFE Model, US Army War College, 2004. 27 Ibid. ...

2005-03-18

113

The concept of power correction techniques and its use in the reactor regulation and protection systems in Indian PHWRs  

International Nuclear Information System (INIS)

Reactor Power Measurement is an essential part of the Reactor Power Control Loop in PHWRs. None of the available power measuring sensor offers characteristics which allow their direct use in the Reactor Power Control Loop. Thermal power, which is considered as relatively accurate, suffers from measurement delays and is used only as reference. Neutronic power sensors like Ion Chambers and Self Powered Neutron Detectors (SPNDs) which sense instantaneous power suffer from inaccuracies. A technique is required which makes use of both types-reference power and instantaneous power to extract real power information from the signals. This paper describes techniques to calibrate (correct) neutronic ...

2010-02-01

114

Long-term storage facility for reactor compartments in Sayda Bay - German support for utilization of nuclear submarines in Russia  

Science.gov (United States)

The German-Russian project that is part of the G8 initiative on Global Partnership Against the Spread of Weapons and Materials of Mass Destruction focuses on the speedy construction of a land-based interim storage facility for nuclear submarine reactor compartments at Sayda Bay near Murmansk. This project includes the required infrastructure facilities for long-term storage of about 150 reactor compartments for a period of about 70 years. The interim storage facility is a precondition for effective activities of decommissioning and dismantlement of almost all nuclear-powered submarines of the Russian Northern Fleet. The project also includes the establishment of a computer-assisted waste monitoring system. In addition, the project involves clearing Sayda Bay of other shipwrecks of the Russian navy. On the German side the project is carried out by the Energiewerke Nord GmbH (EWN) on behalf of the Federal Ministry of ...

2007-07-01

115

Epidemic giardiasis caused by a contaminated public water supply.  

UK PubMed Central (United Kingdom)

In the period November 1, 1985 to January 31, 1986, 703 cases of giardiasis were reported in Pittsfield, Massachusetts (population 50,265). The community obtained its water from two main reservoirs...Full Text Available

1988-02-01

116

Childhood cancer mortality and radon concentration in drinking water in North Carolina.  

UK PubMed Central (United Kingdom)

We explored the association between groundwater radon levels and childhood cancer mortality in North Carolina. Using data from two state-wide surveys of public drinking water supplies, counties were...Full Text Available

1991-04-01

117

Pumped storage in the future power supply system  

Energy Technology Data Exchange (ETDEWEB)

Pumped storage plants (PSP) supply up to several GW of power and several ten GWh of capacity. Short start-up times and low start-up costs predestine PSP for the control energy market. Grid charges for PSP endanger the further integration of renewable energy and lead to higher electricity supply costs. Therefore, an amendment of legislation is urgently required. Requirements for building large PSP are met at numerous sites in the low mountain ranges of Germany. (orig.)

2010-07-01

118

Fuels and materials testing capabilities in Fast Flux Test Facility  

Energy Technology Data Exchange (ETDEWEB)

The Fast Flux Test Facility (FFTF) reactor, which started operating in 1982, is a 400 MWt sodium-cooled fast neutron reactor located in Hanford, Washington State, and operated by Westinghouse Hanford Co. under contract with U.S. Department of Energy. The reactor has a wide variety of functions for irradiation tests and special tests, and its major purpose is the irradiation of fuel and material for liquid metal reactor, nuclear reactor and space reactor projects. The review first describes major technical specifications and current conditions of the FFTF reactor. Then the plan for irradiation testing is outlined focusing on general features, fuel pin/assembly irradiation tests, and absorber irradiation tests. Assemblies for special tests include the material open test assembly (MOTA), fuel open test assembly (FOTA), ...

1989-07-01

119

Fuels and materials testing capabilities in Fast Flux Test Facility  

International Nuclear Information System (INIS)

The Fast Flux Test Facility (FFTF) reactor, which started operating in 1982, is a 400 MWt sodium-cooled fast neutron reactor located in Hanford, Washington State, and operated by Westinghouse Hanford Co. under contract with U.S. Department of Energy. The reactor has a wide variety of functions for irradiation tests and special tests, and its major purpose is the irradiation of fuel and material for liquid metal reactor, nuclear reactor and space reactor projects. The review first describes major technical specifications and current conditions of the FFTF reactor. Then the plan for irradiation testing is outlined focusing on general features, fuel pin/assembly irradiation tests, and absorber irradiation tests. Assemblies for special tests include the material open test assembly (MOTA), fuel open test assembly (FOTA), ...

120

Radiological hazards following a nuclear emergency  

International Nuclear Information System (INIS)

Following the 1986 Chernobyl accident there was an understandable increase in public interest in nuclear accidents and emergency planning for them. It became clear that the broad nature, timing and scale of the radiological hazard presented by such accidents was, however, little understood. This Paper sets out in simple terms the basic features of the radiological hazard to persons in the vicinity of a nuclear power plant should a serious accident occur. The Paper starts by stressing the difference between faults -events that may occur relatively frequently - and accidents -unplanned releases of radioactivity that are by design extremely unlikely events. The Paper examines the significance of different exposure pathways and relates them to the protective measures (countermeasures) that may be taken. These countermeasures include sheltering, evacuation and the consumption of stable iodine tablets. The Paper illustrates the effectiveness of these ...

121

Containment integrated leakage rate test (ILRT) of Indian PHWR  

International Nuclear Information System (INIS)

Integrated Leakage Rate Test (ILRT) of containment system plays a very important role in safety of a Nuclear Power Plant. Containment system constitutes the last physical barrier to release of radioactivity from the core and is called upon to mitigate the consequences of not only accidents within the design basis, but also some of the highly unlikely severe accidents. Hence, leak tightness of containment becomes uttermost priority for the safety of plant personnel and public. The containment and associated ESFs are tested before the first criticality and there after periodically during service. The pre-operational integrated leakage rate is carried out at LOCA based design pressure, at periodic test pressure and at some intermediate pressure points to assess the leakage characteristics. This paper summarizes the various requirements and activities relevant to the ILRT of the Indian Pressurized Heavy Water Reactor (PHWR) ...

2005-12-01

122

BR-100 spent fuel shipping cask development  

Energy Technology Data Exchange (ETDEWEB)

Continued public acceptance of commercial nuclear power is contingent to a large degree on the US Department of Energy (DOE) establishing an integrated waste management system for spent nuclear fuel. As part of the from-reactor transportation segment of this system, the B W Fuel Company (BWFC) is under contract to the DOE to develop a spent-fuel cask that is compatible with both rail and barge modes of transportation. Innovative design approaches were the keys to achieving a cask design that maximizes payload capacity and cask performance. The result is the BR-100, a 100-ton rail/barge cask with a capacity of 21 PWR or 52 BWR ten-year cooled, intact fuel assemblies. 3 figs.

1990-01-01

123

Now try to explain network security  

Science.gov (United States)

Overloaded transmission lines are only part of the problem. The ability of the network to carry power is also limited by the supply of reactive power and by frequency stability. Reactive power problems must be corrected in minutes, frequency stability problems in seconds. There is no way that market forces can handle these problems. Reactive power must be supplied to all long transmission and distribution lines to compensate for the loss of reactive volt-amperes - and resulting voltage drop - in the reactance along the line`s length. 7 figs.

1996-10-01

124

Positive safety features of US nuclear reactors: technical lessons confirmed at Chernobyl. Hearing before the Subcommittee on Energy Research and Production of the Committee on Science and Technology, US House of Representatives, Ninety-Ninth Congress, Second Session, May 14, 1986, No. 138  

Science.gov (United States)

Dr. Rudolf Schulten of West Germany and expert witnesses from national laboratories, utilities, and the nuclear industry testified on reactor safety issues as they relate to the Chernobyl accident and public concern that modern technology has not paid enough attention to public safety. Each of the witnesses contributed safety-related information based on what has been learned from the Soviet incident. Particular focus went to similarities and differences between the Chernobyl and US reactors in safety design and engineering and to the environmental effects of the accident. The N reactor near Richland and a commercial reactor at Fort St. Vrain, Colorado are the only two operating graphite reactors, but neither is a boiling water reactor.

1986-01-01

125

Positive safety features of US nuclear reactors: technical lessons confirmed at Chernobyl. Hearing before the Subcommittee on Energy Research and Production of the Committee on Science and Technology, US House of Representatives, Ninety-Ninth Congress, Second Session, May 14, 1986, No. 138  

International Nuclear Information System (INIS)

Dr. Rudolf Schulten of West Germany and expert witnesses from national laboratories, utilities, and the nuclear industry testified on reactor safety issues as they relate to the Chernobyl accident and public concern that modern technology has not paid enough attention to public safety. Each of the witnesses contributed safety-related information based on what has been learned from the Soviet incident. Particular focus went to similarities and differences between the Chernobyl and US reactors in safety design and engineering and to the environmental effects of the accident. The N reactor near Richland and a commercial reactor at Fort St. Vrain, Colorado are the only two operating graphite reactors, but neither is a boiling water reactor.

126

Hydrogen production for better nuclear utilization  

International Nuclear Information System (INIS)

... no. 2) p. 27-28. economics hydrogen power reactors nonmetals (ELEMENTS

1972-08-22

127

Management of open pit mining operations at Megalopolis, Greece  

Energy Technology Data Exchange (ETDEWEB)

The Greek energy economy in response to the rising energy demand yielded to the pressure to develop new sources, particularly since the early closing of the Aliveri mine was approaching. The well known lignite deposits in the Megalopolis Basin, with approximately 380 MMt of economically recoverable fuel, had remained undeveloped since its low heat value, averaging 4012 kJ (960 kcal/kg), had been considered in all countries of the world to be of too poor quality to be economically usable in thermal power plants. With the onset of energy shortages in Greece, which in the course of the year 1967 led to intermittent interruptions of power, finally induced the Public Power Corp., within a German economic assistance agreement to advertise an idea competition among German consortia. In 1967 various planning consortia submitted their plans for the treatment of the Megalopolis open-pit mine and for the laying ...

1982-04-01

128

Application of GO methodology in reliability analysis of offsite power supply of Daya Bay NPP  

International Nuclear Information System (INIS)

The author applies the GO methodology to reliability analysis of the offsite power supply system of Daya Bay NPP. The direct quantitative calculation formulas of the stable reliability target of the system with shared signals and the dynamic calculation formulas of the state probability for the unit with two states are derived. The method to solve the fault event sets of the system is also presented and all the fault event sets of the outer power supply system and their failure probability are obtained. The resumption reliability of the offsite power supply system after the stability failure of the power net is also calculated. The result shows that the GO methodology is very simple and useful in the stable and dynamic reliability analysis of the repairable system

2003-02-01

129

TAG Oil hunting elephants in New Zealand  

International Nuclear Information System (INIS)

Calgary-based TAG Oil is an exploration company that manages 4.1 million acres of major producing oil and gas fields in New Zealand. The enormous Maui field, with 4 tcf of natural gas in place, has dominated the gas market in New Zealand by meeting nearly 90 per cent of the country's energy demand at costs much lower than world prices. However, the maturing field is in decline and will cease production by 2008. New gas field discoveries will only meet 60 per cent of the country's energy requirements for 5 additional years. Unless new large reserves of gas are discovered, the supply and demand situation will get worse. Lead time to place new production on-stream requires 5 to 10 years, which creates a large supply gap over the next decade. Public resistance to coal-fired power plants, new hydroelectric dams and nuclear power has left the country with no viable alternative to natural ...

2005-10-01

130

The Thai-Canadian nuclear human resources development linkage project  

Energy Technology Data Exchange (ETDEWEB)

The Thai-Canadian Nuclear Human Resources Development Linkage Project (the ''Project'') was initiated in 1994 in order to develop the engineering and scientific expertise needed for Thailand to decide whether and how the country can best benefit from the establishment of a nuclear power program. The Project was designed to upgrade current academics and people in industry, and to develop an adequate supply of new technical personnel for academic, industry, utility, regulatory and other government institutions. The key Project objectives included the establishment of a Chair in Nuclear Engineering at Chulalongkorn University, the upgrading of the current Masters level curriculum, the establishment of undergraduate and doctorate level curricula, development and delivery of an industrial training program for people in industry and government, exchanges of Thai and Canadian academics and industry experts to ...

1998-07-01

131

Far East combined-cycle update  

Energy Technology Data Exchange (ETDEWEB)

Korea Electric Power Corporation (Kepco) of South Korea has awarded Asea Brown Boveri Switzerland, a member of the ABB Group, a contract to supply the main equipment for two gas-fired combined-cycle power stations. News of the contract followed an announcement last year that Kepco will build a series of gas-fired power stations in the early 1990s to supply electricity to new housing and commercial areas being built in the Seoul-Incheon connurbation. (author).

1991-03-01

132

Development of power supplies for compact medical synchrotron  

International Nuclear Information System (INIS)

A compact medical synchrotron is being developed which aims to promote the advanced radiotherapy based on the accelerator. As it is small-sized, a high field dipole magnet of 3 T at 200 kA is used. It is excited by the discharge current of the capacitor bank of which waveform is half sinusoidal. To provide with the flat field of 10 - 20 #mu#s duration for the multi-turn injection an additional power supply is developed. For the quadrupole magnet a 100 kHz switch-mode power supply is adopted as it requires the fine tuning and accurate field tracking to the dipole field. (author)

2005-06-01

133

Evolution of reactivity control mechanisms for nuclear research and power reactors in India  

International Nuclear Information System (INIS)

Division of Remote Handling and Robotics (DRHR) at Bhabha Atomic Research Centre (BARC) has been working on design and development of Reactivity Control Mechanisms for Nuclear Research Reactors (Dhruva, KAMINI and recently Critical Facility of Advanced Heavy Water Reactor (AHWR)) as well as Power Reactors in India (Pressurized Heavy Water Reactors of 220 MWe at Narora and recently India's first 540 MWe PHWR Unit -1 and 2 at Tarapur). This paper gives a brief account of evolution of reactivity control mechanisms for nuclear research and power reactors in India. (author)

2009-10-01

134

INEEL Advanced Radiotherapy Research Program Annual Report 2001  

Energy Technology Data Exchange (ETDEWEB)

This report summarizes the major activities and accomplishments of the Idaho National Engineering and Environmental Laboratory (INEEL) Advanced Radiotherapy Research Program for calendar year 2001. Applications of supportive research and development, as well as technology deployment in the fields of chemistry, radiation physics and dosimetry, and neutron source design and demonstration are described. Contributions in the fields of physics and biophysics include development of advanced patient treatment planning software, feasibility studies of accelerator neutron source technology for Neutron Capture Therapy (NCT), and completion of major modifications to the research reactor at Washington State University to produce an epithermal-neutron beam for NCT research applications.

2002-04-01

135

INEEL Advanced Radiotherapy Research Program Annual Report 2001  

Energy Technology Data Exchange (ETDEWEB)

This report summarizes the major activities and accomplishments of the Idaho National Engineering and Environmental Laboratory (INEEL) Advanced Radiotherapy Research Program for calendar year 2001. Applications of supportive research and development, as well as technology deployment in the fields of chemistry, radiation physics and dosimetry, and neutron source design and demonstration are described. Contributions in the fields of physics and biophysics include development of advanced patient treatment planning software, feasibility studies of accelerator neutron source technology for Neutron Capture Therapy (NCT), and completion of major modifications to the research reactor at Washington State University to produce an epithermal-neutron beam for NCT research applications.

2002-04-30

136

Public power's roots deep in the Northwest  

Energy Technology Data Exchange (ETDEWEB)

Municipal power systems developed early in the Pacific Northwest, but a new dimension was added in the 1930s when the public utility district (PUD) concept combining urban and rural areas encited vigorous debate and the public rejected private-utility candidates. A favorable national climate developed for consumer-owned systems during the 1920s and 30s encouraging the passage of the Federal Water Power Act, the creation of the Tennessee Valley Authority, the building of Hoover Dam, and the establishment of the Bonneville Power Administration. This article reviews developments following the Public Utility Act of 1935, which authorized the Federal Power Commission and the uniform system of accounts. After tracing the record of investigations and policy trends during the Roosevelt era, it concludes that utilities benefited from accounting ...

1982-01-01

137

A College Guide to Disabled Student Services in Washington State.  

Science.gov (United States)

Prepared by volunteers representing a wide range of interests and experience and including students with disabilities, this guide provides basic information about support services available to students with disabilities at public and private postsecondary education institutions in the State of Washington. The guide may also serve as a resource for family members, school counselors and others who assist students in furthering their education. The first section presents general information, discussing students' rights to appropriate education, giving basic rules for managing the transition to college life, charting effects of functional limitations in the academic setting, and providing a planning checklist for new students. Institutional profiles are presented in the second section, covering vocational-technical institutes (5), community colleges (27), and 4-year colleges and universities (16). Information is included on contact person, ...

1986-08-01

138

High voltage to complaints; Hoeyspent til besvaer  

Energy Technology Data Exchange (ETDEWEB)

Power supply to Bergen has created headaches. Many will not have the land-based high-voltage wire. But the alternatives are costly and will delay the line by many years. (AG)

2010-07-01

139

Advanced Instrumentation and Control Methods for Small and Medium Reactors with IRIS Demonstration. Final Report. Volume 1  

International Nuclear Information System (INIS)

Development and deployment of small-scale nuclear power reactors and their maintenance, monitoring, and control are part of the mission under the Small Modular Reactor (SMR) program. The objectives of this NERI-consortium research project are to investigate, develop, and validate advanced methods for sensing, controlling, monitoring, diagnosis, and prognosis of these reactors, and to demonstrate the methods with application to one of the proposed integral pressurized water reactors (IPWR). For this project, the IPWR design by Westinghouse, the International Reactor Secure and Innovative (IRIS), has been used to demonstrate the techniques developed under this project. The research focuses on three topical areas with the following objectives. Objective 1 - Develop and apply simulation capabilities and sensitivity/uncertainty analysis methods to address sensor ...

2009-02-23

140

Transient overpower test E8 on FFTF-type low-power irradiated fuel  

International Nuclear Information System (INIS)

... excursions fftf reactor fuel elements lmfbr type reactors reactivity insertions

1975-06-08

141

Analysis of the MEX-15 multipurpose reactor using SRAC code system  

Energy Technology Data Exchange (ETDEWEB)

The MEX-15 is a conceptual design of a Multipurpose Reactor with thermal power of 15 MW and this reactor is pool type with fuel plates U{sub 3}0{sub 8}-Al of low enrichment uranium. This report presents the static calculation for the MEX-15 reactor using SRAC code system and was developed under the collaboration agreement between ININ-JAERI in Research Reactor Technology Development Division of Department of Research Reactor in Tokai Research Establishment. (Author)

1992-12-15

142

Creating reliable pharmaceutical distribution networks and supply chains in African countries: Implications for access to medicines  

British Library Electronic Table of Contents (United Kingdom)

The presence of inefficient distribution networks and supply chains of medicines creates problems in that even if African countries can secure steep, sustainable cost-containing procurements, access to needed medicines may still be impaired. The expected health benefits from affordable pricing or subsidies on prices of medicines may not be realized. This article evaluates drug supply chains in African countries and advocates for consolidated private wholesale markets and multiplicity of retail pharmacies. Public supply chains should be shortened and supported by contracting out with private distributors, including wholesalers and retail pharmacies. Additionally, drug regulatory authorities should be allowed to charge registration fees that are proportionate to the costs of technical regula...

2009-01-01

143

Annual report 2005-2006  

International Nuclear Information System (INIS)

Research and development and other activities of the various constituent units of Department of Atomic Energy (DAE) and also of the institution aided by DAE for the year 2005-2006 are reported. The various constituents units of DAE consist of nuclear research centres, nuclear power stations, fuel reprocessing and heavy water plants, nuclear fuel fabrication facilities, electronic and instrumentation production organisations, atomic mineral processing units and other nuclear installations. The activities of DAE cover the whole gamut of nuclear fuel cycle, research and development in nuclear science and reactor technology, applications of radiation and radioisotopes, radiation protection, research and development in front line areas such as robotics, lasers, mathematics and computational sciences. International research collaborations like CERN-DAE collaboration were completed by BARC. These activities are described broadly under: executive ...

144

Interaction between supply and end-use  

Energy Technology Data Exchange (ETDEWEB)

In a future power system with a high proportion of distributed and intermittent generation, it will be difficult and costly to ensure short-term security of supply if demand is unable to react to fluctuations on the supply side. At present, most power consumers in the EU, with the exception of the largest consumers such as energy intensive industries, buy their power on fixed tariffs. Fixed tariffs provide no incentives for consumers to alter their patterns of power consumption. This calls for more interaction between the supply and demand sides, which in turn would allow better matching of demand to intermittent supply. The development of cheap and reliable electronic communication technologies has made this a realistic option, so we are left with the general question of how the demand side can become more active in the ...

2005-10-01

145

Electromagnetic fields and public health.  

UK PubMed Central (United Kingdom)

A review of the literature is provided for the topic of health-related research and power frequency electromagnetic fields. Minimal evidence for concern is present on the basis of animal and plant research....Full Text Available

1987-11-01

146

Combining innovative technology demonstrations with dense nonaqueous phase liquids cleanup  

Energy Technology Data Exchange (ETDEWEB)

Radioactively contaminated acidic aqueous wastes and organic liquids were discharged to the soil column at three disposal sites within the 200 West Area of the Hanford Site, Washington. As a result, a portion of the underlying groundwater is contaminated with carbon tetrachloride several orders of magnitude above the maximum contaminant level accepted for a drinking water supply. Treatability testing and cleanup actions have been initiated to remove the contamination from both the unsaturated soils to minimize further groundwater contamination and the groundwater itself. To expedite cleanup, innovative technologies for (1) drilling, (2) site characterization, (3) monitoring, (4) well field development, and (5) contaminant treatment are being demonstrated and subsequently used where possible to improve the rates and cost savings associated with the removal of carbon tetrachloride from the soils and groundwater.

1993-05-01

147

An overview of AECL's participation in the Korean Wolsung Tritium Removal Facility Project (WTRF)  

International Nuclear Information System (INIS)

Full text: In heavy-water-moderated power reactors, tritium is primarily produced by neutron capture in deuterium nuclei in the moderator and coolant. For CANDU 6 reactors, the estimated steady-state values are #approx# 3 TBq#centre dot#kg"-"1 D_2O in the moderator and #approx# 74 GBq#centre dot#kg"-"1 D_2O in the coolant. Tritium removal is one option available to reactor operators for use in their heavy water and tritium management strategies. The WTRF is designed to remove tritium from tritiated heavy water in each of the four CANDU units at the Wolsung Site, to immobilize the tritium and to store it on site. The detritiation process is based on three steps: the first one (front-end) involves the transfer of tritium from heavy water to deuterium gas; the second one (enrichment) concentrates the tritium in a cryogenic distillation system to produce essentially pure D_2 and T_2 streams; and in the ...

2007-11-07

148

Small propulsion reactor design based on particle bed reactor concept  

Science.gov (United States)

In this paper Particle Bed Reactor (PBR) designs are discussed which use /sup 233/U and /sup 242m/Am as fissile materials. A constant total power of 100MW is assumed for all reactors in this study. Three broad aspects of these reactors is discussed. First, possible reactor designs are developed, second physics calculations are outlined and discussed and third mass estimates of the various candidates reactors are made. It is concluded that reactors with a specific mass of 1 kg/MW can be envisioned of /sup 233/U is used and approximately a quarter of this value can be achieved if /sup 242m/Am is used. If this power level is increased by increasing the power density lower specific mass values are achievable. The limit will be determined by uncertainties in the thermal-hydraulic analysis. 5 refs., 5 ...

1989-01-01

149

Commission for Energy regulation (CRE) - Activity report june 2008; Commission de regulation de l'energie (CRE) - Rapport d'activite juin 2008  

Energy Technology Data Exchange (ETDEWEB)

CRE is the French commission for energy regulation. CRE's remit is to assist in ensuring the proper operation of the electricity and natural gas markets for the benefit of the end-user. In particular, CRE ensures that the conditions of access to electricity and natural gas transmission and distribution systems do not hinder the development of competition. It monitors, for the electricity and natural gas sectors, all transactions made between suppliers, traders and producers, all transactions made on the organised markets and cross-border trading. It ensures that suppliers, traders and producers propose offers that are consistent with their financial and technical constraints. It monitors the implementation of and compliance with regulations giving consumers the right to choose their supplier in a competitive market, and allowing new suppliers to enter the market. This document is the 2008 activity report of CRE. Content: A - How CRE works: CRE regulatory authority and ...

2008-07-01

150

hysics Facility - NASA  

Science.gov (United States)

vehicles including the H2-A rocket and the space shuttle. .... The vacuum can's main function is to provide a high vacuum so that the science experiment and its sensors ... EMI-shielded power conversion from the incoming ISS power supply. 4. ...

151

Short-term energy outlook, Quarterly projections. Third quarter 1993  

Energy Technology Data Exchange (ETDEWEB)

The Energy Information Administration (EIA) prepares quarterly, short-term energy supply, demand, and price projections for publication in February, May, August, and November in the Short-Term Energy Outlook (Outlook). An annual supplement analyzes the performance of previous forecasts, compares recent cases with those of other forecasting services, and discusses current topics related to the short-term energy markets. (See Short-Term Energy Outlook Annual Supplement, DOE/EIA-0202.) The forecast period for this issue of the Outlook extends from the third quarter of 1993 through the fourth quarter of 1994. Values for the second quarter of 1993, however, are preliminary EIA estimates (for example, some monthly values for petroleum supply and disposition are derived in part from weekly data reported in the Weekly Petroleum Status Report) or are calculated from model simulations using the latest exogenous information available ...

1993-08-04

152

Experience of HWR nuclear fuel fabrication technology development in Korea  

Energy Technology Data Exchange (ETDEWEB)

Since January, 1981, the project of development of nuclear fuel fabrication technology for Wolsung reactor (CANDU type) was undertaken by KAERI(Korea Advanced Energy Research Institute) and successfully fulfilled with loading 24 fuel bundles made by KAERI in Wolsung reactor in September, 1984. On the basis of this accumulated technology and experience, mass production plan to supply all the nuclear fuels for Wolsung reactor is under way. In this presentation, the Korean experience in the development of the nuclear fuel fabrication technology, safety and performance evaluation of KAERI fuel and the results of irradiation of KAERI fuels in Wolsung reactor will be described.

1985-07-01

153

Experience of HWR nuclear fuel fabrication technology development in Korea  

International Nuclear Information System (INIS)

Since January, 1981, the project of development of nuclear fuel fabrication technology for Wolsung reactor (CANDU type) was undertaken by KAERI(Korea Advanced Energy Research Institute) and successfully fulfilled with loading 24 fuel bundles made by KAERI in Wolsung reactor in September, 1984. On the basis of this accumulated technology and experience, mass production plan to supply all the nuclear fuels for Wolsung reactor is under way. In this presentation, the Korean experience in the development of the nuclear fuel fabrication technology, safety and performance evaluation of KAERI fuel and the results of irradiation of KAERI fuels in Wolsung reactor will be described.

1985-10-29

155

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).

156

Alteration in reactor installation (addition of Unit 2) in the Sendai Nuclear Power Station of Kyushu Electric Power Co., Inc  

International Nuclear Information System (INIS)

The deliveration by the Nuclear Safety Commission was commenced on the alteration in reactor installation, as it had been inquired by the Ministry of International Trade and Industry. The alteration is the additional installation of the reactor No. 2 in the Sendai Nuclear Power Station, Kyushu Electric Power Co., Inc. It is a PWR power plant with thermal output of about 2,660 MW (electric output of 890 MW), to be installed, adjoining to the reactor No. 1 of the same type and capacity under construction. In the examination by MITI, it was confirmed that the technological capabilities for its construction and operation and the radiation protection measures in power generation are both sufficient. The contents of the examination include the siting conditions, the location and construction of reactor facilities, etc. ...

1980-01-01

157

Alteration in reactor installation (addition of Unit 2) in the Sendai Nuclear Power Station of Kyushu Electric Power Co. , Inc  

Energy Technology Data Exchange (ETDEWEB)

The deliberation by the Nuclear Safety Commission was initiated on the alteration in reactor installation, as was required by the Ministry of International Trade and Industry. The alteration is the additional installation of the reactor No. 2 in the Sendai Nuclear Power Station, Kyushu Electric Power Co., Inc. It is a PWR power plant with thermal output of about 2,660 MW (electric output of 890 MW), to be installed, adjoining to the reactor No. 1 of the same type and capacity under construction. In the examination by MITI, it was confirmed that the technological capabilities for its construction and operation and the radiation protection measures in power generation are both sufficient. The contents of the examination include the siting conditions, the location and construction of reactor facilities, etc.

1980-10-01

158

Criticality experiments: analysis, evaluation, and programs. 6. CORAL-I Reactor: Evaluation of Critical Experiments and Mass Reactivity Coefficient Measurement  

International Nuclear Information System (INIS)

CORAL-I was an experimental, zero-power, fast-spectrum, high-enriched metal uranium reactor that operated from 1968 until 1988 at the former Junta de Energia Nuclear (JEN), CIEMAT at present. The critical measurements performed at the startup of the reactor are being evaluated as part of the International Critical Safety Benchmark Evaluation Program (ICSBEP) and proposed to be included in its 2001 edition. Additionally, the measurement of the mass reactivity coefficient is compared with MCNP4B calculations. This measurement allows one to perform the approach to critical without the need of a previous control rod calibration, thus enhancing the safety of such an approach. This technique can also be applied to other reactor types. CORAL-I (Ref. 1) is a 90% enriched metal uranium reactor domestically designed and manufactured in the experimental facilities of JEN, now CIEMAT, in ...

2001-06-17

159

TEXAS LPG FUEL CELL DEVELOPMENT AND DEMONSTRATION PROJECT Full-Text - Submission contains both citation data and full-text of the journal article. Full-text can be either a pre-print or post-print, but not the copyrighted article.  

Energy Technology Data Exchange (ETDEWEB)

The State Energy Conservation Office has executed its first Fuel Cell Project which was awarded under a Department of Energy competitive grant process. The Texas LPG Fuel Processor Development and Fuel Cell Demonstration Program is a broad-based public/private partnership led by the Texas State Energy Conservation Office (SECO). Partners include the Alternative Fuels Research and Education Division (AFRED) of the Railroad Commission of Texas; Plug Power, Inc., Latham, NY, UOP/HyRadix, Des Plaines, IL; Southwest Research Institute (SwRI), San Antonio, TX; the Texas Natural Resource Conservation Commission (TNRCC), and the Texas Department of Transportation (TxDOT). The team proposes to mount a development and demonstration program to field-test and evaluate markets for HyRadix?s LPG fuel processor system integrated into Plug Power?s residential-scale GenSys 5C (5 kW) PEM fuel cell system in a variety of building ...

2004-07-26

160

Influence of duration and rate of pulse rise of the applied voltage on ozone concentration in the barrier glow discharge  

International Nuclear Information System (INIS)

The barrier glow discharge between two planar electrodes, covered with dielectric, is studied under high-voltage pulsed power supply. Wide applications of such type of discharges, in particular, for ozone production, stimulated a number of investigations in this direction. In this work we investigated the dependence of ozone concentration on the duration and the rate of pulse rise of the applied voltage. The thyristor converter circuit with the shortening of input pulses on the base of the saturable throttle was used for the realization of this task. The output pulses with amplitude up to 15 kV, repetition frequency of 1 kHz, pulse duration of 0.3 #mu#s (or 7 #mu#s) and the rate of pulse rise of 0.1 #mu#s were generated with this scheme. Measurements of the ozone concentration produced in the air mixture have shown that its value increased by factor two with variation of the rate of pulse rise from 0.5 #mu#s to 0.1 #mu#s (for pulse duration of ...

2005-09-06

161

Development of QA/QC technology in Korea  

International Nuclear Information System (INIS)

KAERI (Korea Advanced Energy Research Institute) has performed research to develop the fabrication technology of CANDU nuclear fuel since 1981. Based on the satisfactory results of in-pile and out-of-pile tests of prototype nuclear fuel and the outstanding performance of 48 KAERI-made nuclear fuels in Wolsung(CANDU) power reactor, Korean government decided KAERI to supply all the nuclear fuels for Wolsung from 1988. In order to guarantee the safety and performance of nuclear fuel manufactured in mass production scale, well-organized quality assurance system and appropriate quality control techniques should be established. To establish the QA system, KAERI reviewed various QA standards and decided to establish QA system based on the 10 CFR 50 Appendix B. Quality control techniques was also revised to fit the mass production even though quality inspection techniques have already been developed during research period. By ...

1986-10-06

162

Measuring preferences for low-carbon energy technologies in South-East England: the case of electricity generation  

Energy Technology Data Exchange (ETDEWEB)

This paper presents a survey on public preferences in SE England for the use of wind, biomass and nuclear power in electricity generation. Using a labelled CE the perceived importance (value) to the public of distance and the energy options' impacts on biodiversity, emissions, land occupation and household cost was explored. Results suggest that impacts, technology name, demographic characteristics, attitudes towards the environment, knowledge and experience with the technologies were significant choice determinants. Considering the current debate about the development of nuclear power and biomass in UK and worldwide, this survey provides an insight into the factors affecting public acceptability

2008-07-01

163

Electric power monthly: March 1996, with data for December 1995  

Energy Technology Data Exchange (ETDEWEB)

The Electric Power Monthly (EPM) presents monthly electricity statistics for a wide audience including Congress, Federal and State agencies, the electric utility industry, and the general public. The purpose of this publication is to provide energy decision makers with accurate and timely information that may be used in forming various perspectives on electric issues that lie ahead. The EIA collected the information in this report to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275) as amended. 69 tabs.

1996-03-01

164

Electric power monthly: February 1995, with data for November 1994  

Energy Technology Data Exchange (ETDEWEB)

The Electric Power Monthly (EPM) presents monthly electricity statistics for a wide audience including Congress, Federal and State agencies, the electric utility industry, and the general public. The purpose of this publication is to provide energy decisionmakers with accurate and timely information that may be used in forming various perspectives on electric issues that lie ahead. The EIA collected the information in this report to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275) as amended. 64 tabs.

1995-02-22

165

Electric power monthly, May 1997 with data for February 1997  

Energy Technology Data Exchange (ETDEWEB)

The Electric Power Monthly (EPM) presents monthly electricity statistics for a wide audience including Congress, Federal and State agencies, the electric utility industry, and the general public. The purpose of this publication is to provide energy decisionmakers with accurate and timely information that may be used in forming various perspectives on electric issues that lie ahead. The EIA collected the information in this report to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275) as amended. 63 tabs.

1997-05-01

166

ARE. Regional energy supplies - progress report 2000-2001; ARE. Regionale Energieversorgung 2000-2001. Taetigkeitsbericht  

Energy Technology Data Exchange (ETDEWEB)

The ARE progress report discusses the following issues: Economic development and its effects on power supply; Deregulation of the electricity and gas market; Competition between regional utilities; Energy policy of the new German government; European regulations; Legislation on energy supply; Energy supply and cartel law; Regional supply in the East German states. [German] Der Taetigkeitsbericht der ARE befasst sich mit folgenden Themen: Gesamtwirtschaftliche Entwicklung und ihre Auswirkung auf die Energiewirtschaft, Oeffnung des Monopoles fuer Strom und Gas, Wettbewerb der regionalen Energieversorger, Energiepolitik der neuen Bundesregierung, Europaeische Richtlininen, energiewirtschaftsrecht, Versorgungswirtschaft und Kartellrecht und der Regionalversorgung in den neuen Bundeslaendern.

2002-05-01

167

Financing of power supply systems and pollution control equipment. Models, dimensions, developments  

Energy Technology Data Exchange (ETDEWEB)

The authors explain the bankers' point of view of the financial and economic aspects of developments in the energy sector, discussing the financing of natural gas pipelines (Muro, Megal, etc.), of nuclear power plant construction, of projects in the oil supply sector, and of pollution abatement measures and equipment for the power industry and other industries. The different financial situations of small firms or large firms supplying pollution control equipment are discussed referring to the financing schemes to be set up, explaining among other things the profitability assessment taking into account long-term development or delays in return on capital investment from borrowed funds as induced, e.g., by delays in the licensing procedure. Future demand for borrowed capital for pollution control or nuclear power plant development is difficult to assess by the banking ...

1988-11-01

168

Development of magnet power supply for J-PARC 50-GEV synchrotron  

International Nuclear Information System (INIS)

A new magnet power supply system for J-PARC 50GeV Synchrotron is proposed as solutions both in the power capacity and in the precision at the same time. The developed 10MW class magnet power supply consists of the advanced self-commutated current-source type converter (ACSC) using the new device IEGT rated at 4500V-2100A and the ''hybrid filter'' including the variable impedance filter with the equivalent 16 kHz switching. With 1/16 scale-model system using a prototype bending magnet, the experimental results showed the current ripple less than 1 x 10"-"6 and the tracking error less than #+-#0.5 x 10"-"4. (author)

2004-08-04

169

Characteristics and development report for the T1576 power supply and the MC3935 battery  

Energy Technology Data Exchange (ETDEWEB)

This report describes the requirements, designs, performance, and development histories for the T1576 power supply and the MC3935 rechargeable battery. These devices are used to power Permissive Action Link (PAL) ground controllers. The T1576 consists of a stainless steel container, one SA3553 connector, and one MC3935 battery. The MC3935 is a vented nickel/cadmium battery with 24 cells connected in series. It was designed to deliver 5.5 Amp-hours at 25{number_sign}C and the one-hour rate, with a nominal voltage of 28 V. The battery was designed to operate for 5 years or 500 full charge/discharge cycles. The power supply is expected to last indefinitely with replacement batteries and hardware.

1993-10-01

170

1992 Conversion Resources Supply Document  

Energy Technology Data Exchange (ETDEWEB)

In recent years conservation of electric power has become an integral part of utility planning. The 1980 Pacific Northwest Electric Power Planning and Conservation Act (Northwest Power Act) requires that the region consider conservation potential in planning acquisitions of resources to meet load growth. The Bonneville Power Administration (BPA) developed its first estimates of conservation potential in 1982. Since that time BPA has updated its conservation supply analyses as a part of its Resource Program and other planning efforts. Major updates were published in 1985 and in January 1990. This 1992 document presents updated supply curves, which are estimates of the savings potential over time (cumulative savings) at different cost levels of energy conservation measures (ECMs). ECMs are devices, pieces of equipment, or actions that increase the efficiency of ...

1992-03-01

171

Direct liquefaction Proof-of-Concept facility. Final technical progress report  

Energy Technology Data Exchange (ETDEWEB)

This report presents the results of work which included extensive modifications to HRI`s existing 3 ton per day Process Development Unit (PDU) and completion of the first PDU run. The 58-day Run 1 demonstrated scale-up of the Catalytic Two-Stage Liquefaction (CTSL Process) on Illinois No. 6 coal to produce distillate liquid products at a rate of up to 5 barrels per to of moisture-ash-free coal. The Kerr McGee Rose-SR unit from Wilsonville was redesigned and installed next to the US Filter installation to allow a comparison of the two solids removal systems. Also included was a new enclosed reactor tower, upgraded computer controls and a data acquisition system, an alternate power supply, a newly refurbished reactor, an in-line hydrotreater, interstage sampling system, coal handling unit, a new ebullating pump, load cells and improved controls and remodeled preheaters. Distillate liquid yields of 5 ...

1995-08-01

172

Design of a 60 MW CFB gasification system (CGAS) for Uganda : utilising rice husks as input fuel  

Energy Technology Data Exchange (ETDEWEB)

In Uganda, biomass comprises more than 95 per cent of the total energy supply. Agricultural residues are a major source of energy that can be converted into producer gas in biomass gasifiers. The high poverty levels in Uganda can be attributed in part to the fact that more than 90 per cent of the population does not have access to electricity due to limited and unreliable electricity produced in the country. A circulating fluidized bed (CFB) gasification system was designed in this study in order to generate a system for the effective use of agricultural wastes for energy production. Rice husks were used as the feedstock for a power output of 60 MW. The gasification system was designed using ERGUN CFB software with available theoretical and experimental data. The design comprises a reactor subsystem, air distribution plate, cyclone, air inlet and fuel feeding systems. The reactor is 10 m high and has a ...

2010-07-01

173

Transuranium isotopes production and their effect on the three-dimensional core calculation  

Energy Technology Data Exchange (ETDEWEB)

The operation of a nuclear power reactor necessarily implies the consumption or burnup of reactor fuel by fission and capture, which gives rise to a decrease in the reactivity of the reactor. The effect of americium formation on the criticality of a thermal power reactor using two types of fuel is studied. The three-dimensional core calculation is used to calculate the production of the transuranium isotopes and their effect on the effective multiplication factor (K[sub eff]). This effect cannot be neglected for thermal power reactors with UO[sub 2]-PuO[sub 2] fuel (3.11% after 70 weeks of operation). The effect of the transuranium isotopes on the K[sub eff] for a thermal power reactor with UO[sub 2] fuel is about 0.0018% and can be ignored. (author).

1993-02-01

174

Transuranium isotopes production and their effect on the three-dimensional core calculation  

International Nuclear Information System (INIS)

The operation of a nuclear power reactor necessarily implies the consumption or burnup of reactor fuel by fission and capture, which gives rise to a decrease in the reactivity of the reactor. The effect of americium formation on the criticality of a thermal power reactor using two types of fuel is studied. The three-dimensional core calculation is used to calculate the production of the transuranium isotopes and their effect on the effective multiplication factor (K_e_f_f). This effect cannot be neglected for thermal power reactors with UO_2-PuO_2 fuel (3.11% after 70 weeks of operation). The effect of the transuranium isotopes on the K_e_f_f for a thermal power reactor with UO_2 fuel is about 0.0018% and can be ignored. (author).

175

Heat transfer augmentation by gas-particle two-phase flow  

International Nuclear Information System (INIS)

The helium-cooled HTGR (High Temperature Gas-cooled Reactor) will take an important position in the global energy strategy. It is expected to supply not only electricity but also high quality thermal energy for various industries and local utilities without exhausting any green house effect gas or acid rain gas. The key R and D issue of the HTGR is economical competitiveness, particularly against light water reactors. Due to the poor heat transfer of the single phase helium, the HTGR's volumetric power density is restricted to tenth of corresponding PWR's value so that increasing the power density by improving heat transfer is strongly desired. The standstill can be broken through by adopting gas-solid suspension medium. Its heat transfer performance is quite excellent. Its heat capacity can be increased drastically without excessive pressurization. Although the thermal radiation is ...

1995-06-01

176

Transportation cost of nuclear off-peak power for hydrogen production based on water electrolysis  

International Nuclear Information System (INIS)

The paper describes transportation cost of the nuclear off-peak power for a hydrogen production based on water electrolysis in Japan. The power could be obtainable by substituting hydropower and/or fossil fueled power supplying peak and middle demands with nuclear power. The transportation cost of the off-peak power was evaluated to be 1.42 yen/kWh when an electrolyser receives the off-peak power from a 6kV distribution wire. Marked reduction of the cost was caused by the increase of the capacity factor. (author)

177

Hematological responses after inhaling "2"3"8PuO_2: An extrapolation from beagle dogs to humans  

International Nuclear Information System (INIS)

The alpha emitter plutonium-238 ("2"3"8Pu), which is produced in uranium-fueled, light-water reactors, is used as a thermoelectric power source for space applications. Inhalation of a mixed oxide form of Pu is the most likely mode of exposure of workers and the general public. Occupational exposures to "2"3"8PuO_2 have occurred in association with the fabrication of radioisotope thermoelectric generators. Organs and tissue at risk for deterministic and stochastic effects of "2"3"8Pu-alpha irradiation include the lung, liver, skeleton, and lymphatic tissue. Little has been reported about the effects of inhaled "2"3"8PuO_2 on peripheral blood cell counts in humans. The purpose of this study was to investigate hematological responses after a single inhalation exposure of Beagle dogs to alpha-emitting "2"3"8PuO_2 particles and to extrapolate results to humans.

1994-11-01

178

Fluid mixing in reactor containment  

Energy Technology Data Exchange (ETDEWEB)

Full text of publication follows: Hydrogen release and distribution in nuclear power plant containment is an important safety issue. Selection of a proper turbulence model is important for accurate estimation of the mixing process. The selection of turbulence model is dictated by the best compromise between accuracy and computational efforts. For this, three different turbulence models, viz. Standard k-{epsilon}, RNG k-{epsilon} and Reynolds Stress Model, based on Reynolds averaged Navier Stokes equations (RANS) approach, were used. The computations were done using the CFD code FLUENT, which is based on the control volume methodology. The computational results were compared with the experimental results of HYMIS test facility, where helium was used to simulate hydrogen. The processes of helium plume rise, multiple plume merging, distribution and mixing were studied. Based on these computations, a simple analytical/empirical zone based model was ...

2005-07-01

179

Fluid mixing in reactor containment  

International Nuclear Information System (INIS)

Full text of publication follows: Hydrogen release and distribution in nuclear power plant containment is an important safety issue. Selection of a proper turbulence model is important for accurate estimation of the mixing process. The selection of turbulence model is dictated by the best compromise between accuracy and computational efforts. For this, three different turbulence models, viz. Standard k-#epsilon#, RNG k-#epsilon# and Reynolds Stress Model, based on Reynolds averaged Navier Stokes equations (RANS) approach, were used. The computations were done using the CFD code FLUENT, which is based on the control volume methodology. The computational results were compared with the experimental results of HYMIS test facility, where helium was used to simulate hydrogen. The processes of helium plume rise, multiple plume merging, distribution and mixing were studied. Based on these computations, a simple analytical/empirical zone based model was ...

2005-10-02

180

A study of public acceptance of construction of atomic power plant  

International Nuclear Information System (INIS)

In June 2010, Basic Energy Plan was approved in a Cabinet meeting. It says that Japan aims to construct more than 14 atomic power plants by 2030. Today, there are 12 plans of construction of atomic power plant, but it is hard to say that their plans easily come off. That's because public acceptance of atomic power plant is low in Japan, for example local residents wage opposition campaigns. This study conducts a survey in the form of a questionnaire and analyzes it by Analytical Hierarchical Process (AHP). Analytic Hierarchy Process is a structured technique for dealing with complex decisions. A questionnaire using AHP is very easy to answer and analyze. This survey was conducted in 2 areas. First area is Hohoku-cho, Yamaguchi Pref. that had a plan of construction of atomic power plant and the plan was demolished by opposition campaigns. Second area is Kaminoseki-cho, Yamaguchi ...

2011-01-01

181

Regulatory quality assurance requirements for the operation of nuclear R and D facilities in Korea  

International Nuclear Information System (INIS)

Full text: Korea Atomic Energy Research Institute (KAERI) has many R and D facilities in operation. including HANARO research reactor, radioactive waste treatment facility (RWTF), post-irradiation examination facility (PIEF) and irradiated material test facility (IMEF). Recently. nation-wide interest is focused on the safety and security of major industrial facilities. Safe operation of nuclear facilities is imperative because of the consequence of public disaster by radiological release/contamination, in case of an accident. Recently, Ministry of Science and Technology (MOST) of the Korean government announced amendments of Atomic Energy laws to enforce requirements of the physical protection and radiological emergency. All provisions on nuclear safety regulation and radiation protection are entrusted to the Atomic Energy Act(AEA). The Act is enacted as the main law concerning the safety regulation of nuclear installations, and is supplemented ...

2006-10-15

182

Properties of SiC/SiC joining s and coatings for fusion  

International Nuclear Information System (INIS)

Full text of publication follows: As SiCf/SiC composites are very low activation materials, their use as structural material for the reactor blanket and first wall components appears essential to demonstrate the potential of D-T fusion power reactor. Positive features of SiCf/SiC are their high performances at elevated operating temperature and the ability to produce a specific component. Critical issues of SiCf/SiC are the mechanical properties, radiation stability and, with regard to technological issues, their hermeticity and joining processes. Improvement of joining processes for SiC/SiC components is also needed. Recently, several blanket designs have been studied: the TAURO blanket concept in the European Union, the ARIESAT concept in the US and the DREAM concept in Japan. In those reactors, hermetic SiCf/SiC or self-sealing coatings are mandatory. The basic idea of self ...

2007-12-10

183

ESTABLISHING FINAL END STATE FOR A RETIRED NUCLEAR WEAPONS PRODUCTION REACTOR; COLLABORATION BETWEEN STAKEHOLDERS, REGULATORS, AND THE FEDERAL GOVERNMENT - 11052  

Science.gov (United States)

The Savannah River Site (SRS) is a 310-square-mile United States Department of Energy nuclear facility located along the Savannah River (SRS) near Aiken, South Carolina. Nuclear weapons material production began in the early 1950s, utilizing five production reactors. In the early 1990s all SRS production reactor operations were terminated. The first reactor closure end state declaration was recently institutionalized in a Comprehensive Environmental Response and Compensation and Liability Act (CERCLA) Early Action Record of Decision. The decision for the final closure of the 318,000 square foot 105-P Reactor was determined to be in situ decommissioning (ISD). ISD is an acceptable and cost effective alternative to off-site disposal for the reactor building, which will allow for consolidation of remedial action wastes generated from other cleanup activities within the P Area. ISD is ...

2010-11-17

184

Washington: a guide to geothermal energy development  

Energy Technology Data Exchange (ETDEWEB)

Washington's geothermal potential is discussed. The following topics are covered: exploration, drilling, utilization, legal and institutional setting, and economic factors of direct use projects. (MHR)

1980-06-01

185

Gas turbines and steam turbines for power plants of the next generation; Gas- und Dampfturbinen fuer Kraftwerke der naechsten Generation  

Energy Technology Data Exchange (ETDEWEB)

Electricity is a universal energy and one of the driving powers of civilisation. World-wide, future developments like growing economies and structural changes in industry, a higher standard of living and a bigger world population - are impossible without appropriate supply of power and electricity. An expert of Siemens Power Generation presents his views. (orig.)

2006-11-15

186

Effect of power supply ripple on emittance growth in the collider  

Energy Technology Data Exchange (ETDEWEB)

Power supply ripple at frequencies of 720 Hz and its harmonies is expected to affect the motion of particles in the collider. These ripple frequencies are nearly resonant with the betatron frequencies. To estimate the tolerable ripple levels, we have tracked particles through the complete nonlinear lattice for 10[sup 4] turns with ripple fed from 10 different power stations and including up to 7 different ripple frequencies. We presently estimate that relative ripple amplitudes must be below the 10[sup 8] level for there to be no significant impact on the emittance over the short term.

1993-05-01

187

Effect of power supply ripple on emittance growth in the collider  

Energy Technology Data Exchange (ETDEWEB)

Power supply ripple at frequencies of 720 Hz and its harmonies is expected to affect the motion of particles in the collider. These ripple frequencies are nearly resonant with the betatron frequencies. To estimate the tolerable ripple levels, we have tracked particles through the complete nonlinear lattice for 10{sup 4} turns with ripple fed from 10 different power stations and including up to 7 different ripple frequencies. We presently estimate that relative ripple amplitudes must be below the 10{sup 8} level for there to be no significant impact on the emittance over the short term.

1993-05-01

188

Nuclear power and target-oriented CO{sub 2} reduction strategies; Kernenergie und zielorientierte CO{sub 2}-Minderungsstrategie  

Energy Technology Data Exchange (ETDEWEB)

Compared to the reference year of 1990, CO{sub 2} emissions of the Federal Republic of Germany have been curbed by about 12%, primarily as a result of industrial backfitting and pollution abatement measures accomplished in the industrial infrastructure of the new Federal Laender of Germany. Federal Government policy sticks to the previous commitment, to reduce carbon dioxide emissions by 25% by the year 2005. Current forecasts and scenarios of future greenhouse gas emissions show that only immediate adherence to a very stringent reduction policy might ensure that this ambitious goal will be achieved. In this context, any change of the baseline data and scenarios hitherto used for progonostic assessments is a crucial factor, so that the article here discusses the impacts of a change in the nuclear generation scenario, as recently ventilated by the German Federal Government, and expected effects on public power supply. ...

1999-01-01

189

Summary of Information Presented at an NRC-Sponsored Low-Power Shutdown Public Workshop, April 27, 1999, Rockville, Maryland  

Energy Technology Data Exchange (ETDEWEB)

This report summarizes a public workshop that was held on April 27, 1999, in Rockville, Maryland. The workshop was conducted as part of the US Nuclear Regulatory Commission's (NRC) efforts to further develop its understanding of the risks associated with low power and shutdown operations at US nuclear power plants. A sufficient understanding of such risks is required to support decision-making for risk-informed regulation, in particular Regulatory Guide 1.174, and the development of a consensus standard. During the workshop the NRC staff discussed and requested feedback from the public (including representatives of the nuclear industry, state governments, consultants, private industry, and the media) on the risk associated with low-power and shutdown operations.

1999-07-01

190

Integrated evolutionary neural network approach with distributed computing for congestion management  

British Library Electronic Table of Contents (United Kingdom)

Electric supply industry is facing deregulation all over the world. Under deregulated power supply scenario, power transmission congestion has become more intensified and recurrent, as compared to conventional regulated power system. Congestion may lead to violation of voltage or transmission capacity limits, thus threatens the power system security and reliability. Also the growing congestion may lead to unanticipated divergent electricity pricing. Owing to these facts congestion management has become a crucial issue in the deregulated power system scenario. Fast and precise prediction of nodal congestion prices in real time deregulated/spot power market may enable market participants and system operators to keep pace with the congestion by taking preventive measures like transaction resc...

2010-01-01

191

Charging a Battery-Powered Device with a Fiber-Optically Connected Photonic Power System for Achieving High-Voltage Isolation  

Energy Technology Data Exchange (ETDEWEB)

This paper describes the development and testing of a system to provide isolated power to the cathode-subsystem electronics of an x-ray tube. These components are located at the cathode potential of several hundred kilovolts, requiring a supply of power isolated from this high voltage. In this design a fiber-optically connected photonic power system (PPS) is used to recharge a lithium-ion battery pack, which will subsequently supply power to the cathode-subsystem electronics. The suitability of the commercially available JDSU PPS for this application is evaluated. The output of the ppe converter is characterized. The technical aspects of its use for charging a variety of Li-Ion batteries are discussed. Battery charge protection requirements and safety concerns are also addressed.

2008-01-01

192

APOPTOSIS AND PROLIFERATION DURING DICHLOROACETIC ACID (DCA) INDUCED HEPTACELLULAR CARCINOGENESIS IN THE F344 MALE RAT  

Science.gov (United States)

Apoptosis and Proliferation During DicWoroacetic Acid (DCA) Induced Hepatocellular Carcinogenesis in the F344 Male Rat Chlorine, introduced into public drinking \\\\'ater supplies for disinfection, can react with organic compounds in surface waters to form toxic by-prod...

193

Formation and decay of secondary actinides in water reactor and fast neutron reactors  

International Nuclear Information System (INIS)

Actinides other than the main uranium or plutonium isotopes take a growing part in the different stages of the nuclear cycle. For the French nuclear power program based on the development of light water reactors and fast breeders, many evaluations of the secondary actinides build up are made for the both reactor types using mainly the existing reactor codes. The comparison of these foreseen compositions with experimental results allows to perform some adjustments of the neutronic data. The secondary actinide compositions are given for some typical fuels and their consequences on the nuclear cycle are discussed. An hypothetical burning of these wastes in fast reactors has been studied and the main conclusions are reported.

194

Axiomatic Design Approach for a Reactor Head Structure Assembly  

Energy Technology Data Exchange (ETDEWEB)

Korea Atomic Energy Research Institute (KAERI) has been developing the integral reactor. The reactor head structure assembly (RHSA) is the structure installed over the reactor cover. Due to the characteristics of an integral reactor, there are many instrument cables and power cables coming out from the reactor cover and main components. The RHSA provides an interface location to connect these cables from Architecture Engineer (AE) and System Designer (SD). It also prevents a pipe whip and it prohibits instruments from becoming missiles. In this research, the axiomatic design approach for the RHSA is performed.

2006-07-01

195

FFTF [Fast Flux Test Facility] fuel handling experience (1979--1986)  

International Nuclear Information System (INIS)

The Fast Flux Test Facility (FFTF)is a 400 MW (th) sodium-cooled fast flux test reactor located on the Hanford Site in southeastern Washington State. The FFTF is operated by the Westinghouse Hanford Company for the United States Department of Energy. The FFTF is a three loop plant designed primarily for the purpose of testing full-scale core components in an environment prototypic of future liquid metal reactors. The plant design emphasizes features to enhance this test capability, especially in the area of the core, reactor vessel, and refueling system. Eight special test positions are provided in the vessel head to permit contact instrumented experiments to be installed and irradiated. These test positions effectively divide the core into three sectors. Each sector requires its own In-Vessel Handling Machine (IVHM) to access all the core positions. Since the core and the in-vessel refueling components ...

1987-09-01

196

FFTF [Fast Flux Test Facility] cesium trap design, installation, and operating experience  

International Nuclear Information System (INIS)

The Fast Flux Test Facility (FFTF) is a 400-MWt, sodium-cooled reactor located on the Hanford Site near Richland, Washington, USA. The FFTF is owned by the U.S. Department of Energy and is operated by the Westinghouse Hanford Company. The FFTF was designed to test fuels and materials for use in liquid metal reactors. Since initial operation in 1982, anticipated breaches of experimental fuel pins have released fission products, including cesium, into the primary sodium. Because of its high volatility, cesium vaporizes into the cover gas space, where it condenses on components and equipment and is transported into the cover gas outlet. Because of the long half-life of "1"3"7Cs, these deposits result in long-term, local radiation levels that make contact maintenance difficult. Thus, a cesium trap was installed in FFTF to reduce the cesium level in the sodium. The trap could also permit a Run Beyond Cladding Breach (RBCB) ...

1988-10-17

197

Engaging both the Eagle and the Dragon: The Philippines' Precarious and Futile Attempt in Equi balancing  

British Library Electronic Table of Contents (United Kingdom)

The article examines the limits and challenges small powers face when they adjust to systemic changes. Specifically, this article discusses the Philippines' conduct of a diplomatic strategy of equi balancing between the USA and China. In this strategy, the Philippines enhances and deepens its security relations with its strategic ally, the USA and at the same time, obtains economic assistance and politico diplomatic concessions from East Asia's emergent power, China. The Philippines' diplomatic gambit, however, is restrained by its formal alliance with the USA and its chronic territorial dispute with China over the Spratly Islands. At present, several developments are undermining Manila's efforts in playing this balancing game with Washington and Beijing. These are: the Philippines' passiv...

2010-01-01

198

Omega process for the use of substitute fuels; Waste energy: Omega-Verfahren zur Verwertung von Ersatzbrennstoffen  

Energy Technology Data Exchange (ETDEWEB)

Only about 25% of residue accumulating in the Federal Republic of Germany is currently used for the purposes of energy. This residue will be converted into fuel for power stations by the Omega process when the dumping of waste with a calorific value in excess of 5 MJ/kg is prohibited with effect from 2005. This oxygen melting process is suitable for the local use of substitute fuels. Waste is converted into a high-quality synthesis gas with a wide range of uses. The Omega process combines drying, thermal decomposition, gasification and melting of the material used in a single-stage process. This is now technologically possible for the first time by combining a metallurgical cupola furnace with a traditional gas producer. The highly-calorific synthesis gas produced by the Omega process can be used in block heat and power stations or as an industrial fuel gas, instead of natural gas. It is also suitable as a starting material for synthesising ...

2003-03-01

199

Nuclear power generation. Chapter 14  

International Nuclear Information System (INIS)

As part of a handbook on the efficient use of energy a chapter is included which is intended to give an appreciation of the principles and problems involved in the generation of nuclear power. The subject is discussed under the following headings: introductory nuclear physics; basic reactor physics; thermal reactors; fast reactors; fuel reserves and utilization; environmental considerations; nuclear fusion. (U.K.).

1975-01-01

200

Combined cycles and combined energy systems for a safe and sound environment and life  

Energy Technology Data Exchange (ETDEWEB)

Discussion is presented of world CO{sub 2} emissions and the effect rising population and population distribution has on this. Possible ways of decreasing emissions are presented, including potential for heat recovery, exhaust-air purification as an energy supply, shared power supply in industry, the use of cogeneration, and multiple use of heat in industry. 9 refs., 10 figs., 3 tabs.

1992-01-01

201

Air pollution abatement measures: Energy supply at Gelsenkirchen; Klimaschutz im Aufwaertstrend am Beispiel der Energieversorgung in Gelsenkirchen  

Energy Technology Data Exchange (ETDEWEB)

The author cites the example of Gelsenkirchen in order to illustrate the measures taken in the field of power supply with regard to air pollution abatement. (orig.) [Deutsch] Der Verfasser gibt am Beispiel der Stadt Gelsenkirchen einen Ueberblick darueber, was hinsichtlich des Klimaschutzes - und zwar bezogen auf die Energieversorgung - in den letzten Jahren in Gelsenkirchen getan wurde. (orig.)

1996-07-01

202

Department of Nuclear Safety Research and Nuclear Facilities annual report 1995  

Energy Technology Data Exchange (ETDEWEB)

The report presents a summary of the work of the Department of Nuclear Safety Research and Nuclear Facilities in 1995. The department`s research and development activities are organized in three research programmes: Radiation Protection, Reactor Safety, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the Research Reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the Educational Reactor DR1. Lists of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au) 5 tabs., 21 ills.

1996-03-01

203

Cost sensitivity analysis of possible fusion power plants  

International Nuclear Information System (INIS)

A reference design was used in preparing a mathematical model of a fusion power plant with a tokamak reactor to investigate the extent to which the uncertainty still inherent in the physical reactor parameters affects the power costs. While only limited reductions of the power costs are achieved by improvements of the reference values for the reactor burn time, power density in the torus and load on the first wall, the power costs rise in keeping with the extent to which these parameters fall short of the reference values. As the results obtained in present-day experiments are still well below the reference values, a great deal of effort is still required in the fields of plasma physics and materials research to achieve an economically operating fusion power plant. (orig.).

204

Advanced Power Electronics Interfaces for Distributed Energy Workshop Summary: August 24, 2006, Sacramento, California  

Energy Technology Data Exchange (ETDEWEB)

The Advanced Power Electronics Interfaces for Distributed Energy Workshop, sponsored by the California Energy Commission Public Interest Energy Research program and organized by the National Renewable Energy Laboratory, was held Aug. 24, 2006, in Sacramento, Calif. The workshop provided a forum for industry stakeholders to share their knowledge and experience about technologies, manufacturing approaches, markets, and issues in power electronics for a range of distributed energy resources. It focused on the development of advanced power electronic interfaces for distributed energy applications and included discussions of modular power electronics, component manufacturing, and power electronic applications.

2006-10-01

205

Public Understanding of Cognitive Neuroscience Research Findings: Trying to Peer Beyond Enchanted Glass  

British Library Electronic Table of Contents (United Kingdom)

This article considers the appeal of cognitive neuroscience research to the general public within the context of the deep puzzles involved in using our minds to understand how our minds work. It offers a few promising examples of findings that illuminate the ways of the mind and reveal these workings to be counter-intuitive with our subjective experience. However, this promise is tempered by the powerful role that perception, attention, and cognition play in how we reason about evidence. It argues that the interplay between what we believe about the nature of our minds and what the findings suggest constitutes a primary challenge in encouraging public understanding of cognitive neuroscience findings.

2011-01-01

206

Supply of medium and small hydropower equipment  

Energy Technology Data Exchange (ETDEWEB)

This paper presents a brief account of Lingling Hydroelectric Power Equipment General Works, the capacity of equipment production, the organization body, the quality assurance system and supervision of government department on its product quality.

1995-07-01

207

OPC Server and BridgeView Application for High Voltage Power Supply Lecroy 1458  

CERN Document Server

Abstract The aim of this project was to develop an OPC server to communicate over an RS232 serial line. This communication media is commonly used with commercial instruments. The development was made for a High Voltage power supply in the context of the Alice [1] experiment. In addition, the structured modular concept will allow changing the transmission media or power supply type with little effort. The high voltage power supply should be accessible remotely through a network. OPC[2] is an acronym for OLE[3] for Process Control. OPC is based on the DCOM [3] communication protocol, which allows communication with any computer running a Windows based OS. This standard is widely used in industry to access device data through Windows applications. The concept is based on the client-server architecture. The hardware and the software architecture are described. ...

2000-01-01

208

Computing needs of the superconducting super collider  

Energy Technology Data Exchange (ETDEWEB)

Following a brief description of the SSC, the computing needs are discussed for both the accelerator design and the experimentation. The computing power required is considerably beyond that being used at present facilities, and parallel processing is expected to play an important role in supplying these needs.

1984-01-01

209

Final Report of ''On-the-Job Training'' on the CANDU Reactor.  

Science.gov (United States)

This is the final Report for the technical ''on-the-job traning'' for the Wolsung CANDU nuclear power plant which is the first Pressurized Heavy Water Reactor setting up in Korea. The technical ''on-the-job traning'' was established to increase the capabi...

1983-01-01

210

Exploration and practice on contract management of Daya Bay Nuclear Power Station  

International Nuclear Information System (INIS)

In the market economy, Daya Bay Nuclear Power Station needs to out source or allow to suppliers among industries, while concentrating its core competitive capability, for safely and stable operation. By evaluating the features of contract management in Daya Bay Nuclear Power Station, set up the organization and process of the supply management

2002-02-01

211

A self-tuning Power System Stabilizer for wide-range synchronous generator operation  

Energy Technology Data Exchange (ETDEWEB)

A self-tuning Power System Stabilizer (PSS) is suggested in this paper. Computer simulations, of a lightly-damped single turbine-generator supplying power to an infinite bus system, show that this self-tuning PSS can work over a large operating range and make a significant improvement in rotor damping.

1989-08-01

212

Geopolitical and socioeconomic factors presently impacting on United States uranium supply  

International Nuclear Information System (INIS)

The near-term availability of domestic and selected foreign uranium resources for use by United States electric utilities is considered in light of projected geopolitical and socioeconomic considerations. No attempt is made to analyze the impact on domestic uranium supply of inflation or cost-price considerations, the introduction of the breeder reactor, limitations in enrichment capacity, or the presently expanding uranium inventory. All data are current as of mid-1980. The period with which this research is concerned is 1980-1995. It is concluded that the United States must promote responsible, environmentally acceptable uranium resource exploration and development, if this nation is to remain self sufficient in this necessary energy commodity.

1980-10-28

213

Some studies on physics parameters of Wolsung unit no. 1  

International Nuclear Information System (INIS)

Nuclear physics parameters of the Wolsung CANDU-PHW reactor are computed by use of the PHWCELL computer code that is an improved version of LATREP. The PHWCELL code mainly computes cell parameters of heavy water moderated reactors, and modeling scheme of heavy water reactor cell calculations has been developed with the PHWCELL computer code. The reactor operating conditions considered in the study are cold zero power (CZP) and hot full power (HFP) with equilibrium poison. The cell parameters are also computed as a function of fuel burnup and the numerical results are compared with the results in PSR of the Wolsung unit and in the previous study. (author).

1980-01-01

214

Structure of energy supply, energy analysis, projections for energy demand development and for emission-reducing energy carrier application in powered vehicles in the district Schmalkalden-Meiningen; Struktur der Energieversorgung, Energieanalysen, Prognosen zur Energiebedarfsentwicklung und zum emissionsmindernden Energietraegereinsatz fuer Kraftfahrzeuge im Landkreis Schmalkalden-Meiningen  

Energy Technology Data Exchange (ETDEWEB)

The present publication is based on facts, data, knowledge and projects, which have been incorporated in the development of an energy concept for the district Schmalkalden-Meiningen. The energy concept of a district is a concept oriented at action on and realisation of mid-term and long term decisions in the fields of energy policy, economy and ecology, which must be taken by municipal and economic decision-making bodies. The energy concept accords with the targets of the Agenda 21, the environmental targets of the Federal Republic of Germany and of the Land Thuringia. Accepting this energy concept the district Schmalkalden-Meiningen shows its willingness to contribute to a lasting development in all fields of economy and ecology and thus does justice to its increasing responsibility. (orig.) [German] Die vorliegende Veroeffentlichung baut auf Fakten, Daten, Erkenntnissen und Projekten auf, die in die Erarbeitung des Energiekonzeptes fuer den Landkreis ...

2001-07-01

215

The need and prospects for improved fusion reactors  

International Nuclear Information System (INIS)

Conceptual fusion reactor studies over the past 10-15 yr have projected systems that may be too large, complex, and costly to be of commercial interest. One main direction for improved fusion reactors points toward smaller, higher-power-density approaches. First-order economic issues (i.e., unit direct cost and cost of electricity) are used to support the need for more compact fusion reactors. The results of a number of recent conceptual designs of reversed-field pinch, spheromak, and tokamak fusion reactors are summarized as examples of more compact approaches. While a focus has been placed on increasing the fusion-power-core mass power density beyond the minimum economic threshold of 100-200 kWe/tonne, other means by which the overall attractiveness of fusion as a long-term energy source are also addressed.

216

Insights from Development of Regulatory PSA Model for SMART  

International Nuclear Information System (INIS)

SMART (System-Integrated Modular Advanced Reactor) is a first-of-the-kind integral reactor with 330 MW thermal power under active development by Korea Atomic Energy Research Institute (KAERI) for power generation and seawater desalination. SMART employs various design features that are not typically found in other nuclear power plants. Examples include a unique passive residual heat removal system (PRHRS), and enclosure of a pressurizer, eight helical steam generators, and eight canned reactor coolant pumps inside the reactor pressure vessel. This paper presents risk insights on the SMART reactor gained during the development of a regulatory PSA model by Korea Institute of Nuclear Safety (KINS)

2010-10-01

217

The advanced MAPLE reactor concept  

International Nuclear Information System (INIS)

High-flux neutron sources are continuing to be of interest both in Canada and internationally to support materials testing for advanced power reactors, new developments in extracted-neutron-beam applications, and commercial production of selected radioisotopes. The advanced MAPLE reactor concept has been developed to meet these needs. The advanced MAPLE reactor is a new tank-type D_2O reactor that uses rodded low-enrichment uranium fuel in a compact annular core to generate peak thermal-neutron fluxes of 1 x 10"1"9 n#centre dot#s"-"1 in a central irradiation rig with a thermal power output of 50 MW. Capital and incremental development costs are minimized by using MAPLE reactor technology to the greatest extent practicable.

1985-10-14

218

Techniques and tools for condition monitoring and life prediction of fluid power controls used in fuel handling systems of PHWRs  

International Nuclear Information System (INIS)

Various diagnostics techniques for condition monitoring and life prediction of fluid power components and system are discussed. Though some of the techniques are very promising but may not be accepted because of increase in the instrumentation, it is planned to implement these techniques on various circuits of Fluid Power Lab for further improving and developing these for direct implementation in various fluid power circuits of power reactors. (author). 6 figs.

219

System behavior after a loss of electric power in HANARO  

International Nuclear Information System (INIS)

A LOss of Electric Power(LOEP) experiment was conducted after a 30MW full power operation as one of the reactor performance tests to verify the design characteristics of the HANARO. The objective of LOEP test was to investigate the integral behaviors of the system and the components as well as the cooling characteristics when the electric power was lost unexpectedly. Through the test, it was confirmed that the residual heat from the core was safely removed by the natural convection cooling and the assistant power systems operated normally

2005-04-11

220

Core power distribution measurement and data processing in Daya Bay Nuclear Power Station  

International Nuclear Information System (INIS)

For the first time in China, Daya Bay Nuclear Power Station applied the advanced technology of worldwide commercial pressurized reactors to the in-core detectors, the leading excore six-chamber instrumentation for precise axial power distribution, and the related data processing. Described in this article are the neutron flux measurement in Daya Bay Nuclear Power Station, and the detailed data processing.

221

Control rod drives  

International Nuclear Information System (INIS)

Purpose: To secure the reactor operation safety by the provision of a fluid pressure detecting section for control rod driving fluid and a control rod interlock at the midway of the flow pass for supplying driving fluid to the control rod drives. Constitution: Between a driving line and a direction control valve are provided a pressure detecting portion, an alarm generating device, and a control rod inhibition interlock. The driving fluid from a driving fluid source is discharged by way of a pump and a manual valve into the reactor in which the control rods and reactor fuels are contained. In addition, when the direction control valve is switched and the control rods are inserted and extracted by the control rod drives, the pressure in the driving line is always detected by the pressure detection section, whereby if abnormal pressure is resulted, the alarm generating device is actuated to warn the ...

222

Living and Working Around High-Voltage Power Lines.  

Energy Technology Data Exchange (ETDEWEB)

This booklet presents safe practices that you should follow if your activities take you near high-voltage transmission lines. It documents information that has generally been available to the public.

1981-08-01

223

Electric power monthly, July 1995 - with data for April 1995  

Energy Technology Data Exchange (ETDEWEB)

This publication provides statistical data on net generation, fuel consumption, fossil fuel stocks, electricity sales, revenue, and average revenue per kilowatthour of electricity sold. Data on fossil fuel stocks and costs are also included.

1995-07-01

224

Dose Optimization for Long-term rAAV-mediated RNA Interference in the Nigrostriatal Projection Neurons  

UK PubMed Central (United Kingdom)

Short-hairpin RNA (shRNA)–mediated gene knockdown is a powerful tool for targeted gene silencing and an emerging novel therapeutic strategy. Recent publications, however, reported unexpected...Full Text Available

2009-09-01

225

Annual report on heavy water reactor fuel fabrication  

Energy Technology Data Exchange (ETDEWEB)

The CANDU-type nuclear fuel localization project started in 1981, and mass-production system completed in 1987 through the pilot scale demonstration of fuel manufacturing. Since the completion of the mass-production system, about 24,000 fuel bundles (450 ton-U) had been delivered to Wolsung Nuclear Power Plant by the end of 1992, according to the fuel supply contracts with KEPCO. The superiority of KAERI-made nuclear fuel has been demonstrated by having achieved the highest utilization factor in the world in 1992. In 1993, as contracted, 4,824 fuel bundles well fabricated and delivered to Wolsung Nuclear Power Plant. The process improvement, quality control, safety management, safeguards of nuclear materials and various kinds of audits have also been performed in the course for fuel manufacturing. Especially in 1993, the difficulties of the reduction of participating work-force were overcome by improving the manufacturing ...

1994-03-01

226

Energy saver A-sector power test results  

Energy Technology Data Exchange (ETDEWEB)

The superconducting magnets and associated cryogenic components in A-sector represent the initial phase of installation of the Fermilab superconducting accelerator, designed to accelerate proton beams to energies of 1 TeV. Installation of the magnets, comprising one-eighth of the ring, was completed in December, 1981. Cooldown and power tests took place in the first half of 1982, concurrent with main ring use for 400 GeV high energy physics. The tests described in this paper involved 151 cryogenic components in the tunnel: 94 dipoles, 24 quadrupoles, 25 spool pieces, 3 feed cans, 4 turn-around boxes and 1 bypass. Refrigeration was supplied by three satellite refrigerators, the Central Helium Liquefier, and two compressor buildings. The magnets were powered by a single power supply.

1982-09-15

227

Radionuclide air emissions report for the Hanford Site -- calendar year 1997  

Energy Technology Data Exchange (ETDEWEB)

This report documents radionuclide air emission from the Hanford Site in 1997, and the resulting effective dose equivalent to the maximally exposed member of the public, referred to as the MEI. The report has been prepared in accordance with reporting requirements in the Code of Federal Regulations, Title 40, Protection of the Environment, Part 61, National Emissions Standards for Hazardous Air Pollutants, Subpart H, National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities. This report has also been prepared in accordance with the reporting requirements of the Washington Administrative Code Chapter 246-247, Radiation Protection-Air Emissions. The effective dose equivalent to the MEI from the Hanford Site`s 1997 point source emissions was 1.2 E-03 mrem (1.2 E-05 mSv), which is well below the 40 CFR 61 Subpart H regulatory limit of 10 mrem/yr. Radon and thoron emissions, exempted from 40 CFR ...

1998-06-17

228

Monte Carlo verification of point kinetics for safety analysis of nuclear reactors  

Energy Technology Data Exchange (ETDEWEB)

Monte Carlo neutron transport methods can be used to verify the applicability of point kinetics for safety analysis of nuclear reactors. KENO-NR was used to obtain the transfer function of the Advanced Neutron Source reactor and the time delay between the core power production and the external detectors, a parameter of interest to the safety systems design. The good agreement between the Monte Carlo generated transfer function and the point kinetics transfer function validates that the uncommon ANS geometry does not preclude the use of point kinetics in the frequency range that was investigated. Various features of the power spectral densities also demonstrated the applicability of point kinetics. The time delay was obtained from the cross-power spectral density (CPSD) and is {approximately}15 ms. These analyses show that frequency analysis can be used experimentally to investigate ...

1995-06-01

229

Investigation of thermohydraulic processes in steam generators for nuclear power stations equipped with VVER reactors  

British Library Electronic Table of Contents (United Kingdom)

The results obtained from experimental investigations and mathematical simulation of horizontal steam generators are considered. Recommendations for continuing these works are given.

2006-01-01

231

Human factors  

Energy Technology Data Exchange (ETDEWEB)

This is a presentation on Human Factors in reactor operations. It discusses issues that deal with power plant operations, training and design, operational effectiveness and safety, supporting people to achieve effective and error free performance.

2002-07-01

233

A compilation of reports of the Advisory Committee on reactor safeguards. 1996 Annual report  

Energy Technology Data Exchange (ETDEWEB)

This compilation contains 47 ACRS reports submitted to the Commission, or to the Executive Director for Operations, during calendar year 1996. It also includes a report to the Congress on the NRC Safety Research Program. All reports have been made available to the public through the NRC Public Document Room, the U.S. Library of Congress, and the Internet at http://www.nrc.gov/ACRSACNW. The reports are divided into two groups: Part 1 contains ACRS reports by project name and by chronological order within project name. Part 2 categorizes the reports by the most appropriate generic subject area and by chronological order within subject area.

1997-04-01

234

Safety System Design Concept and Performance Evaluation for a Long Operating Cycle Simplified Boiling Water Reactor  

Science.gov (United States)

The long operating cycle simplified boiling water reactor is a reactor concept that pursues both safety and the economy by employing a natural circulation reactor core without a refueling, a passive decay heat removal, and an integrated building for the reactor and turbine. Throughout the entire spectrum of the design basis accident, the reactor core is kept covered by the passive emergency core cooling system. The decay heat is removed by the conventional active low-pressure residual heat removal system. As for a postulated severe accident, the suppression pool water floods the lower part of the reactor pressure vessel (RPV) in the case when core damage occurs, and the in-vessel retention that keeps the melt inside the RPV is achieved by supplying the coolant. The containment adopts a parallel-double-steel-plate structure similar to a hull ...

2003-07-15

235

Tucannon River Spring Chinook Captive Broodstock Program Final Environmental Assessment and Finding of No Significant Impact  

Energy Technology Data Exchange (ETDEWEB)

Bonneville Power Administration (BPA) is proposing to fund the Tucannon River Spring Chinook Captive Broodstock Program, a small-scale production initiative designed to increase numbers of a weak but potentially recoverable population of spring chinook salmon in the Tucannon River in the State of Washington. BPA has prepared an Environmental Assessment (EA) (DOE/EA-l326) evaluating the proposed project. Based on the analysis in the EA, BPA 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) of 1969. Therefore, the preparation of an Environmental Impact Statement (EIS) is not required, and BPA is issuing this Finding of No Significant Impact (FONSI).

2000-05-24

236

Hanford Cultural Resources Laboratory annual report for fiscal year 1990  

Energy Technology Data Exchange (ETDEWEB)

The Hanford Cultural Resources Laboratory (HCRL) was established by the US Department of Energy Field Office, Richland (RL) in 1987 as part of Pacific Northwest Laboratory. The HCRL provides support for managing the archaeological, historical, and cultural resources of the Hanford Site, Washington, in a manner consistent with federal statutes and regulations. This report summarizes activities of the HCRL during fiscal year (FY) 1990. The HCRL responsibilities have been set forth in the Hanford Cultural Resources Management Plan (HCRMP) as a prioritized list of tasks. The task list guided cultural resources management activities during FY 1990 and is the outline for this report. In order, these tasks were to (1) conduct cultural resource reviews, (2) develop an archaeological resources protection plan, (3) monitor the condition of known archaeological sites, (4) plan a curation system for artifacts and records, (5) evaluate cultural resources for potential ...

1991-11-01

237

Environmental Restoration Remedial Action quality assurance requirements document  

International Nuclear Information System (INIS)

This document defines the quality assurance requirements for the US Department of Energy-Richland Operations Office Environmental Restoration Remedial Action program at the Hanford Site. The Environmental Restoration Remedial Action program implements significant commitments made by the US Department of Energy in the Hanford Federal Facility Agreement and Consent Order entered into with the Washington State Department of Ecology and the US Environmental Protection Agency. This document combines quality assurance requirements from various source documents into one set of requirements for use by the US Department of Energy-Richland Operations Office and other Environmental Restoration Remedial Action program participants. This document will serve as the basis for developing Quality Assurance Program Plans and implementing procedures by the participants. The requirements of this document will be applied to activities affecting quality, using a graded approach based on ...

238

PWR primary circuit piping installation of Daya Bay Nuclear Power Plant  

International Nuclear Information System (INIS)

The installation procedure, the fabrication, fitting up, positioning, adjustment and welding of piping, examinations, hydrostatics testing and insulation of piping for reactor primary circuit piping of Daya Bay Nuclear power Plant are briefly described.

239

Canada in the world power market  

Energy Technology Data Exchange (ETDEWEB)

Canadian power and industrial projects world-wide are highlighted in this annual feature. A short section on the CANDU Wolsung Reactor in the Republic of Korea mentions that it went critical in November 1982 after taking only 60 months to complete.

1983-01-01

240

A compilation of reports of the Advisory Committee on Reactor Safeguards: 1991 annual. Volume 13  

Energy Technology Data Exchange (ETDEWEB)

This compilation contains 41 Advisory Committee on Reactor Safeguards (ACRS) reports submitted to the Commission, Executive Director for Operations, or to the Office of Nuclear Regulatory Research, during calendar year 1991. It also includes a report to the Congress on the NRC Safety Research Program. All reports have been made available to the public through the NRC Public Document Room and the US Library of Congress. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part 1 contains ACRS reports alphabetized by project name and by chronological order within project name. Part 2 categorizes the reports by the most appropriate generic subject area and by chronological order within subject area.

1992-04-01

241

A compilation of reports of the Advisory Committee on Reactor Safeguards: 1991 annual  

Energy Technology Data Exchange (ETDEWEB)

This compilation contains 41 Advisory Committee on Reactor Safeguards (ACRS) reports submitted to the Commission, Executive Director for Operations, or to the Office of Nuclear Regulatory Research, during calendar year 1991. It also includes a report to the Congress on the NRC Safety Research Program. All reports have been made available to the public through the NRC Public Document Room and the US Library of Congress. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part 1 contains ACRS reports alphabetized by project name and by chronological order within project name. Part 2 categorizes the reports by the most appropriate generic subject area and by chronological order within subject area.

1992-04-01

242

A compilation of reports of the Advisory Committee on Reactor Safeguards, 1990 annual  

Energy Technology Data Exchange (ETDEWEB)

This compilation contains 31 Advisory Committee on Reactor Safeguards (ACRS) reports submitted to the Commission or to the Executive Director for Operations during calendar year 1990. It also includes a report to the Congress on the NRC Safety Research Program. All reports have been made available to the public through the NRC Public Document Room and the US Library of Congress. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subject. Part 1 contains ACRS reports alphabetized by project name and by chronological order within project name. Part 2 categorizes the reports by the most appropriate generic subject area and by chronological order within subject area.

1991-04-01

243

Radionuclide Air Emissions Report for the Hanford Site Calendar year 1998  

Energy Technology Data Exchange (ETDEWEB)

This report documents radionuclide air emissions from the Hanford Site in I998 and the resulting effective dose equivalent to the maximally exposed individual (MEI) member of the public. The report has been prepared in accordance with the Code of Federal Regulations, Title 40, Protection of the Environment, Part 61, National Emission Standards for Hazardous Air Pollutants (40 CFR SI), Subpart H, ''National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities,'' and with the Washington Administrative Code Chapter 246-247, Radiation Protection--Air Emissions. The federal regulations in 40 CFR 61, Subpart H; require the measurement and reporting of radionuclides emitted from Department of Energy facilities and the resulting offsite dose from those emissions. A standard of 10 mrem/yr effective dose equivalent (EDE) is imposed on them. The EDE to the MEI due to ...

1999-06-15

244

HISTORICAL AMERICAN ENGINEERING RECORD - IDAHO NATIONAL ENGINEERING AND ENVIRONMENTAL LABORATORY, TEST AREA NORTH, HAER NO. ID-33-E  

Energy Technology Data Exchange (ETDEWEB)

Test Area North (TAN) was a site of the Aircraft Nuclear Propulsion (ANP) Project of the U.S. Air Force and the Atomic Energy Commission. Its Cold War mission was to develop a turbojet bomber propelled by nuclear power. The project was part of an arms race. Test activities took place in five areas at TAN. The Assembly & Maintenance area was a shop and hot cell complex. Nuclear tests ran at the Initial Engine Test area. Low-power test reactors operated at a third cluster. The fourth area was for Administration. A Flight Engine Test facility (hangar) was built to house the anticipated nuclear-powered aircraft. Experiments between 1955-1961 proved that a nuclear reactor could power a jet engine, but President John F. Kennedy canceled the project in March 1961. ANP facilities were adapted for new reactor projects, the most important of which ...

2005-02-01

245

Experimental 1 kW 20 cell PEFC stack  

Energy Technology Data Exchange (ETDEWEB)

A 20-cell PEFC stack was designed and built. Resin impregnated graphite was used as bipolar plate material. The air cooling of the stack was optimized by introducing high surface structures into the open space of the cooling plates. At {eta} (H{sub 2} LHV) = 0.5 a power of 880 W was obtained under conditions of low gas-pressures of 1.15 bar{sub a}. The auxiliary power for process air supply and cooling at 880 W power is less than 7% of the power output, indicating that the described system may be operated at a high efficiency. (author) 5 figs., 2 refs.

1999-08-01

246

IECEC '91; Proceedings of the 26th Intersociety Energy Conversion Engineering Conference, Boston, MA, Aug. 4-9, 1991. Vol. 2 - Aerospace power systems, conversion technologies  

International Nuclear Information System (INIS)

The present volume on energy and the environment discusses space power requirements, space power systems, space power systems hardware, space radioisotope systems, space solar arrays, space solar cells, space station power, and terrestrial applications of aerospace technology. Attention is given to NASA future space power requirements and issues, the design of a battery charger for the NASA EOS Space Platform, in situ carbon dioxide fixation on Mars, and a preliminary design update of the CRAF/Cassini Power Subsystem. Topics addressed include concentrator testing using projected images, solar power satellites and demonstraton platforms from nonterrestrial materials, a mass sensitivity analysis of lunar orbiting beam power systems, and a power-beaming-based infrastructure for space ...

1991-08-03

247

Biofuels for electricity and heating - obstacles for increased utilization  

International Nuclear Information System (INIS)

The aim of this report is to describe the present situation regarding biomass utilization in small power plants, 0.5 - 20 MW fuel power. Also discussed are the most important technical, economical and environmental conditions which may prevent a fast expansion of small biomass fueled power plants for generation of district heating in smaller networks and also for electric power generation. Biofuels means a reduction of the net emission of carbon dioxide, but emission of other compounds are not very well known for this size of power plants. There are only a few biofueled power plants in Sweden and only a couple with less than 20 MW power supplied. New concepts are under development but not much have been achieved during the most recent years. 25 refs, 10 figs, 9 tabs.

248

Heavy water leak due to fretting of DN tube  

International Nuclear Information System (INIS)

Wolsung nuclear power plant has experienced four occasions of reactor shutdown owing to heavy water leaks since its commercial operation. Among these heavy water leaks, only one case was acute and brought about reactor shutdown but the other cases listed below were chronic and repaired after manual reactor shutdown. (author). 4 tabs., 10 figs.

1989-06-04

249

Efficiency of preliminary transmutation of actinides before ultimate storage  

International Nuclear Information System (INIS)

The concept of preliminary transmutation of minor actinides before placement to the long-term storage is considered. The purpose of such preliminary transmutation before ultimate storage is to incinerate a part of actinides and to transform another part into new actinides providing low level of radiotoxicity accumulated in the storage. Modes of transmutation in reactors of PWR, PHWR (CANDU), and Superfenix types are compared. Among power reactors, heavy-water PHWR type reactor is most acceptable for preliminary transmutation. (author)

2003-04-20

250

Afterheat assessment for conceptual tokamak reactors  

International Nuclear Information System (INIS)

Afterheat represents an important consideration in design of conceptual fusion power reactors, particularly during normal or unplanned shutdown. Afterheat calculations have been undertaken for various generic designs, but with special reference to the Culham DEMO reactor. These calculations have included the redistribution of heating by gamma ray transport. Selected temperature response calculations have been undertaken. (author).

1987-12-01

251

Case studies: Experience in China [Factors affecting public and political acceptance for the implementation of geological disposal  

International Nuclear Information System (INIS)

China operates 10 nuclear power reactors and has 5 more under construction. A large extension of nuclear power is expected by 2020. Nuclear generated electricity accounts for 2% of the total electric power generation. The Chinese policy is to have spent fuel reprocessed in China. So, final disposal include vitrified waste and some CANDU spent fuel for direct disposal. There is a legal framework in place in China to manage HLW. The China Atomic Energy Authority (CAEA) has the responsibility for setting policy on HLW disposal and implementing the disposal programme, while the National Nuclear Safety Administration (NNSA) and the State Environment Protection Agency (SEPA) are the regulatory bodies, which are responsible for licensing and reviewing of environment impact assessment report. The China National Nuclear Corporation (CNNC) is considered to be the actual implementer, conducting the major ...

2007-10-01

252

Negative-ion based NBI system for JT-60U  

Energy Technology Data Exchange (ETDEWEB)

A 500 keV negative-ion based NBI system is under construction for NB current drive and plasma core heating in high density plasma in JT-60U. Part of the beamline and the high voltage power supply required for a verification test of an ion source was completed in March 1995. After having done a high potential test of the power supply, the negative-ion generation and acceleration tests started in June 1995 aiming at deuterium beams of 500 keV, 22A. In initial experiment, deuterium negative-ion beams of 410 keV, 6.1A (2.5 MW) for 0.2 sec, so far, have been achieved. This is the world highest D{sup {minus}} current and negative ion beam power. The construction of the total system will be completed by the beginning of 1996, and the beam injection will start in March 1996.

1995-12-31

253

Implementation of denitrification systems in power plants fueled with brown coal from Rhine region deposits  

Energy Technology Data Exchange (ETDEWEB)

Based on the air pollution values typical of brown coal furnaces the paper discusses pollution abatement measures on the part of fuel engineering and flue gas technology. Fuel engineering contributes to air pollution abatement by measures such as stepped air supply, stepped fuel supply and flue gas draw-in. Flue gas technology largely relies on measures such as the SCR method using different catalytic converters, the noncatalytic reduction of nitrogen oxides, the simultaneous separation of sulfur dioxides and nitrogen oxides, and the Denox-Luvo method. The paper concludes with remarks on the RWE brown coal power plant retrofitting scheme planning to have all power plants equipped with adequate denitrification systems until the end of 1989 at the latest. (orig./PW)

1987-05-01

254

Recent developments in the design of conceptual fusion reactors  

International Nuclear Information System (INIS)

Since the first round of conceptual fusion reactor designs in 1973 - 1974, there has been considerable progress in design improvement. Two recent tokamak designs of the Wisconsin and Culham groups, with increased plasma beta and wall loading (power density), lead to more compact reactors with easier maintenance. The Reference Theta-Pinch Reactor has undergone considerable upgrading in the design of the first wall insulator and blanket. In addition, a conceptual homopolar energy storage and transfer system has been designed. In the case of the mirror reactor, there are design changes toward improved modular construction and ease of handling, as well as improved direct converters. Conceptual designs of toroidal-multiple-mirror, liner-compression, and reverse-field pinch reactors are also discussed. A design is presented of a toroidal multiple-mirror ...

255

Solar aeroplane. Solair I: the answer for alternative flying  

Energy Technology Data Exchange (ETDEWEB)

In December 1980, Guenther Rochelt from Munich (FRG) managed the first flight in a solar aircraft. Energy was supplied by 2,500 solar cells with a rated power of 2.2 kW. Self-starting and flying were made possible by a special aircraft construction with an electromotor with a gross power of 1.8 and a rated voltage of 88 V.

1981-03-01

256

Development and application of technology-neutral safety requirements for the regulation of new nuclear power reactors  

International Nuclear Information System (INIS)

This paper explores the current trends in development of technology-neutral safety requirements to be used in the regulation of future nuclear power reactors and the role of the quantitative safety goals in the design of reactor safety systems. Establishing the requirements concerning the reliability of safety functions rather than on particular systems employed to achieve the functions, as well as the use of the recommendations of the International Commission on Radiological Protection (ICRP) on protection against potential exposure could form the basis of a technology-neutral framework for safety requirements on new reactor designs. Also it could contribute to international harmonisation of nuclear safety assessment practices as part of the licensing processes for future nuclear power plants. (author)

2009-10-12

257

Power systems for space exploration  

Energy Technology Data Exchange (ETDEWEB)

The Outreach Program was designed to solicit creative ideas from academia, research institutions, private enterprises, and the general public and is intended to be helpful in defining promising technical areas and program paths for more detailed study. To the Outreach Program, a number of power system concepts were proposed. In conclusion, there are a number of advanced concepts for space power and propulsion sources that deserve study if we want to expand our ability to not only explore space, but to utilize it. Advanced nuclear concepts and power beaming concepts are two areas worthy of detailed assessments.

1992-01-01

258

The role of small and medium reactors in the energy security of a country, IRIS example  

International Nuclear Information System (INIS)

Nuclear options for electricity generations are assessed in this paper. Probabilistic (stochastic) method is used for economic comparison of nuclear power plants, wind plants and natural gas fired plants. Optimal nuclear power plant size is also discussed. IRIS is presented as a representative of small and medium reactors

2009-05-26

259

Steam generator tube failures: experience with water-cooled nuclear power reactors during 1976  

International Nuclear Information System (INIS)

A survey was conducted of experience with steam generator tubes at nuclear power stations during 1976. Failures were reported at 25 out of 68 water-cooled reactors. The causes of these failures and the repair and inspection procedures designed to cope with them are summarized. Examination of the data indicates that corrosion was the major cause of steam generator tube failures. Improvements are needed in steam generator design, condenser integrity and secondary water chemistry control. (author).

1994-10-18

260

Atoms at work  

International Nuclear Information System (INIS)

This illustrated booklet describes the fission process; the use of uranium to produce power in nuclear power stations (and a brief explanation of the differences between the principal types of reactor); the formation of plutonium and fission products; radioactive wastes and their management; nuclear fusion and a conceptual fusion reactor; alpha, beta and gamma radiations; radioisotopes and their applications. (U.K.).

261

Apparatuses for the dissolution of dioxide nuclear fuel of power reactors  

International Nuclear Information System (INIS)

A brief review of apparatuses used at enterprises engaged in industrial processing of spent nuclear fuel for dissolving dioxide nuclear fuel from power reactors is provided. Advantages and drawbacks of facilities operating in periodic, semi-continuous and continuous modes are considered. It is pointed out that today there are two promising trends in developments in the field, i.e. rotor- and vibrational-type dissolving apparatuses operated continuously

262

Tritium bioassay and dosimetry at a CANDU reactors  

Energy Technology Data Exchange (ETDEWEB)

Tritium dose management is an important aspect of the radiation protection program at CANDU type reactor sites. This paper describes the bioassay and dosimetry of tritium at CANDU reactor sites, especially for Wolsung Nuclear Power Plant. It presents a compilation of information drawn from published papers, technical reports, international and national guidelines as well as practical experience both in Korean and Canadian CANDU Nuclear Power Plants. The implementation of this program would provide a technical basis for calculations and records should be of acceptable quality and should meet overall radiation protection program objectives.

1996-07-01

263

Non-linear mathematical model of dynamics of horizontal steam generator for nuclear power unit with pressurized water reactor  

International Nuclear Information System (INIS)

A non-linear mathematical model of dynamics of horizontal steam generator for nuclear power unit with WWER type reactor is presented. To realize this model the GEMMA-120 simulation language for computer Odra-1204 has been used. Necessity of taking into account disposited thermal storage capacities along tubulation of a primary cycle is demonstrated. A number of lumped elements of reactor division against a required static accuracy of calculations has been determined. (author).

1977-01-01

264

Multi-megawatt space power reactors  

Energy Technology Data Exchange (ETDEWEB)

In response to the need of the Strategic Defence Initiative (SDI) and long range space exploration and extra-terrestrial basing by the National Air and Space Administration (NASA), concepts for nuclear power systems in the multi-megawatt levels are being evaluated. The requirements for these power systems are being driven primarily by the need to minimize weight and maximize safety and reliability. This paper discusses the present requirements for space based advanced power systems, technological issues associated with the development of these advanced nuclear power systems, and some of the concepts proposed for generating large amounts of power in space. (author).

1990-01-01

265

Policy implications of funding DOE's K Reactor Cooling tower Project  

Energy Technology Data Exchange (ETDEWEB)

This report has reviewed the construction of a cooling tower for the K reactor at the DOE Savannah River Site in Aiken, South Carolina. It has been found that the cooling tower would prevent further destruction of cypress and tupelo trees, would maintain a more consistent flow from site streams, and would allow earlier recovery of stream corridors inside a portion of the site. About 630 acres of wetlands have already been affected by the hot water discharged by the K reactor during the past 35 years. GAO believes that about 10 to 12 acres of additional damage would be prevented by the tower for every year the reactor is operated, and if current plans for re-start and retirement of the reactor are followed, less than 100 acres would be preserved. As requested, GAO also identified an example of a project that could be funded as compensation to the public for the damage the K ...

1989-10-01

266

Use of the River Saale cascade in terms of energy supply and water control. Energetische und wasserwirtchaftliche Nutzung der Saale-Kaskade  

Energy Technology Data Exchange (ETDEWEB)

The river Saale cascade consists of seven reservoirs with a total capacity of approx. 415 Mio. m[sup 3]. The entire reservoir system covers a catchment area of 1665 km[sup 2]. The water management tasks extend to the following main fields: flood protection upkeep of minimum water stock, salt load control and power generation. The energy supply capacity of the cascade is mainly used by pumped storage plants. The last of these plants, Hohenwarte II, was put into service in 1963. (orig.)

1993-01-01

267

An impending platinum crisis and its implications for the future of the automobile  

International Nuclear Information System (INIS)

The global demand for platinum has consistently outgrown supply in the past decade. This trend likely will continue and the imbalance may possibly escalate into a crisis. Platinum plays pivotal roles in both conventional automobile emissions control and the envisioned hydrogen economy. A platinum crisis would have profound implications on energy and environment. On the one hand, inadequate platinum supply will prevent widespread commercialization of hydrogen fuel-cell vehicles. On the other hand, expensive platinum may enhance the competitiveness of hybrid, plug-in hybrid, and battery-powered electric cars. Policymakers should weigh the potential impacts of a platinum crisis in energy policy.

2009-05-01

268

Instruments for X-ray fluorescence analysis and spectrometry  

International Nuclear Information System (INIS)

The radionuclide X-ray fluorescence analyzer consists of a source changer and a sample changer. "5"5Fe, "1"0"9Cd and "2"4"1Am are used as excitation sources. The radiation is detected with a semiconductor Si(Li) detector. The complete assembly of the apparatus consists of an imagine unit, a keyboard, a floppy disc drive, a printer, a console and a rack with analog and digital electronics. Its multichannel amplitude analyzer consists of power supplies, a high voltage supply, a linear amplifier, an analog-to-digital converter and a computer. The technical specifications are given. The control and data processing system is controlled with an MHB 8080A microprocessor. Software for semiconductor gamma spectrometry and for quantitative gamma spectrometry will be supplied with the equipment. (E.S.). 3 figs., 4 refs.

269

Cooling facility for reactor container  

International Nuclear Information System (INIS)

Cooling water is sprayed on the outer surface of an upper portion of a container, and a pool is formed by the cooling water flowing down while cooling the container. Further, the cooling water stored in the cooling water pool is recycled by a pump for spraying the cooling water on the outer surface of the upper portion of the container. Sufficient amount of cooling water is supplied for spraying the cooling water to the outer surface of the upper portion of the container so that the outer surface of the container is free from drying and a liquid membrane is formed on the entire surface. The amount of the cooling water is made greater than that of the cooling water evaporated when the entire amount of the heat generate in the reactor core of the reactor is transferred to the cooling water. Since the liquid membrane is formed on the entire surface of the container with no drying of the outer surface, the area of cooling ...

1993-05-07

270

The SBWR (simplified boiling water reactor) thermal-hydraulic performance analysis and testing  

Science.gov (United States)

Utility interest has recently increased in potential future nuclear units that combine the characteristics of smaller size, greater simplicity, and more passive safety features. In response to such interest, General Electric (GE) began development in 1982 of a 600-MW(electric) reactor with simplified power generation and safety systems. This paper provides an overview of the simplified boiling water reactor (SBWR) design, with emphasis on the thermal-hydraulic aspects of the design. The SBWR is a natural circulation reactor requiring no pumps to circulate the water through the core.

1989-11-01

271

Investigation of FP paths during hypothetical severe accident as a result of Small Break LOCA of WWER-1000 reactor type  

International Nuclear Information System (INIS)

Modelling the behaviour of fission product (FP) in a nuclear reactor coolant system (RCS) undergoing a hypothetical severe accident is an important step in the evaluation of radioactive release outside a nuclear power plant. This paper scrutinize Small Break LOCA sequence for WWER1000 reactor in order to investigate the possible paths for release of FP from fuel pallets to the reactor containment. Contemporaneous computer code for simulation of RCS will be use for the analysis. The results from analysis of fuel damage and release of FP trough the break of cold leg are present. (author)

2006-04-01

272

Directions for improved fusion reactors  

International Nuclear Information System (INIS)

Conceptual fusion reactor studies over the past 10 to 15 years have projected systems that may be too large, complex, and costly to be of commercial interest. One main direction for improved fusion reactors points towards smaller, higher-power-density approaches. First-order economic issues (i.e., unit direct cost and cost of electricity) are used to support the need for more compact fusion reactors. A generic fusion physics/engineering/costing model is used to provide a quantiative basis for these arguments for specific fusion concepts.

273

Status report on the fusion breeder  

Energy Technology Data Exchange (ETDEWEB)

The rationale for hybrid fusion-fission reactors is the production of fissile fuel for fission reactors. A new class of reactor, the fission-suppressed hybrid promises unusually good safety features as well as the ability to support 25 light-water reactors of the same nuclear power rating, or even more high-conversion-ratio reactors such as the heavy-water type. One 4000-MW nuclear hybrid can produce 7200 kg of /sup 233/U per year. To obtain good economics, injector efficiency times plasma gain (eta/sub i/Q) should be greater than 2, the wall load should be greater than 1 MW m/sup -2/, and the hybrid should cost less than 6 times the cost of a light-water reactor. Introduction rates for the fission-suppressed hybrid are unusually rapid.

1980-12-12

274

Space reactor fuel element testing in upgraded TREAT  

Energy Technology Data Exchange (ETDEWEB)

The testing of candidate fuel elements at prototypic operating conditions with respect to temperature, power density, hydrogen coolant flow rate, etc., a crucial component in the development and qualification of nuclear rocket engines based on the Particle Bed Reactor (PBR), NERVA-derivative, and other concepts. Such testing may be performed at existing reactors, or at new facilities. A scoping study has been performed to assess the feasibility of testing PBR based fuel elements at the TREAT reactor. initial results suggest that full-scale PBR, elements could be tested at an average energy deposition of {approximately}60--80 MW-s/L in the current TREAT reactor. If the TREAT reactor was upgraded to include fuel elements with a higher temperature limit, average energy deposition of {approximately}100 MW/L may be achievable.

1993-05-01

275

Laser application in the fabrication of gas-tagged capsules. A leak detection system  

Energy Technology Data Exchange (ETDEWEB)

Encapsulation of a unique isotopic blend of krypton and xenon gas employs a special application of laser technology. The encapsulated gas is then used as the primary medium for detection and identification of failed nuclear fuel rods. The use of gas tagging as a means of detecting and identifying failed nuclear fuel rods has been successfully demonstrated and used by the Argonne National Laboratory, Experimental Breeder Reactor (EBR-2) Project, and the Westinghouse Hanford Company (WHC), Fast Flux Test Facility (FFTF) Fast Breeder Reactor Program. The Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan has selected this leak detection system for use in their MONJU Prototype Reactor fuel assemblies. The MONJU reactor is almost identical in design to the highly successful FFTF reactor, which is currently in standby status.

1993-12-01

276

High-power operation of heterobarrier blocking structure InGaAlP visible light laser diodes  

Energy Technology Data Exchange (ETDEWEB)

Heterobarrier blocking structure InGaAlP visible light laser diodes employing a thin active layer (0.04 {mu}m) and asymmetry coatings have been fabricated. The high light-output power operation with this heterobarrier blocking structure was investigated. The light-output power versus cw current curve was linear up to 43 mW and a maximum light output power of 51 mW was obtained. A high-power operation such as 20 mW was maintained at 40 {degree}C. Stable oscillation in the fundamental transverse mode was obtained up to 30 mW. These results show that this heterobarrier blocking structure supplies a sufficient current confinement effect even under a high-light output power operation.

1990-04-30

277

Secretary of State Clinton Photos: July  

Science.gov (United States)

Washington, DC -07/24/09 Photo: Secretary Clinton and Iraqi Prime Minister al-Maliki at HCC Bilateral; Washington, DC -07/24/09 Photo: Secretary Clinton at Joint Press...

2011-09-18

278

TRIMPWR: A post processor for TRIMHX  

Energy Technology Data Exchange (ETDEWEB)

The TRIMPWR code has been developed as a post processor for TRIMHX (transient 3D diffusion code) in support of the reactor limits program. TRIMPWR is designed to produce JOSHUA files containing: core power as a function of time, assembly power by hex as a function of time, assembly power post peaking as a function of time, and axial power shapes for each assembly as a function of time (formatted for use by the FLOWTRAN code) from the output of a TRIMHX run. In an attempt to simplify the reactor limits process by reducing the number of assemblies which must be run through FLOWTRAN, TRIMPWR also sorts the assemblies by the product of the power post peaking and the maximum normalized axial power density for each assembly. This follows from the assumption that those assemblies having the maximum value of this product will ...

1989-11-01

279

Large-scale integration of optimal combinations of PV, wind and wave power into the electricity supply  

Energy Technology Data Exchange (ETDEWEB)

This article presents the results of analyses of large-scale integration of wind power, photo voltaic (PV) and wave power into a Danish reference energy system. The possibility of integrating Renewable Energy Sources (RES) into the electricity supply is expressed in terms of the ability to avoid excess electricity production. The different sources are analysed in the range of an electricity production from 0 to 100% of the electricity demand. The excess production is found from detailed energy system analyses on the computer model EnergyPLAN. The analyses have taken into account that certain ancillary services are needed in order to secure the electricity supply system. The idea is to benefit from the different patterns in the fluctuations of different renewable sources. And the purpose is to identify optimal mixtures from a technical point of view. The optimal mixture seems to be when onshore wind ...

2006-04-01

280

Safety and environment tritium problems in a tokamak reactor optimization of workers and public protection and the robotics challenge  

International Nuclear Information System (INIS)

The philosophy of containing tritium and activated products very close to the source and of operating by remote techniques is justified by a comparison with other concepts on protection and availability points of view. Several design options are studied according to the optimization protection methodology of ICRP. Provided that an important technological development is accomplished, the utilization of robotics and the limitation of containment volumes should be generalized.

1983-04-26

281

Review and evaluation of the Nuclear Regulatory Commission safety research program for Fiscal Year 1983. Report to the Congress  

Energy Technology Data Exchange (ETDEWEB)

Public Law 95-209 includes a requirement that the Advisory Committee on Reactor Safeguards submit an annual report to Congress on the safety research program of the Nuclear Regulatory Commission. This report presents the results of the ACRS review and evaluation of the NRC safety research program for Fiscal Year 1983. The report contains a number of comments and recommendations.

1982-02-01

282

Review and evaluation of the Nuclear Regulatory Commission safety research program for Fiscal Year 1982. Report to the Congress  

Energy Technology Data Exchange (ETDEWEB)

Public Law 95-209 includes a requirement that the Advisory Committee on Reactor Safeguards submit an annual report to Congress on the safety research program of the Nuclear Regulatory Commission. This report presents the results of the ACRS review and evaluation of the NRC safety research program for Fiscal Year 1982. The report contains a number of comments and recommendations.

1981-02-01

283

Radiation protection in connection with the decommissioning of nuclear plants  

Energy Technology Data Exchange (ETDEWEB)

This document presents the SSI preliminary views and position concerning the decommissioning of nuclear plants. To prevent the exposure of the decommissioning personnel and the general public to unacceptable levels of radiation and to protect the environment and future generations, it is SSI`s task to formulate and issue the necessary terms and regulations with which the reactor licensees must comply during the decommissioning work. The views and principles presented here are the basis of SSI`s continued work on guidelines and regulations for the decommissioning of nuclear plants.

1997-04-01

284

Britain's first pressurised-water reactor  

Energy Technology Data Exchange (ETDEWEB)

The recent announcement that the public inquiry into the CEGB's plans to build a PWR at Sizewell will begin in January 1983 and the statement which followed from the task force that was set up in July 1981 to consider the future of the PWR programme in the UK, are considered. The relevant time scales, costs and safety, in particular the cost incurred due to the added safety features for the British PWR, are discussed. The effect of political aspects on the future of the PWR in Britain is considered.

1982-01-28

285

A techno-economic comparison of spark ignition engine versus solid polymer fuel cell power systems for utility vehicles  

Energy Technology Data Exchange (ETDEWEB)

Solid polymer fuel cell (SPFC) systems are compared to spark ignition (SI) engine power systems for utility vehicle applications. Utility vehicles provide crew and payload transport and electrical power at work sites lacking grid supply. The methodology emphasizes comparison on an equal service basis. Using power system component models and numerical analysis, power systems are designed using SI engine and SPFC technologies. The power systems are compared on the basis of fuel energy consumed and life cycle cost (LCC). Gasoline is the fuel for the SI engines, while liquid hydrogen is used for the SPFC. Three types of SPFC power system configurations are studied. The superior SPFC in terms of LCC is a fuel cell/battery hybrid where the fuel cell is sized to provide average driving power. Using today's technology, ...

1992-01-01

286

Paul Scherrer Institut Scientific Report 2001. Volume V: General Energy  

Energy Technology Data Exchange (ETDEWEB)

Major advances in 'Energy and Materials Cycles' have been achieved in the removal of heavy metals from the solid residues of municipal waste incineration. It has been conclusively shown that the oxidation/reduction conditions established during the thermal treatment of filter ash have a decisive influence on the evaporation of groups of heavy metals. With respect to biomass gasification, studies have been carried out with respect to the best way of extracting pure hydrogen from the low calorific value gas that is typically obtained from a biomass gasifier. The overarching goal of the laboratory 'High Temperature Solar Technology' is the use of solar energy for the production of solar fuels, or for the reduction of CO{sub 2} emissions in large scale industrial processes that are conventionally carried out with the use of fossil fuels. In a short-term project targeted at the solar production of lime, highly encouraging results (98% degree of ...

2002-03-01

287

Status of the ANS low power and shutdown PRA standard  

Energy Technology Data Exchange (ETDEWEB)

The Low Power and Shutdown (LPSD) PRA (Probabilistic Risk Assessment) Standard (ANS-58.22) is currently being drafted by a Writing Group under the auspices of the Risk Informed Standards Committee of the American Nuclear Society (ANS). The Writing Group includes representatives from nuclear utilities, US Nuclear Regulatory Commission (NRC), national laboratories, universities, and consultants with substantial experience producing LPSD PRAs. This draft standard is scheduled to be released for public comment in the second quarter of 2004, with publication by the end of 2004. The LPSD PRA Standard is based on a mature technology that shares many requirements with full power PRAs. It will provide specific methods and criteria whereby PRAs of appropriate quality and scope can be used in the conduct of plant decision-making and other activities, including addressing NRC requirements. This paper presents the ...

2004-07-01

288

Radioactive source management in Daya Bay NPP  

International Nuclear Information System (INIS)

'Small radioactive source results in big accident' have occurred repeatedly in China and worldwide alike. Radioactive source management is one of the key activities for a nuclear power plant to maintain its good safety record and image to the public. From aspects of establishing the management system, centralized storage, periodic accounting, performing whole process control to the source usage and experience feedback etc., the author reports the practice and experience of radioactive source management in Daya Bay Nuclear Power Plant

1999-11-01

289

Wien Automatic System Planning (WASP) Package. A computer code for power generating system expansion planning. Version WASP-IV. User's manual  

International Nuclear Information System (INIS)

As a continuation of its efforts to provide methodologies and tools to Member States to carry out comparative assessment and analyse priority environmental issues related to the development of the electric power sector, the IAEA has completed a new version of the Wien Automatic System Planning (WASP) Package WASP-IV for carrying out power generation expansion planning taking into consideration fuel availability and environmental constraints. This manual constitutes a part of this work and aims to provide users with a guide to use effectively the new version of the model WASP-IV. WASP was originally developed in 1972 by the Tennessee Valley Authority and the Oak Ridge National Laboratory in the USA to meet the IAEA needs to analyse the economic competitiveness of nuclear power in comparison to other generation expansion alternatives for supplying the future electricity requirements of a country or ...

1997-12-01

290

PWM applications for the electric railway traction system fed by the AC/DC dual power line  

Energy Technology Data Exchange (ETDEWEB)

The latest electronic circuit technology that can be used for the electric railway traction system fed by an AC/DC dual power line was developed. This system consists of reverse conducting GTO thyristors, microprocessors, and DSP`s. In the AC power supply line section, the line converter is controlled by PWM technology to secure a high power factor and reduce the higher harmonic generation of an input current as far as possible. The line converter and motor converter use reverse conducting GTO thyristors. Since these converters are cooled using a heat pipe cooler, they are reduced in size and weight. The electric grounding point of the main power circuit is set to the negative side of the DC line for AC and DC line sections. Therefore, the AC/DC selector switch was simplified in structure. Moreover, the DC input for the auxiliary power ...

1996-01-01

291

MOX in reactors: present and future  

International Nuclear Information System (INIS)

In Europe, MOX fuel has been supplied by AREVA for more than 30 years, to 36 reactors: 21 in France, 10 in Germany, 3 in Switzerland, 2 in Belgium. For the present and future, recycling is compulsory in the frame of sustainable development of nuclear energy. By 2030 the overall volume of used fuel will reach about 400 000 t worldwide. Their plutonium and uranium content represents a huge resource of energy to recycle. That is the reason why, the European Utilities issued an EUR (European Utilities Requirement) demanding new builds reactors to be able of using MOX Fuel Assemblies in up to 50 % of the core. AREVA GEN3+ reactors, like EPR"T"M or ATMEA"T"M designed with MHI partnership, are designed to answer any utility need of MOX recycling. The example of the EPR"T"M reactor operated with 100 % MOX core optimized for MOX recycling will be presented. A standard EPR"T"M can be operated ...

292

Fast breeder reactor safety : a perspective  

International Nuclear Information System (INIS)

Taking into consideration India's limited reserves of natural and vast reserves of thorium, the fast reactor route holds a great promise for India's energy supply in future. The fast reactor fueled with "2"3"9Pu/"2"3"8U (unused or depleted) produces (breeds) more fissionable fuel material "2"3"9Pu than it consumes. Calculations show that a fast breeder reactor (FBR) increases energy potential of natural uranium by about 60 times. As the fast reactor can also convert "2"3"2Th into "2"3"3U which is a fissionable material, it can make India's thorium reserves a source of almost inexhaustible energy supply for a long time to come. Significant advantage of FBR plants cooled by sodium and their world-wide operating experience are reviewed. There are two main safety issues of FBR, one nuclear and the other non-nuclear. The nuclear issue concerns core disruptive ...

293

Evaluation of ROP Margin Effectiveness by REFORM Region  

Energy Technology Data Exchange (ETDEWEB)

In CANDU reactors, the Regional Overpower Protection Trip (ROPT) system protects the reactor against overpowers in the reactor fuel, whether due to localized peaking within the core or a general increase in core power levels. Due to Primary Heat-Transport System (PHTS) aging the ROP trip setpoint is decreasing over time. Reductions in ROP trip setpoints are required to maintain the required trip-probability and ROP trip effectiveness, and results in a decrease of the ROP margin-to-trip during normal operation. In addition, full power operation can be threatened. In this point, to recover ROPT margin, channel power needs to be redistributed. ROPT setpoint is very conservative in normal operation because distortion of regional overpower is over 1.2 times as nominal power in slow loss of regulation (SLOR). Channel power ...

2007-07-01

294

The development of the high-temperature reactor. In memoriam Prof. Dr. rer.nat. Dr.-Ing. e.h. Rudolf Schulten; Die Entwicklung des Hochtemperaturreaktors. Zum Tode von Prof. Dr. rer.nat. Dr.-Ing. e.h. Rudolf Schulten  

Energy Technology Data Exchange (ETDEWEB)

In the future even more than in the past, nuclear power will be indispensable in the present industrialized countries and in those still under development. The safe, nonpolluting, and economic supply of energy to mankind in the future includes so many different problems that the technology of the high-temperature reactor at its present level of development, and with the possibilities is offers above and beyond those provided by other, established, technologies, does not have to mark the end of some old line of development, but rather should be seen as the starting point of a development offering promise for the future. It is for this very reason that the extensive, valuable knowledge and experience accumulated in the construction, operation, and decommissioning of the AVR and THTR plants, the development of the HTR module and other variants and, last, but not least, the valuable results of projects such as PNP, NFE, and ...

1996-08-01

295

Assessment of RELAP5 model for the University of Massachusetts Lowell research reactor  

International Nuclear Information System (INIS)

RELAP5 (Reactor Excursion and Leak Analysis Program) is a system code developed at the Idaho National Environmental and Engineering Laboratory for thermal hydraulic analysis of nuclear reactors. The code RELAP5 is widely used for safety analysis studies of commercial nuclear power plants. However, recent released version of RELAP5/3.2 and over present significant capabilities for analysis of nuclear reactor research systems. As a contribution to the assessment of RELAP5/3.3 for research reactor safety analysis, experimental data from the University of Massachusetts Lowell Research Reactor UMLRR are used. The UMLRR is a 1 MW, light water moderated and cooled, graphite-reflected, open-pool type research reactor. This paper presents the development and the validation of a UMLRR-RELAP model using experimental data. For this purpose, a series of ...

296

Mergers in the power supply sector. Empirical analysis of mergers in the nineties in North America and Europe; Unternehmenszusammenschluesse in der Energieversorgung. Empirische Analyse der Uebernahmewelle der 1990er Jahre in Nordamerika und Europa  

Energy Technology Data Exchange (ETDEWEB)

The author investigates the effects of 529 mergers in the European and North American power industries between 1990 and 2002. The focus is on the effects on the capital market and the changes in the utilities' performance in successive years. It is assumed that as a rule mergers resulted in a lower value of the companies concerned. On the other hand, the target businesses appear to have obtained added value in the same period. Apart from the fight for market power, the author identifies especially financial synergies as an important motive. (orig.)

2006-07-01

297

Kinetics of reduction of iron oxides using microwaves as power source  

Energy Technology Data Exchange (ETDEWEB)

This work deals with kinetic description of carbothermic reduction of iron oxides using microwaves as power source. Previous researches show that it is possible to conduct this kind of process successfully, but real kinetic comparisons between conventional and microwaves procedure have been presented partially. The aim of this work is to describe reduction kinetics, taking into account how the iron oxide is reduced by microwaves compared with conventional energy supply. In this study the authors used iron ore in pellet shape and dust. They found that both, pellet and dust reduction stops when it reaches approximately 40%, even at whole power.

1996-12-31

298

Support vector machines for nuclear reactor state estimation  

Energy Technology Data Exchange (ETDEWEB)

Validation of nuclear power reactor signals is often performed by comparing signal prototypes with the actual reactor signals. The signal prototypes are often computed based on empirical data. The implementation of an estimation algorithm which can make predictions on limited data is an important issue. A new machine learning algorithm called support vector machines (SVMS) recently developed by Vladimir Vapnik and his coworkers enables a high level of generalization with finite high-dimensional data. The improved generalization in comparison with standard methods like neural networks is due mainly to the following characteristics of the method. The input data space is transformed into a high-dimensional feature space using a kernel function, and the learning problem is formulated as a convex quadratic programming problem with a unique solution. In this paper the authors have applied the SVM method for data-based state ...

2000-02-14

299

A novel concept for CRIEC-driven subcritical research reactors  

Energy Technology Data Exchange (ETDEWEB)

A novel scheme is proposed to drive a low-power subcritical fuel assembly by means of a long Cylindrical Radially-convergent Inertial Electrostatic Confinement (CRIEC) used as a neutron source. The concept is inherently safe in the sense that the fuel assembly remains subcritical at all times. Previous work has been done for the possible implementation of CRIEC as a subcritical assembly driver for power reactors. However, it has been found that the present technology and stage of development of IEC-based neutron sources can not meet the neutron flux requirements to drive a system as big as a power reactor. Nevertheless, smaller systems, such as research and training reactors, could be successfully driven with levels of neutron flux that seem more reasonable to be achieved in the near future by IEC devices. The need for custom-made expensive nuclear fission fuel, ...

2001-07-01

300

Gamma and X-ray shielding compositions utilizing bauxite - Red Mud regional research laboratory (CSIR), Bhopal, India  

International Nuclear Information System (INIS)

Available in abstract form only. Full text of publication follows: The application spectrum of X-ray and Gamma radiation is increasing exponentially in the area of diagnostic, nuclear medicine, food preservation, nuclear power plants and strategic utilities. To prevent the harmful effects of these radiations, shielding materials based on lead metal and its compounds are being used historically, which are toxic in nature. To protect environment it has become necessary to develop non-toxic lead free shielding materials. The use of titanium metal and its compounds as synthetic rock i.e. SYNROC are reported to be very effective non-toxic shielding materials for various applications. Red mud waste generated in aluminum producing industries possesses a unique mineralogical compositions containing fairly high quantity of titanium oxide and iron oxide useful for making non toxic shielding compositions and therefore red mud has been utilized for the ...

2007-09-02

301

Development of the Decontamination Approach for the West Valley Demonstration Project Decontamination Project Plan  

Energy Technology Data Exchange (ETDEWEB)

This paper details the development of a decontamination approach for the West Valley Demonstration Project (WVDP), Decontamination Project Plan (Plan). The WVDP is operated by West Valley Nuclear Services Company (WVNSCO), a subsidiary of Westinghouse Government and Environmental Services, and its parent companies Washington Group International and British Nuclear Fuels Limited (BNFL). The WVDP is a waste management effort being conducted by the United States Department of Energy (DOE) at the site of the only commercial nuclear fuel reprocessing facility to have operated in the United States. This facility is part of the Western New York Nuclear Service Center (WNYNSC), which is owned by the New York State Energy Research and Development Authority (NYSERDA). As authorized by Congress in 1980 through the West Valley Demonstration Project Act (WVDP Act, Public Law 96-368), the DOE's primary mission at the WVDP is to solidify high-level ...

2002-02-25

302

High voltage transmission lines - what are the hazards  

International Nuclear Information System (INIS)

With the increasing use of high voltage alternating current (HVAC) transmission lines there is a growing concern among the public about possible human health effects resulting from exposure to the electric fields associated with these lines. While there is no definitive evidence of such effects, mounting public fear and activism over hypothesized health risks is already causing delays in the licensing and constuction of major power transmission facilities, and is encouraging the formation of regulatory policy. This paper briefly reviews the concerns, biological effects data and standards for HVAC transmission lines.

1984-07-01

303

Controlling the atom  

Energy Technology Data Exchange (ETDEWEB)

The authors trace the early history of nuclear power regulation in the US. Focusing on the Atomic Energy Commission, they describe the role of other groups that figured in the development of regulatory policies, including the Congressional Joint Committee on Atomic Energy, other federal agencies, state governments, the nuclear industry, and scientific organizations. They consider changes in public perceptions of and attitudes toward atomic energy and the dangers of radiation exposure. The basic purpose of the book is to provide the Nuclear Regulatory Commission and the general public with information on the historical antecedents and background of regulatory issues so that there will be continuity in policy decisions. The book concludes with an annotated bibliography of selected references. 19 figures.

1984-01-01

304

Renewable energy technology for off-grid power generation solar hybrid system  

International Nuclear Information System (INIS)

Off-grid power generation is meant to supply remote or rural area, where grid connection is almost impossible in terms of cost and geography, such as island, aborigine's villages, and areas where nature preservation is concern. Harnessing an abundance renewable energy sources using versatile hybrid power systems can offer the best, least-cost alternative solution for extending modern energy services to remote and isolated communities. The conventional method for off-grid power generation is using diesel generator with a renewable energy (RE) technology utilizing solar photovoltaic, wind, biomass, biogas and/or mini/micro hydro. A hybrid technology is a combination of multiple source of energy; such as RE and diesel generator and may also include energy storage such as battery. In our design, the concept of solar hybrid system is a combination of solar with diesel genset and battery as an energy storage. ...

2006-12-01

305

How an IPO Helps in M&A  

British Library Electronic Table of Contents (United Kingdom)

An initial public offering (IPO) can often provide a powerful stimulus to private companies seeking to pursue an acquisition-driven growth strategy. Based on a comprehensive analysis of U.S. IPOs, the authors show that newly public companies are prolific acquirers. Over 30% of companies conducting an IPO make at least one acquisition in their IPO year, and the typical IPO firm makes about four acquisitions during its first five years as a public company. IPOs facilitate M&A not only by providing infusions of capital but also by creating ongoing access to equity and debt markets for cash-financed deals. In addition, IPOs create an acquisition currency that can prove valuable in stock-financed deals when the shares are attractively priced. The authors also argue that IPOs improve the ability...

2010-01-01

306

Consuming for production - Procurement for power production at Cernavoda NPP - Nuclear Sector  

International Nuclear Information System (INIS)

The paper presents some aspects relating to the importance of a good communication and cooperation between all factors involved in procurement process at Societatea Nationala 'Nuclearelectrica', SNN. In order to comply with the internal and international rules related to safety in nuclear field and public procurement requirements and for maintaining a high standard of operational performance of Cernavoda NPP, adequate procurement systems were developed by SNN SA. The importance of human factor and the training activities for all personnel from this chain of procurement process is the main key issue to maintain high quality of their activities considering that procurement documents are reviewed and approved before to be issued by all departments involved in procurement process. The specialized department for public acquisition is supervising that the procurement processes initiated at the level of branches, in accordance with their needs and ...

2009-10-12

307

Alteration of installation of reactors (alteration of No. 1 and No. 2 reactor facilities) in the Sendai Nuclear Power Station, Kyushu Electric Power Co. , Inc  

Energy Technology Data Exchange (ETDEWEB)

The Nuclear Safety Commission presented the report to the Minister of International Trade and Industry on April 5, 1984, after the careful investigation and deliberation on the alteration of installation of No.1 and No.2 reactor facilities in the Sendai Nuclear Power Station. The technical capability of Kyushu Electric Power Co., Inc., was recognized to be adequate. It was judged that the safety after this alteration of installation of the reactor facilities can be ensured. The main items of examination were as follows. The mechanical, nuclear and thermo-hydraulic designs of 17 x 17 B-type fuel assemblies were regarded as adequate. The coexistence of A-type and B-type fuel assemblies does not cause any problem about the safety. The safety at the time of abnormal transient change and accident in the mixed fuel assembly core was confirmed. In No.2 reactor, the degree of enrichment of ...

1984-08-01

308

Core reactor calculation using the adaptive remeshing with a current error estimator  

International Nuclear Information System (INIS)

With the objective to improve the reactor physics calculation on a 2D and 3D nuclear reactor via the Diffusion Equation, an adaptive automatic finite element remeshing method, based on the elementary area (2D) or volume (3D) constraints, has been developed. The adaptive remeshing technique, guided by a posteriori error estimator, makes use of two external mesh generator programs: Triangle and TetGen. The use of these free external finite element mesh generators and an adaptive remeshing technique based on the current field continuity show that they are powerful tools to improve the neutron flux distribution calculation and by consequence the power solution of the reactor core even though they have a minor influence on the critical coefficient of the calculated reactor core examples. Two numerical examples are presented: the 2D IAEA reactor ...

309

Status and trends of nuclear technologies - Report of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). Additional information (Companion CD-ROM)  

International Nuclear Information System (INIS)

The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was launched in the year 2000, based on a resolution by the IAEA General Conference (GC(44)/RES/21). INPRO intends to help to ensure that nuclear energy is available in the 21st century in a sustainable manner, and seeks to bring together all interested Member States, both technology holders and technology users, to consider, jointly, actions to achieve desired innovations. INPRO is taking care of the specific needs of developing countries. This IAEA publication is part of Phase 1 of INPRO. It intends to provide an overview on history, present situation and future perspectives of nuclear fuel cycle technologies. While this overview focuses on technical issues, nevertheless, the aspects of economics, environment, and safety and proliferation resistance are important background issues for this study. After a brief description about the INPRO project and an evaluation ...

1991-01-01

310

Modeling of a self-excited pulse combustor and stability analysis  

British Library Electronic Table of Contents (United Kingdom)

The major bottleneck for popularization and utilization of the conventional mechanical valve pulse combustors is the self-priming mode of gas supply. An aerodynamic valve (as against mechanical valve) self-excited pulse combustor of the Helmholtz-type with continuous supply of gas and air was designed and a mathematical model was established in this paper. The theoretical model employed well-stirred reactor model and a single step Arrhenius chemistry, and took those factors which might affect the combustion stability into account. The factors include the variation of the mass rate of the reactants affected by the pressure in the combustion chamber, the convective and radiation heat loss in the combustion chamber, and the heat transfer and wall friction in the tailpipe. The effect of wall t...

2011-01-01

311

The behavior of fission products during nuclear rocket reactor tests  

Energy Technology Data Exchange (ETDEWEB)

The experience base regarding fission product behavior developed during the Rover program, the nuclear rocket development program of 1955--1972, will be useful in planning a renewed nuclear rocket program. During the Rover program, 20 reactors were tested at the Nuclear Rocket Development Station in Nevada. Nineteen of these discharged effluent directly into the atmosphere; the last reactor tested, a non-flight-prototypic, fuel-element-testing reactor called the Nuclear Furnace (NF-1) was connected to an effluent cleanup system that removed fission products before the hydrogen coolant (propellant) was discharged to the atmosphere. In general, we are able to increase both test duration and fuel temperature during the test series. Therefore fission product data from the later part of the program are more interesting and more applicable to future reactors. We have collected fission product retention (and ...

1991-01-01

312

Technologies for Saving Energy in Railway Operation: General Discussion on Energy Issues Concerning Railway Technology  

British Library Electronic Table of Contents (United Kingdom)

Early technical history of electric supply to electric railways is briefly reviewed as an introduction to the following seven papers included in this special issue on technologies for saving energy in railway operation. Continuous power supply played a significant role in the early history of railway technologies. The variable voltage variable frequency (VVVF) power electronic technology had also a substantial impact on railway traction systems after 1980s. VVVF technology made it possible to have more efficient drives, downsize rolling stocks, and develop regenerative brakes. Because detailed discussions on each technical development are presented in the following papers, the general remarks of those technologies made in this introduction provide logical links to the ideas presented in th...

2010-01-01

313

Independent power plant using wood waste  

Energy Technology Data Exchange (ETDEWEB)

A 1 MWe power plant using waste wood fuel is to be installed at a US Marine Corps base, which will supply all wood from a landfill site. The core energy conversion technology is a down-draft gasifier supplying approximately 150 Btu/scf gas to both spark ignition and diesel dual-fuel engine-generator sets. Features of the plant design include: (1) grinding wood fuel from a wide range of waste resources, (2) specialized screening for fines removal, (3) complete tar and other waste product control without landfill disposal, and (4) use of process heat for bulk fuel drying, gasifier air pre-heating, and wastewater evaporation.

1995-08-01

314

Delta connected resonant snubber circuit  

Energy Technology Data Exchange (ETDEWEB)

A delta connected, resonant snubber-based, soft switching, inverter circuit achieves lossless switching during dc-to-ac power conversion and power conditioning with minimum component count and size. Current is supplied to the resonant snubber branches solely by the dc supply voltage through the main inverter switches and the auxiliary switches. Component count and size are reduced by use of a single semiconductor switch in the resonant snubber branches. Component count is also reduced by maximizing the use of stray capacitances of the main switches as parallel resonant capacitors. Resonance charging and discharging of the parallel capacitances allows lossless, zero voltage switching. In one embodiment, circuit component size and count are minimized while achieving lossless, zero voltage switching within a three-phase inverter.

1998-01-01

315

A gridded D-"3He IEC power plant  

International Nuclear Information System (INIS)

Inertial Electrostatic Confinement (IEC) fusion was recently described by an Electric Power Research Institute (EPRI) review panel as potentially leading to a most attractive fusion reactor from a utility point of view, if the physics issues can be resolved. Consequently, a design for a small 25-MW electric D-"3He fueled power plant has been explored. Key power plant components consist of the IEC, direct energy conversion and a step-down converter for electrical power transmission. (author).

316

Development of cutting technique of reactor core internals by CO laser  

International Nuclear Information System (INIS)

The CO laser is superior in the absorption characteristic to materials to the CO2 laser due to its shorter wavelength. In consideration of this characteristic Nuclear Power Engineering Corporation is studying this applicability sponsored by the Ministry of International Trade Industry of Japan to cutting of reactor core internals of commercial nuclear power plant. In decommissioning of reactor core internals it is necessary to cut stainless steel plates of 305 mm thick. The authors cut stainless steel plates of up to 310mm thick in air and those of up to 150 mm thick underwater with a 20kW class laser. Further, models simulating key structural elements of PWR core internals were cut and secondary products to clarify the applicability of the CO laser cutting to reactor core internals were evaluated. (author)

1995-04-23

317

The determination of the tuning of a Power System Stabilizer (PSS). De bepaling van de instelling van een Power System Stabilizer  

Energy Technology Data Exchange (ETDEWEB)

By means of an analogous simulator, which can simulate a power supply system, a method to determine the transfer function of a Power System Stabilizer (PSS) is developed. The purpose of the PSS is to damp unwanted electro-mechanical oscillations. The method is very systematic and there is no need for specified values of the parameters used in the system. It is assumed that the power generator system is linear for small variations. The system can be considered to be a black box. Measurements executed by means of this method are completely controlled by the person who enforces the measurement. By applying this method carefully, irregularities are almost out of the question. The equipment necessary are a PC with two AD-ports and an adjustable sinus-generator. A comparison is made with a more traditional method, in which a spectrum analyzer is used. 4 figs., 7 refs.

1992-10-01

318

FEOL technology trend  

International Nuclear Information System (INIS)

Trends in front-end-of-line technology are discussed. At the chip level, many of the important parameters are published in the National Technology Roadmap for Semiconductors in 1994. At the device and circuit level, both bipolar and CMOS are scalable. However, the large standby power of bipolar circuits severely limits the integration level of bipolar chips. The inherently low standby power of CMOS, on the contrary, allows the integration level of CMOS circuits to continue increasing with scaling. In reality, both the electric field and power density of CMOS devices have been gradually rising over the generations owing to non-scaling effects of thermal voltage and silicon bandgap. As power supply voltage reaches 1.5V and below, circuit performance can only be gained at the expense of higher active or standby power of the chip. Implications of device scaling on ...

319

Adaptive power-system stabilizer based on turbine governor control  

Energy Technology Data Exchange (ETDEWEB)

A novel adaptive stabilizer, called an Adaptive Governor Power System Stabilizer (AGPSS), which operated on the governor turbine system, was described. There has been extensive research on adaptive excitation control of generators in power systems with the goal of achieving better dynamic performance. AGPSS tracks the frequency and damping of oscillations in a power system, and adjusts to ensure that there is always sufficient damping in the system. There is no interaction between stabilizers on different generating units, and each one acts independently, consuming oscillation energy locally. These stabilizers are easy to design and this facilitates their use in multimachine systems. Results obtained by nonlinear simulation of a single-machine and a three-machine power system were discussed, illustrating the effectiveness of the stabilizers in supplying damping and improving ...

1994-12-31

320

Distributed-processing radiation management system for nuclear power plants  

Energy Technology Data Exchange (ETDEWEB)

The importance of radiation management for nuclear facilities including nuclear power plants has increased as the general public understanding has progressed, and necessary information for management must be processed exactly and quickly. In nuclear power plants, radiation management is performed by each individual operation, and collected information is managed by the system of each operation. The distributed-processing radiation management system has been developed aiming to use a general-purpose LAN and make quick and efficient use of information managed by individual operations. This paper describes the system configuration and functions. (author)

1999-06-01

321

The subject of energy  

International Nuclear Information System (INIS)

Since the 1970s, Danish electricity supply has been dependent on imported coal. This has lead to greater reliability of supply, as could be seen during the Gulf War when Danish electricity prices remained stable in contrast to conditions in other countries. The disadvantage is the air pollution caused by coal combustion. This is regulated, it is stated, by several international laws and agreements, and these are named here. The nature of this form of pollution is explained in relation to actual Danish power plants and their efforts to reduce emissions of sulphur dioxide and nitrogen oxides. Carbon dioxide, which is a greenhouse gas, is also emitted. Danish environmental policy concentrates on these problems. The efforts of the electric power companies to reduce air pollution are detailed, both nationally and internationally, and their positive consequences are described. Desulphurization and ...

1990-10-22

322

Localization explore of electrical and I and C equipments in Daya Bay Nuclear Power Station  

International Nuclear Information System (INIS)

The supply of electronic instrumentation and controlling (I and C) equipments in Daya Bay Nuclear Power Station depends on importation up to now, however, reliable supply of spare parts is presently threatened by many factors. Consequently, Daya Bay Nuclear Power Station tries to localize these equipments. According to a survey, China has possessed the ability to undertake the research, development and production of the I and C system in nuclear power independently. We propose that localization should firstly starts with the production of replacement board and parts for analogical I and C system, gradually leads to the substitution of system cabinet units, and finally realize the independent research, development and production of advanced digital main control system. A series of prominent problems of producing nuclear grade I and C equipments are focused on the designing, ...

2007-10-01

323

An evaluation of the ecological consequences of partial-power operation of the K Reactor, SRS  

International Nuclear Information System (INIS)

The K Reactor at the Savannah River Site (SRS) shut-down in spring 1988 for maintenance and safety upgrades. Since that time the receiving stream for thermal effluent, Indian Grave Branch and Pen Branch, have undergone a pattern of post-thermal recovery that is typical of other SRS streams following removal of thermal stress. Divesity of fish and aquatic macroinvertebrate communities has increased and available habitats have been colonized by numerous species of herbaceous and woody plants. K Reactor is scheduled to resume operation in 1991 and operate through 1992 without a cooling tower to cool the discharge. It is likely that the reactor will operate at approximately one-third to one-half of full power (800--1200 MW thermal) during this period and effluent temperatures will be substantially lower than earlier operation at full power. Monthly average discharge temperatures at ...

324

Production capabilities in US nuclear reactors for medical radioisotopes  

Energy Technology Data Exchange (ETDEWEB)

The availability of reactor-produced radioisotopes in the United States for use in medical research and nuclear medicine has traditionally depended on facilities which are an integral part of the US national laboratories and a few reactors at universities. One exception is the reactor in Sterling Forest, New York, originally operated as part of the Cintichem (Union Carbide) system, which is currently in the process of permanent shutdown. Since there are no industry-run reactors in the US, the national laboratories and universities thus play a critical role in providing reactor-produced radioisotopes for medical research and clinical use. The goal of this survey is to provide a comprehensive summary of these production capabilities. With the temporary shutdown of the Oak Ridge National Laboratory (ORNL) High Flux Isotope Reactor (HFIR) in November 1986, the ...

1992-11-01

325

Divergent views on a possible nuclear waste repository in the community: Social aspects of decision making  

Energy Technology Data Exchange (ETDEWEB)

The paper summarizes the results obtained in two interview studies conducted in the communities of Storuman and Malaa in northern Sweden, 1995 and 1997. It highlights the similarities and differences with respect to the public participation and decision processes which preceded the respective referenda in the two communities. The presentation includes the arguments used by proponents and opponents, the changes over time, as well as the time frame and the information involved in the processes. It is concluded e.g. that local cultures, life-styles, knowledge of similar events, and the time for and management of the participation process are important and salient factors in the resulting social dynamics. Factors of possibly more fundamental importance were also discerned, however, including overall attitude to and valuation of nuclear power, perceptions of development, solidarity, power and power ...

1999-12-01

326

Power density distribution by gamma scanning of fuel rods measurement technique in RA-8 critical facility  

International Nuclear Information System (INIS)

Power density measurements in the critical facility RA-8 are presented. These measurements were the first systematic use of the reactor. A measurement system was designed, built and proved for this goal. Power profiles are showed and the results are compared with calculated values. (author)

1999-10-26

327

New safety device announced for nuclear power plants  

International Nuclear Information System (INIS)

An Ottawa-based company, ECS-Power Systems Inc., has successfully completed a series of tests on an innovative device called a hydrodynamic port (HDP), which makes it possible to automatically initiate and maintain emergency cooling of a nuclear reactor core by natural processes, without relying in any way on human intervention, instrumentation, electric power, valves or moving parts of any kind.

328

Recovery of reactor pressure vessel materials from radiation hardening and embrittlement after a year of irradiation of microtensile and Charpy-V specimens in a nuclear power plant  

International Nuclear Information System (INIS)

Weld metal, base material and stainless steel overlay specimens for Charpy tests and static tensile tests were irradiated for a year in a power reactor of the Bohunice nuclear power plant in place of the evaluated surveillance specimens. The material of the specimens was identical with that of the WWER-440 reactor pressure vessels, and was exposed to a fluence of (1.2 - 4.5) x 10"2"3 m"-"2 (E > 0.5 MeV) at approximately 270 degC. Some of the irradiated as well as unirradiated specimens were subjected to regeneration annealing at 475 degC for 168 h. The behavior of the materials after irradiation and annealing was evaluated. (author). 33 tabs., 32 figs., 8 refs.

329

A design study of reactor core optimization for direct nuclear heat-to-electricity conversion in a space power reactor  

Energy Technology Data Exchange (ETDEWEB)

To propose a new design concept of a nuclear reactor used in the space, research has been conducted on the conceptual design of a new nuclear reactor on the basis of the following three main concepts: (1) Thermionic generation by thermionic fuel elements (TFE), (2) reactivity control by rotary reflector, and (3) reactor cooling by liquid metal. The outcomes of the research are: (1) A calculation algorithm was derived for obtaining convergent conditions by repeating nuclear characteristic calculation and thermal flow characteristic calculation for the space nuclear reactor. (2) Use of this algorithm and the parametric study established that a space nuclear reactor using 97% enriched uranium nitride as the fuel and lithium as the coolant and having a core with a radius of about 25 cm, a height of about 50 cm and a generation efficiency of about 7% can probably be operated continuously ...

1998-01-01

330

Managing system for mounted parts and spare parts of power source facilities  

Energy Technology Data Exchange (ETDEWEB)

The power source facilities of JT-60 consist of poloidal magnetic coil power source, toroidal magnetic coil power source, the power generation facility for heating, operation power distribution facility and secondary cooling facility, and at the time of the experiment operation of JT-60, they supply 1300 MVA of instantaneous maximum power to loads. The component machinery and equipment of the power source facilities are installed in about 20 indoor and outdoor places, and their mounted parts are about 15,000 kinds. About 3,000 kinds of spare parts are preserved in 15 exclusively used stores. The managing system for mounted parts and spare parts of JT-60 power source facilities which possesses the functions of rapidly and efficiently carrying out the storage of large quantity of information, mutual ...

1995-07-01

331

Thermal-hydraulic analysis following a safety flapper valve's fault for a pool-type research reactor  

International Nuclear Information System (INIS)

One of the characteristic safety features of a pool type research reactor is a safety flapper valve. The valve enables natural convection cooling mechanism in one of the following events. (a) Opening flapper valve promote decay heat removal following reactor's shutdown. (b) Also the valve is gravity driven. There is a possibility that the valve fails to open when it is required to do so. In the present paper the cooling characteristics of the core are analyzed for this event. A steady state study was performed for 5 MW power and 18 FE following a reactor shutdown. It is shown that enough margin exists to assure adequate reactor core cooling should the safety flapper valve fails to open. (authors)

332

Low Frequency Phased Array Techniques for Crack Detection in Cast Austenitic Piping Welds: A Feasibility Study  

Energy Technology Data Exchange (ETDEWEB)

Studies conducted at the Pacific Northwest National Laboratory (PNNL) in Richland, Washington have focused on developing and evaluating the reliability of nondestructive testing (NDT) approaches for coarse-grained stainless steel reactor components. The objective of this work is to provide information to the United States Nuclear Regulatory Commission (NRC) on the utility, effectiveness and limitation of NDT techniques as related to inservice testing of primary system piping components in pressurized water reactors. We examined cast stainless steel pipe specimens containing thermal and mechanical fatigue cracks located close to the weld roots and having inner and outer diameter surface geometrical conditions that simulate several water reactor primary piping configurations. In addition, segments of vintage centrifugally cast piping were examined to characterize the inherent acoustic noise and scattering ...

2007-01-01

333

Dynamic simulation of stationary fuel cells in a liberalised energy market; Dynamische Simulation von stationaeren Brennstoffzellen im liberalisierten Energiemarkt  

Energy Technology Data Exchange (ETDEWEB)

An intensified integration of renewable energies and a more extensive use of combined heat and power lead to an increasingly decentralized power economy. Such an economy is characterized by the conversion of energy at the point of the energy demand and depending on the energy system, by the possibility of balancing the fluctuating supply of renewable energies. In the long run, there is no doubt that fuel cells will be part of such a sustainable and flexible energy concept. The scope of this dissertation includes an analysis of the flexibility of fuel cells in energy supply (1,5 kW{sub el}), an assessment of the potential to compensate for the fluctuating supply of wind energy by an aggregation of decentralized fuel cells and a participation as a contractor in the spot and balance energy markets. Therefore two fuel cells were monitored and tested in order to obtain their ...

2010-07-01

334

Power Systems Development Facility Gasification Test Run TC07  

Energy Technology Data Exchange (ETDEWEB)

This report discusses Test Campaign TC07 of the Kellogg Brown & Root, Inc. (KBR) Transport Reactor train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The Transport Reactor is an advanced circulating fluidized-bed reactor designed to operate as either a combustor or a gasifier using a particulate control device (PCD). The Transport Reactor was operated as a pressurized gasifier during TC07. Prior to TC07, the Transport Reactor was modified to allow operations as an oxygen-blown gasifier. Test Run TC07 was started on December 11, 2001, and the sand circulation tests (TC07A) were completed on December 14, 2001. The coal-feed tests (TC07B-D) were started on January 17, 2002 and completed on April 5, 2002. Due to ...

2002-04-05

335

A compilation of reports of the Advisory Committee on Reactor Safeguards: 1995 annual. Volume 17  

Energy Technology Data Exchange (ETDEWEB)

This compilation contains 44 ACRS reports submitted to the Commission, or to the Executive Director for Operations, during calendar year 1995. It also includes a report to the Congress on the NRC Safety Research Program. All reports have been made available to the public through the NRC Public Document Room and the US Library of Congress. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part 1 contains ACRS reports by project name and by chronological order within project name. Part 2 categorizes the reports by the most appropriate generic subject area and by chronological order within subject area.

1996-04-01

336

A compilation of reports of the Advisory Committee on Reactor Safeguards: 1992 Annual. Volume 14  

Energy Technology Data Exchange (ETDEWEB)

This compilation contains 50 ACRS reports submitted to the Commission, Executive Director for Operations, or to the Office of Nuclear Regulatory Research, during calendar year 1992. It also includes a report to the Congress on the NRC Safety Research Program. All reports have been made available to the public through the NRC Public Document Room and the US Library of Congress. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part I contains ACRS reports alphabetized by project name and by chronological order within project name. Part 2 categorizes the reports by the most appropriate generic subject area and by chronological order within subject area.

1993-04-01

337

A compilation of reports of the Advisory Committee on Reactor Safeguards: 1992 Annual  

Energy Technology Data Exchange (ETDEWEB)

This compilation contains 50 ACRS reports submitted to the Commission, Executive Director for Operations, or to the Office of Nuclear Regulatory Research, during calendar year 1992. It also includes a report to the Congress on the NRC Safety Research Program. All reports have been made available to the public through the NRC Public Document Room and the US Library of Congress. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part I contains ACRS reports alphabetized by project name and by chronological order within project name. Part 2 categorizes the reports by the most appropriate generic subject area and by chronological order within subject area.

1993-04-01

338

A compilation of reports of the Advisory Committee on Reactor Safeguards: 1989 annual  

Energy Technology Data Exchange (ETDEWEB)

This compilation contains 54 ACRS reports submitted to the Commission or to the Executive Director for Operations during calendar year 1989. It also includes a report to the Congress on the NRC Safety Research Program. All reports have been made available to the public through the NRC Public Document Room and the US Library of Congress. The reports are divided into two groups: Part 1 -- ACRS Reports on Project Reviews, and Part 2 -- ACRS Reports on Generic Subjects. Part 1 contains ACRS reports alphabetized by project name and within project name by chronological order. Part 2 categorizes the reports by the most appropriate generic subject area and within subject area by chronological order.

1990-04-01

339

A compilation of reports of the Advisory Committee on Reactor Safeguards: 1988 annual  

Energy Technology Data Exchange (ETDEWEB)

This compilation contains 47 ACRS reports submitted to the Commission or to the Executive Director for Operations during calendar year 1988. It also includes a report to the Congress on the NRC Safety Research Program. All reports have been made available to the public through the NRC Public Document Room and the US Library of Congress. The reports are divided into two groups: Part 1, ACRS Reports on Project Reviews, and Part 2, ACRS Reports on Generic Subjects. Part 1 contains ACRS reports alphabetized by project name and within project name by chronological order. Part 2 categorizes the reports by the most appropriate generic subject area and within subject area by chronological order. 136 refs., 1 tab.

1989-04-01

340

A compilation of reports of the Advisory Committee on Reactor Safeguards: 1987 annual  

Energy Technology Data Exchange (ETDEWEB)

This compilation contains 47 ACRS reports submitted to the Commission or to the Executive Director for Operations during calendar year 1987. It also includes a report to the Congress on the NRC Safety Research Program for FY 1988. All reports have been made available to the public through the NRC Public Document Room and the US Library of Congress. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part 1 contains ACRS reports alphabetized by project name and within project name by chronological order. Part 2 categorizes the reports by the most appropriate generic subject area and within subject area by chronological order.

1988-04-01

341

Combined power generation with wind and ocean waves  

Energy Technology Data Exchange (ETDEWEB)

It is often advantageous to generate power with combinations of wind and ocean waves. In fact ocean waves, their generation, propagation, dissipation are directly related to wind velocity and its duration oven the sea. In this paper an attempt has been made to demonstrate statistically to present some advantages with combined wind and ocean wave power generation. Even though many conceptual techniques and methods are possible to harness combined power generation, it is important to test feasibility of combined output as well as individual outputs mathematically. One of the major advantages of combined wind and wave power generation is to improve probability of continuous power supply (it minimises the interruptions and compensates power fluctuations with one another). Some of the major wave characteristics like wave Height (H), Time period ...

1996-09-01

342

Validation of flux mapping system (FMS) of TAPP-4 with TRIVENI  

International Nuclear Information System (INIS)

The reactor core of TAPP-3 and 4 is divided into 14 power zones for spatial power control. Corresponding to each zone is a light water zonal compartment. The 14 ZCCs are located in two radial planes, each containing 7 ZCCs. For each zone, power measurement is carried out using three cobalt Self Powered Neutron Detectors (SPNDs) at appropriate locations close to the respective ZCC. Since the zone power as obtained by the true average of the healthy zone control detector (ZCD) readings belonging to a particular zone may not correspond to its actual power because these 3 detectors per zone, measure only point fluxes but the zone extends over a large core region. Therefore accurate estimation of zone power calibration factors is required to estimate the zone powers and also to provide effective spatial ...

2006-11-13

343

Nuclear power plant support activities in reactors chemistry at CNEA  

International Nuclear Information System (INIS)

Argentina has two operating PHWR nuclear power plants. Atucha I NPP is a pressure vessel type heavy water reactor of 360 MW e with 25 years of operation and Embalse NPP is a pressure tube type CANDU-600 reactor of 640 MW e. Atucha II, a third plant of 600 MW e of the pressure vessel type similar to Atucha I, is being constructed. NASA (Nucleoelectrica Argentina S.A.) currently operates both nuclear power plants. The National Atomic Energy Commission (Comision Nacional de Energia Atomica - CNEA) provides operational support to the plants, including research and development assistance, and actual technical services and maintenance work in different areas. The Chemistry Department, formerly the Reactor Chemistry Department has carried out project and support activities to the plants during the past 20 years. The aim of this work is to describe the present organization and the ...

1999-10-15

344

Operational feedback and design improvements in reactor regulating system of 540MWe PHWR  

International Nuclear Information System (INIS)

Reactor Regulating System (RRS) of TAPP-3 and 4 (540 MWe PHWR) addresses issues of elaborate Flux Tilt Control as applied to large Reactor Cores in addition to the traditional Bulk Power (Actual Power) Control. The control of Bulk and Zonal Power by RRS through the use of Zonal Control Compartments (ZCCs) has been successfully demonstrated in the Indian PHWRs for the first time. Features like automation in Demand Power Maneuvering, Manual Movement of Reactivity Devices through the Human Machine Interface (HMI) and the supervised withdrawal of Shut-off Rods during Auto Criticality are also included. Special algorithms to measure and control the individual Zone Power and Bulk Power also form part of RRS algorithms. This paper describes the salient features of RRS of TAPP-3 and 4 and the improvement carried out based on the ...

2006-11-13

345

A comparison study on activation safety of fusion, fission and hybrid reactor technology  

Energy Technology Data Exchange (ETDEWEB)

The activation aspects of pure fusion and hybrid fusion technology is studied to assess the radioactive safety of various fusion concepts including tokamak pure fusion, fissile fuel producing hybrid and radio waste transmuting hybrid. The activation properties of breeding, coolant and structural materials in fusion reactors might be quite different from those in fission reactors because of the high energy D-T fusion neutrons from the fusion cores. A study on the involved activation reactions and the uncertainties of the associated nuclear cross-sections is carried. The activation properties of various first wall concepts and blanket concepts are discussed. The radioactive inventory during the operation lifetime and the potential hazard of the radioactive nuclides with respect to near term (reprocessing) and long term (waste disposal) aspects are calculated, with reference to ITER/NET (International Thermonuclear Experiment ...

1994-12-31

346

A comparison study on activation safety of fusion, fission and hybrid reactor technology  

International Nuclear Information System (INIS)

The activation aspects of pure fusion and hybrid fusion technology is studied to assess the radioactive safety of various fusion concepts including tokamak pure fusion, fissile fuel producing hybrid and radio waste transmuting hybrid. The activation properties of breeding, coolant and structural materials in fusion reactors might be quite different from those in fission reactors because of the high energy D-T fusion neutrons from the fusion cores. A study on the involved activation reactions and the uncertainties of the associated nuclear cross-sections is carried. The activation properties of various first wall concepts and blanket concepts are discussed. The radioactive inventory during the operation lifetime and the potential hazard of the radioactive nuclides with respect to near term (reprocessing) and long term (waste disposal) aspects are calculated, with reference to ITER/NET (International Thermonuclear Experiment ...

347

Study of dose rates and radionuclides contributing to dose rates in India's 540 MWe pressurised heavy water reactors  

International Nuclear Information System (INIS)

Tarapur Atomic Power Station Unit-3 and 4 (TAPS -3 and 4) are the 540 MWe reactors. Unit-4 attained first criticality on 06th March 2005 and operated for about 230 effective full power days (EFPD). Unit-3 attained first criticality on 21st May 2006 and operated for about 20 EFPD. With the reactor operation radiation field increases on the Primary Heat Transport system equipments, Moderator system equipments and auxiliary system equipments due to deposition of fission products and activation products in different reactor systems. These dose rates significantly contributes to the external exposure and stations collective dose during reactor operation, refueling operation and maintenance activities. A study was undertaken at TAPS 3 and 4 to identify the system equipments showing the significant dose rates and identify the radionuclides present in the primary heat ...

2006-11-13

348

IECEC '87; Proceedings of the Twenty-second Intersociety Energy Conversion Engineering Conference, Philadelphia, PA, Aug. 10-14, 1987. Volumes 1, 2, 3, and 4  

International Nuclear Information System (INIS)

Papers are presented on space power requirements and issues, space photovoltaic systems, space solar dynamic systems, space thermal systems, manned and unmanned space power systems, thermionics, and thermoelectrics. Also considered are high power devices for space power systems, high power conversion for space power systems, 1-10 kWe nuclear space power sources, 100-kW class nuclear power concepts, space reactor safety, and multimegawatt space nuclear power systems. Other topics include space power systems automation, space kilovolt technology, space power electronics, space lithium and nickel-cadmium batteries, lithium sodium storage, and space fuel cells. Papers are also presented on space nickel hydrogen batteries, alternative energy ...

1987-08-10

349

12th Symposium on Space Nuclear Power and Propulsion. Conference on Alternative Power from Space (APFS),Conference on Accelerator-Driven Transmutation Technologies and Applications (A-DTTA)  

International Nuclear Information System (INIS)

These proceedings represent papers presented at the 12th symposium on Space Nuclear Power and Propulsion held in Albuquerque, New Mexico. The symposium theme was ''commercialization and technology transfer''. The topics discussed include: wireless power transmission, solar power from space next generation spacecraft, space power electronics and power management, flight testing of components, manufacturing and processing of materials, nuclear propulsion, reactors and shielding and many others of interest to the scientific community representing industry, government and academic institutions. There were 163 papers presented at the conference and 60 have been abstracted for the Energy Science and Technology database.

1995-01-08

350

A model for calculation of RCS pressure during reflux boiling under reduced inventory conditions and its assessment against PKL data  

International Nuclear Information System (INIS)

There has been recent interest in the United States concerning the loss of residual heat removal system (RHRS) under reduced coolant inventory conditions for pressurized water reactors. This issue is also of interest in the Federal Republic of Germany and an experiment was performed in the integral PKL-III experimental facility at Siemens-KWU to supply applicable data. Recently, an NRC-sponsored effort has been undertaken at the Idaho National Engineering Laboratory to identify and analyze the important thermal-hydraulic phenomena in pressurized water reactors following the long term loss-of-RHRS during reduced inventory operation. The thermal-hydraulic response of a closed reactor coolant system during such a transient is investigated in this report. Some of the specific processes investigated include: reflux condensation in the steam generators, the corresponding pressure increase in the ...

1992-04-01

351

A model for calculation of RCS pressure during reflux boiling under reduced inventory conditions and its assessment against PKL data  

International Nuclear Information System (INIS)

There has been recent interest in the United States concerning the loss of residual heat removal system (RHRS) under reduced coolant inventory conditions for pressurized water reactors. This issue is also of interest in the Federal Republic of Germany and an experiment was performed in the integral PKL-HI experimental facility at Siemens-KWU to supply applicable data. Recently, an NRC-sponsored effort has been undertaken at the Idaho-National Engineering Laboratory to identify and analyze the important thermal-hydraulic phenomena in pressurized water reactors following the long term loss-of-RHRS during reduced inventory operation. The thermal-hydraulic response of a closed reactor coolant system during such a transient is investigated in this report. Some of the specific processes investigated include: reflux condensation in the steam generators, the corresponding pressure increase in the ...

1991-10-28

352

Integrated resource strategic planning in China  

Energy Technology Data Exchange (ETDEWEB)

Many governments around the world are focusing on emissions reduction through energy efficiency improvements, particularly on the demand side. Although Integrated Resource Planning (IRP), which considers both supply-side and demand-side options, had been a useful tool in the planning process for the power industry, its effectiveness has been challenged recently with the restructuring of the power sector that has occurred in China and elsewhere around the world. The paper proposes Integrated Resource Strategic Planning (IRSP) as an alternative to IRP in a deregulated power sector. IRSP takes the resource planning process one step further to the national level. In this paper, the authors demonstrate the tremendous potential for efficiency improvements on both the supply and demand sides of the power sector in China with IRSP. The results show that between 2009 and ...

2010-08-15

353

Integrated resource strategic planning in China  

International Nuclear Information System (INIS)

Many governments around the world are focusing on emissions reduction through energy efficiency improvements, particularly on the demand side. Although Integrated Resource Planning (IRP), which considers both supply-side and demand-side options, had been a useful tool in the planning process for the power industry, its effectiveness has been challenged recently with the restructuring of the power sector that has occurred in China and elsewhere around the world. The paper proposes Integrated Resource Strategic Planning (IRSP) as an alternative to IRP in a deregulated power sector. IRSP takes the resource planning process one step further to the national level. In this paper, the authors demonstrate the tremendous potential for efficiency improvements on both the supply and demand sides of the power sector in China with IRSP. The results show that between 2009 and ...

2010-08-01

354

Steam generator tube performance  

International Nuclear Information System (INIS)

A review of the performance of steam generator tubes in 116 water-cooled nuclear power reactors showed that tubes were plugged at 54 (46 percent) of the reactors. The number of tubes removed from service decreased from 4 692 (0.30 percent) in 1981 to 3 222 (0.20 percent) in 1982. The leading causes of tube failures were stress corrosion cracking from the primary side, stress corrosion cracking (or intergranular attack) from the secondary side and pitting corrosion. The lowest incidence of corrosion-induced defects from the secondary side occurred in reactors that have used only volatile treatment, with or without condensate demineralization.

2005-10-27

355

Investigation of the transportation requirements for fusion power plants  

Science.gov (United States)

This report presents a general investigation of the transport requirements associated with the construction and operation of conceptual fusion reactors. Projections of amounts of construction and operating materials requiring transportation are presented for several proposed designs. The material to be shipped is described along with the shipping containers that might be used, the transport modes and the expected impact of transporting these materials. Transportation of both radioactive and nonradioactive materials will be required. Most of these materials are routinely shipped by the transportation industry. Transportation requirements of a representative fusion reactor are also compared with Liquid Metal Fast Breeder Reactor (LMFBR) requirements.

1976-09-01

356

Outlook for using wind energy for electrification of agriculture in Estonian SSR  

Energy Technology Data Exchange (ETDEWEB)

The developed electrical networks in the agricultural regions of the Estonian SSR make it possible to construct relatively powerful wind power plants at the sites of the most favorable wind conditions with small outlays for the power transmission lines. The wind power plant electricity can be used to electrify the production processes in agriculture, while the surplus can be supplied to the energy system. The inclusion of the wind power plants in the energy system makes it possible to improve the total generation of energy or reduce the consumption of fuel. With the efficient arrangement of the wind power plants, one can also reduce the energy losses during its transfer. Calculations indicated that in the coastal zones of the Estonian SSR, one can obtain specific power of 420-480 kW/km/sup 2/. For comparison it is ...

1982-01-01

357

Finalisation of design provision for active process water system shut down at TAPP-3 and 4  

International Nuclear Information System (INIS)

Active Process Water (APW) system is provided as a unitized system in TAPP-3 and 4. Maintenance on APW system requires shutdown of this system. As shut down heat exchangers are fed by APW system; during APW system shutdown cold shutdown state cannot be maintained. Therefore safety analysis is done to optimize the duration of reactor shutdown (which means low decay heat) after which APW shutdown can be taken with minimum water supply to the shutdown heat exchangers. Based on this analysis, it is proposed in technical specification that APW system shutdown can be taken after 7 days of reactor shutdown with shutdown heat exchangers supplied with about 20 % of normal APW flow. With this configuration, PHTS, moderator, end shield, calandria vault water temperature can be maintained within limits. A design provision is made at TAPP-3 and 4 to interconnect APW system of both units in such a way that one unit ...

2006-11-13

359

Incident report: spillage of reactor coolant at Wolsung  

Energy Technology Data Exchange (ETDEWEB)

Late last year the Wolsung Candu in Korea suffered an incident which resulted in heavy water being released from the primary system into the containment. With the unit now back at full power, this article examines the causes of the incident and the action which is being taken to prevent it happening again.

1985-05-01

360

EDF's experience in the operation of pump-storage plants  

Energy Technology Data Exchange (ETDEWEB)

This paper describes the advent of energy pumped storage plants in France, in connection with nuclear power reactors development and gives detailed specifications of different components (pump turbines, alternators, valves ...). 5 figs., 3 tabs.

1992-01-01

361

Development of Tritium Removal Technology.  

Science.gov (United States)

Liquid Phase Catalytic Exchange (LPCE)- Cryogenic Distillation(CD) process was studied which could be available for an optimal tritium removal process of pressurized heavy water reactor system at Wolsung nuclear power plant in the near future. Based upon ...

1986-01-01

362

Consideration of field experience in developing new projects of steam generators for nuclear power stations equipped with VVER reactors  

British Library Electronic Table of Contents (United Kingdom)

The main problems encountered during the operation of horizontal steam generators are considered. Design features of the new PGV-1000MK and PGV-1500 steam generators are analyzed.

2006-01-01

363

RISKAUDIT Report no. 7, Vol. 1: Safety evaluation of VVER 440/213 and VVER 1000/320 reactors in Rovno NPP Units 1, 2 and 3. Final Report by AIB-Vincotte Nuclear, CIEMAT, ANPA, GRS, IPSN, AEA-T  

Energy Technology Data Exchange (ETDEWEB)

The Riskaudit 7 report has been made by a group of independent experts from Western European countries representing technical organizations specialized in the support of regulatory bodies of those countries. It represents a preliminary estimation of the Ukrainian WWER B 213 and B 320 reactors, based on the example of Rovno NPP, analysed with a Western practice. The first part of the document covers the following aspects of the report: core design and fuel management; pressurized components; electrical supply; instrumentation and control; containment; internal events; site conditions and external events.

1994-07-15

364

Hydrogen production in a 5 kW Diesel Oxidative Steam Reformer  

Energy Technology Data Exchange (ETDEWEB)

This paper presents a reformer prototype for the production of the necessary H{sub 2} to supply a 5 kW PEMFC and its first results. The fuel processor consists of an OSR and a WGS and a PROX reactors. The design of the system was carried out with a one-dimensional model. The mixture chamber was specially studied with a CFD code (Fluent), taking into account the effect of fuel evaporation and the cool flame process. The aim of the designed facility is to be able of characterising each component and controlling each working parameter. Eventually, using diesel as fuel, results from the mixture chamber, OSR, WGS and PROX reactors are presented. It also includes conclusions and future works. (authors)

2006-07-01

365

Thailand: utilisation programme set for massive expansion  

Energy Technology Data Exchange (ETDEWEB)

The US$360 million project to increase gas supplies to Eastern and Southern Thailand is discussed, and the use of international competitive bidding to purchase the line pipe and other facilities is reported. The government approved proposal for a gas fired combined-cycle power station and gas separation plant are discussed. (UK).

1991-11-01

366

Steam turbines. Dampfturbinen  

Energy Technology Data Exchange (ETDEWEB)

In spite of the fact that market requirements for new plants continue to be restricted, steam turbine technology and operation engineers have left nothing undone to improve products and operating characteristics. They are generally guided by the principle of optimum economic power supplies but lowest pollution. The new eastern markets are expected to give new impulses to steam turbine design. Cogeneration is of special future importance. (orig.).

1991-04-01

367

Socioeconophysics: Opinion Dynamics for number of transactions and price, a trader based model  

CERN Document Server

Involving effects of media, opinion leader and other agents on the opinion of individuals of market society, a trader based model is developed and utilized to simulate price via supply and demand. Pronounced effects are considered with several weights and some personal differences between traders are taken into account. Resulting time series and probabilty distribution function involving a power law for price come out similar to the real ones.

2006-01-01

368

Smart Meter - Smart Grid - Smart Energy. The convergence of gas and power; Smart Meter - Smart Grid - Smart Energy. Die Konvergenz von Gas und Strom  

Energy Technology Data Exchange (ETDEWEB)

Smart electricity and gas supply grids are a prerequiste for full-scale utilization of the potential of modern energy-saving appliances and equipment. Direct exchange of information between the supplier and the consumer is indispensable for reducing costly and energy-intensive peak loads. (orig.)

2010-09-15

369

Proceedings of the meeting on the technical study at KEK  

International Nuclear Information System (INIS)

Technical studies on constructing the J-PARC (Japan Proton Accelerator Research Complex) are presented by five authors: (1) on the wiring for electromagnets of the 50 GeV synchrotron, (2) on the fast beam-extraction from the 50 GeV synchrotron into two opposite directions, (3) on the target chamber system for the generation of muons, (4) on the design of large aperture electromagnets, and (5) on the maintenance and control of the electromagnet power supplies. (K.Y.)

2006-11-28

370

New uses for coal  

Energy Technology Data Exchange (ETDEWEB)

As oil supplies diminish, Britain will have to rely more and more on coal as one of the energy alternatives. To burn coal cleanly and efficiently coal will have to be converted into gas and liquid fuels to replace natural gas and oil. The research and development programme of the National Coal Board is directed towards meeting these new challenges. This paper outlines some of the Coal Board's current projects in the fields of industrial combustion, power generation, domestic combustion, coal gasification and coal liquefaction. 10 figs.

1981-01-01

371

Motor drive chassis for the plutonium protection system  

International Nuclear Information System (INIS)

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

1998-10-12

372

Maintenance of energy systems by means of Internet; Energiesystemen onderhouden met Internet  

Energy Technology Data Exchange (ETDEWEB)

Asean Brown Boveri (ABB) developed Glass (Global access for service and support), a monitoring system for the remote control and management of ABB supplied equipment and other equipment through the Internet. Glass can be applied for many different systems, e.g. automated substations of electric power distribution systems or train equipment

1999-04-01

373

Implementation of Renewable Energy Systems in Denmark  

DEFF Research Database (Denmark)

Denmark has been one of the first countries in the world to commit itself to a sustainable energy development. This has been substantiated by two official action plans from 1990 and 1996 with emphasis on energy efficiency and supply systems based on renewable energy. In year 2005, renewable energy sources are planned to cover 12-14% and in year 2030 about 35% of total Danish energy demand. This paper reviews the experiences with implementation of renewable energy in Denmark with a focus on wind power and biomass.

1997-01-01

374

Dual fuel engine solves the solvent problem  

Energy Technology Data Exchange (ETDEWEB)

Some 200 visitors attended the official opening of a new diesel engine driven cogeneration plant in the city of Hamburg at the end of March. The dual fuel engine built by Blohm+Voss will supply 7.7 MW of electricity to the grid and 8.26 MW of thermal power to generate steam and hot water. (author)

1993-05-01

375

Corrosion of Cu-W condensates in tap water  

International Nuclear Information System (INIS)

Corrosion resistance of Cu-W system condensates in tap water was studies. It is shown that with an increase in W concentration in the condensates of the Cu-W system their corrosion in tap water enhances. In the material designated for power supply facilities the optimal tungsten content is up to 6%. Owing to formation of oxide film on the surface of the samples corrosion is stabilitized 40 h after the test start.

376

Biological effects of extremely low frequency (ELF) electromagnetic fields: a perspective on the issues  

Energy Technology Data Exchange (ETDEWEB)

This apper discusses whether health risks are associated with exposure to electromagnetic fields that exist beneath high-voltage transmission lines. This is a question receiving increasing attention as the electric utility industry prepares to supply its customers with increased amounts of electric power. 26 refs.

1980-01-01

377

A solution for solid state detector and preamplifier protection, during HV application and removal transition periods  

International Nuclear Information System (INIS)

Surface barrier detectors may be damaged, because of microplasma breakdown, in rapid application of bias voltage. The high performance FETs of very low noise preamplifiers may also be damaged by rapid changes of the bias voltage. The electronic device described permits the gradual application and removal of the bias voltage, without any influence on the power supply specification. (Auth.).

378

Report on definitional mission: Hungary gas-fired power plants. Export trade information  

Energy Technology Data Exchange (ETDEWEB)

The U.S. Trade and Development Program (TDP) had received a request from the Hungarian Electricity Board (MVMT) for assistance in support of a feasibility study program to: (1) install new generation capability based on gas/oil fired combined cycle power plants, and (2) retrofit/refurbish a number of aging coal and oil fired steam plants. A Definitional Mission (DM) recommends that TDP fund the requested feasibility studies for new gas/oil fired combined cycle capabilities discussed in the Terms of Reference (TOR). Hungary will need to install significant new power capacity between now and the end of the century. Gas/oil fired combined cycle plants present probably the only option to install capacity rapidly. There is an opportunity for U.S. firms to supply technology and services with respect to these advanced power generation technologies.

1991-02-28

379

Rankine-Brayton engine powered solar thermal aircraft  

Energy Technology Data Exchange (ETDEWEB)

A solar thermal powered aircraft powered by heat energy from the sun. A Rankine-Brayton hybrid cycle heat engine is carried by the aircraft body for producing power for a propulsion mechanism, such as a propeller or other mechanism for enabling sustained free flight. The Rankine-Brayton engine has a thermal battery, preferably containing a lithium-hydride and lithium mixture, operably connected to it so that heat is supplied from the thermal battery to a working fluid. A solar concentrator, such as reflective parabolic trough, is movably connected to an optically transparent section of the aircraft body for receiving and concentrating solar energy from within the aircraft. Concentrated solar energy is collected by a heat collection and transport conduit, and heat transported to the thermal battery. A solar tracker includes a heliostat for determining optimal alignment with the sun, and a drive motor ...

2009-12-29

380

Feasibility study on the development of proton accelerator  

Energy Technology Data Exchange (ETDEWEB)

A feasibility on the development of a high energy proton accelerator to be used for R and D in the nuclear field of korea was studied. The proposed one is a proton linac with parameters of about 1 GeV, 20 mA which can supply enough neutrons by the spallation reaction to drive a subcritical reactor. It= is expected to solve the intrinsic problem in the nuclear field such as safety, nuclear waste, proliferation and resource. The study was carried out through a multi-institutional cooperation of universities, institute and industry for a national consensus. 5 refs., 8 tabs., 8 figs. (author)

1996-10-01

381

The Daya Bay Reactor Neutrino Experiment  

International Nuclear Information System (INIS)

The Daya Bay reactor neutrino experiment is designed to study the disappearance of antineutrinos from the Daya Bay nuclear power plant in China. The goal of this experiment is to measure the remaining unknown neutrino mixing parameter ?13 with high precision: sin2(2?13)<0.01. The experiment is presently under construction and it is anticipated that data acquisition will begin in 2011.

2009-12-17

382

The 6th GRS conference  

International Nuclear Information System (INIS)

On the 3. and 4. November 1982 the sixth conference of the Corporation for Reactor Safety (GRS) was held in Cologne's Guerzenich. The theme of this year's meeting was the 'Status of Risk Investigations at Nuclear Power Plants'. A principal topic was a report on findings made by the GRS during the 'Risk Oriented Analysis SNR-300'. The second topic comprised the newest developments within Phase B of the Risk Study of Water Pressure Reactors, the discussion of the dose/effect relationship and considerations on threshold risk values. (orig.).

383

Temperature coefficient in D_2O moderated reactor (Wolsung Unit 1)  

International Nuclear Information System (INIS)

The temperature coefficient has been investigated on the Wolsung nuclear power reactor, in which fuel is natural uranium dioxide and moderator heavy water. The numerical computations are carried out in terms of changes of the effective neutron multiplication factor with respect to fuel, moderator, and coolant temperatures. Those results are compared with the computed values of temperature coefficient based on the LATREP computer code. (author).

1977-01-01

384

In-situ maintenance of low-Z limiters in reactors  

Energy Technology Data Exchange (ETDEWEB)

In a reactor environment, the surface of a limiter or wall is primarily determined by the mechanism of erosion and deposition of surface material. It should be possible to use pellet injection to reduce net erosion to zero everywhere if low-Z materials are used for the surface. Erosion rates can, in general, be minimized by large area limiters and high plasma temperatures, which transmit power to the walls with less sputtering. Under ideal steady state conditions the wall surface is dominated by metallurgical effects in the wall.

1980-01-01

385

Comparison of calculated and measured irradiated wire data for HEU and mixed HEU/LEU cores in the ORR (Oak Ridge Research Reactor)  

Energy Technology Data Exchange (ETDEWEB)

Low power wire activations are being performed in the Oak Ridge Research Reactor (ORR) as part of the whole-core LEU demonstration experiments. Calculations of the demonstration cores, including simulation of the wire activations, are being performed at Argonne National Laboratory (ANL). This paper presents the results of comparisons for 293 wires from five cores and shows that, on the average, the integrated activities agree within 6%.

1986-01-01

386

Automated remote positioning and examination of FFTF reactor power characterization dosimeters  

Energy Technology Data Exchange (ETDEWEB)

The Fast Flux Test Facility (FFTF) reactor characterization by the Hanford Engineering Development Laboratory (HEDL) includes extensive neutronic measurements during startup and initial operation. To aid in the handling and counting of the thousands of passive dosimeters used as part of this effort, an automated dosimetry specimen handling, positioning, and counting system was designed and developed by Westinghouse Hanford for the Department of Energy.

1981-05-04

387

A computer program for estimating decommissioning costs for light water reactors  

Energy Technology Data Exchange (ETDEWEB)

This report discusses a desk-top computer program has been developed for estimating the costs, waste volumes, and occupational radiation exposures associated with decommissioning light-water reactor power stations. Cost categories and cost algorithms used in the program are discussed and a brief description of the user interface is given.

1993-02-01

388

Device for controlling feedwater at low power of nuclear power plants  

International Nuclear Information System (INIS)

Purpose: To provide a feedwater control device capable of minimizing the adverse response of steam drum level at low power. Consitution: In order to perform feedwater control at low power by the substantial control of three factors, that is, main steam flow rate, feedwater flow rate and steam drum level, the main steam flow rate is determined from the reactor output and feedwater rate is determined from the changes in the feedwater temperature due to the mixing of waters in the reactor clean up system and feedwater. If a difference is resulted between these flow rates, a starting feedwater regulator is controlled instantly to eliminate the difference. The water level in the steam drum is used for amending the difference from the final set value of the drum water level, by which the adverse response of the steam drum level can be minimized. (Seki, T.).

389

Prohibitions against the combustion of solid and liquid fuels in urban areas  

Energy Technology Data Exchange (ETDEWEB)

Much as it is accepted for pollution control reasons air pollution abatement still is the subject of heated debates. Pollutant emissions can considerably be reduced with the help of electric power supplies. In order not to prejudice electric power users tariffs have to be adapted to the prices of other energy sources available on the market. There is a general need for energy conservation, resource conservation and the reduction of carbon dioxide emissions. Thermal insulation is among the remedial measures. Fundamental air pollution abatement measures will have to be avoiding smog warnings which are known to considerably interfere with both economic and private activities.

1988-02-01

390

Lessons from Auckland  

Energy Technology Data Exchange (ETDEWEB)

The major distributor and retailer of electrical power to Auckland, New Zealand, is Mercury Energy Limited. Following the sequential failure of the four 110kV underground cables, two gas-filled and two oil-filled, which supply the central business district, power was interrupted for 29 days from the 20th February 1998. A government inquiry was instituted, to examine what happened, why, and what lessons could be drawn for the future. Inadequacies in Mercury Energy`s cable maintenance and operating procedures were identified. The findings of the inquiry and its recommendations are reported. (UK)

1998-08-01

391

Energy options and employment  

International Nuclear Information System (INIS)

Decision making about possible investment options for energy supply technology is usually based on economic criteria reflecting primarily the unit cost of energy and the return on capital invested. This study attempts to reverse the process. The chosen starting point is a UK investment programme geared towards reliance on conservation, renewable energy systems and the more efficient use of our remaining fossil fuels (through combined heat and power and district heating systems). The number and type of jobs likely to be created is then estimated and compared with the jobs likely to be created by the currently proposed nuclear power programme. (author).

392

Correct monitoring of stationary battery systems; Stationaere Batteriesysteme richtig ueberwacht  

Energy Technology Data Exchange (ETDEWEB)

There are many applications that necessitate reliable and permanent power supply, e.g. power stations, airports, computer centers or hospitals. The stationary battery systems must be monitored by efficient systems, e.g. Batlog. (orig.) [Deutsch] Viele Anwendungen verlangen eine permanent verfuegbare und zuverlaessige Stromversorgung. Kraftwerke, Flughaefen, Rechenzentren oder Krankenhaeuser muessen ihre Prozesse auch bei einem Netzausfall oder einer Versorgungsunterbrechung weiterbetreiben. Dies gelingt nur, wenn sich der entsprechende Energiespeicher in einsatzbereitem Zustand befindet. Die Ueberwachung der stationaeren Batterieanlagen erfordert leistungsfaehige Systeme wie Batlog. (orig.)

1998-10-01

393

Large eddy simulation based fire modeling applications for Indian nuclear power plant  

Energy Technology Data Exchange (ETDEWEB)

Full text of publication follows: The Nuclear Power Plants (NPPs) are always designed for the highest level of safety against postulated accidents which may be initiated due to internal or external causes. One of the external/internal causes, which may lead to accident in the reactor and its associated systems, is fire in certain vital areas of the plant. Conventionally, the fire containment approach and/or the fire confinement approach is used in designing the fire protection systems of NPPs. Indian NPPs (PHWRs) follow the combined approach to ensure plant safety and all newly designed plants are required to comply with the provisions of Atomic Energy Regulatory Board (AERB) fire safety Guide. In respect of older plants, the reassessment of adequacy of fire safety provisions in the light of current advances has becomes essential so as to decide upon the steps for retrofitting. Keeping this in mind the deterministic fire ...

2005-07-01

394

Stationary low power reactor No. 1 (SL-1) accident site decontamination & dismantlement project  

Science.gov (United States)

The Army Reactor Area (ARA) II was constructed in the late 1950s as a test site for the Stationary Low Power Reactor No. 1 (SL-1). The SL-1 was a prototype power and heat source developed for use at remote military bases using a direct cycle, boiling water, natural circulation reactor designed to operate at a thermal power of 3,000 kW. The ARA II compound encompassed 3 acres and was comprised of (a) the SL-1 Reactor Building, (b) eight support facilities, (c) 50,000-gallon raw water storage tank, (d) electrical substation, (e) aboveground 1,400-gallon heating oil tank, (f) underground 1,000-gallon hazardous waste storage tank, and (g) belowground power, sewer, and water systems. The reactor building was a cylindrical, aboveground facility, 39 ft in diameter and 48 ft high. The lower portion of the ...

1995-11-01

395

{sup 242m}Am fueled nuclear battery  

Energy Technology Data Exchange (ETDEWEB)

A nuclear battery based on the direct energy conversion of the fission products is presented. Such energy conversion is possible by using a nuclear reactor with ultra-thin fuel elements of 0.2 {mu}m of {sup 242m}Am. The amount of nuclear fuel is 376 g and the dimensions of the battery are 2.4x2.4x2.4 m{sup 3} (including the vacuum spacing), with a BeO moderator and Be electrodes. The total power of the reactor is 10.6 MW and the electrical power is 0.652 MW.

2004-10-01

396

The hunt for ?13 at the Daya Bay nuclear power plant  

International Nuclear Information System (INIS)

The Daya Bay reactor neutrino experiment is located at the Daya Bay nuclear power plant in Shenzhen, China. The experiment deploys eight 'identical' antineutrino detectors to measure antineutrino fluxes from six 2.9 GWth reactor cores in three underground experimental halls at different distances. The target zone of the Daya Bay detector is filled with 20 t 0.1% Gd doped LAB liquid scintillator. The baseline uncorrelated detector uncertainty is ?0.38% using current experimental techniques. Daya Bay can reach a sensitivity of sin22?13<0.01 with baseline uncertainties after 3 years of data taking.

2010-03-30

397

Prevention of lung cancer by remediation of residential exposure to radon daughters  

Energy Technology Data Exchange (ETDEWEB)

The United States Bonneville Power Administration (BPA), as part of an energy conservation programme in the states of Washington, Oregon, Idaho, Wyoming, and Montana, has collected over 36,000 residential radon concentration measurements. Data were collected between 1983 and 1989 with ambient {alpha} etched track dosemeters. Based on the linear risk coefficient from the BEIR IV report for lifetime lung cancer in smokers and non-smokers, numbers of lung cancer cases attributable to radon exposure were predicted. Numbers of baseline lung cancer cases and numbers of these that were preventable by remediation were also estimated. Remediation to 10 pCi.1{sup -1}, to 4 pCi.1{sup -1}, and to outdoor levels were considered. With vital statistics data, results were extrapolated to populations in the states represented by the BPA data. Costs of remediation were estimated. Results were evaluated in terms of cost per cancer saved and per cent reduction in ...

1991-01-01

398

Corrosion and reliability of PWR power plants  

International Nuclear Information System (INIS)

Corrosion is increasingly becoming an important factor reducing the reliability of many nuclear power plant components. The significance is evaluated of corrosion phenomena with respect to the reliability of primary circuit components of LWR's, viz., the reactor pressure vessel, primary piping, steam generator, and fuel elements. The mechanism of corrosion phenomena is explained and methods of minimizing their effects are presented. An analysis is made of the needs to solve the corrosion problems of nuclear power plants from the point of view of Czechoslovak producers and research and development activities. International cooperation is reviewed and main problems are formulated on which the solution of corrosion problems of structural materials used in WWER type nuclear power plants should be focussed. (author).

399

Pursuing energy supply options: cost effective R and D strategies. US Library of Congress. Report for the Joint Economic Committee, US Congress, April 27, 1981  

Energy Technology Data Exchange (ETDEWEB)

Large amounts of US public funds are deviated to energy-related R and D conflicts with the country's simultaneous attempts to control inflation and to limit federal government expansion. Congress must concentrate the funds at its disposal upon a manageable number of energy technologies - those most likely to improve the supply side of the domestic energy equation while maintaining an adequate return on investment. An examination of a wide array to technology alternatives concludes that (1) the development of unconventional gas would yield a large return while requiring only limited federal R and D support, (2) combined-cycle coal gasification and the manufacture of low- and medium-Btu gas need relatively little government aid and produce moderate returns, (3) although requiring limited support, energy from municipal solid waste (MSW) yields a small return, and (4) high-Btu coal gasification needs extensive federal funding and produces ...

1981-01-01

400

Supporting Thermal Hydraulic Calculations for the SGTR Event Tree of SMART Level 1 PSA  

International Nuclear Information System (INIS)

SMART (System integrated Modular Advanced ReacTor) , is under development at the Korea Atomic Energy Research Institute (KAERI). SMART is an integral type pressurized water reactor which contains a pressurizer, 4 reactor coolant pumps (RCPs), and 8 steam generator cassettes(S/Gs) in a single reactor vessel. This reactor has substantially enhanced its safety with an integral layout of its major components, 4 trains of safety injection system (SIS), and an adoption of 4 trains of passive residual heat removal system (PRHRS) instead of an active auxiliary feedwater system . The thermal power is 330 MWth. During the conceptual design stage, a preliminary PSA was performed. PSA results identified that a steam generator tube rupture (SGTR) is one of the most important initiating events which results in a high core damage frequency. Clear understanding of accident ...

2010-10-01

401

Analysis of the requirements for economic magnetic fusion  

Energy Technology Data Exchange (ETDEWEB)

A generic reactor model is used to examine the economic viability of electricity generation by magnetic fusion. The simple model uses components which are representative of those used in previous reactor studies of deuterium-tritium burning tokamaks, stellarators, bumpy tori, reverse field pinches and tandem mirrors. Conservative costing assumptions are made. The generic reactor is not a tokamak but rather it is intended to emphasize what is common to all magnetic fusion reactors. The reactor uses a superconducting toroidal coil set to produce the dominant magnetic field. To this extent it is a less good approximation to systems, such as the reversed field pinch in which the main field is produced by a plasma current. The main output of the study is the cost of electricity as a function of the weight and size of the fusion core - blanket, shield, structure and coils. The model shows ...

1986-01-01

402

Design and safety evaluation of radioactive gas handling and storage in the FFTF  

International Nuclear Information System (INIS)

During the operation of the Fast Flux Test Facility (FFTF), radioactive gases, primarily xenon and krypton, will be produced which will require processing and storing. Two systems have been installed in the FFTF for handling these gases: (1) one to handle, primarily, the reactor cover gas system, and (2) a second to handle the cells and cover gas systems, other than the reactor, whose atmosphere may become contaminated. The system that processes the reactor cover gas, which is argon, is called the Radioactive Argon Processing System (RAPS). The effluent argon from RAPS will normally be sufficiently decontaminated to allow its reuse as the reactor cover gas. If the radioactive level in the RAPS becomes too high, the exhaust stream will be diverted to the Cell Atmosphere Processing System (CAPS), a system which can function as a backup to RAPS. The design and operation of the RAPS and CAPS systems are ...

1976-06-13

403

Challenges for Lithuania: Ignalina NPP Early Closure  

International Nuclear Information System (INIS)

As a condition of accession into the European Union (EU), Lithuania is committed to the closure and decommissioning of Ignalina NPP comprising two RBMK-1500 reactor units (Fig. 1). It was agreed in a special protocol to the Accession Treaty that, in return for adequate EU financial assistance, Unit 1 would be closed before 2005 and Unit 2 by the end of 2009. The first unit was duly shut down on December 31, 2004. Lithuania, which has borders with Russia (Kaliningrad territory), Poland, Latvia and Belarus, spent fifty years as part of the Soviet Union and was deeply integrated into its economy and electrical infrastructure. At the break-up of the USSR, Lithuania inherited electricity generating capacity designed to supply the north-west region including ownership of Ignalina NPP located in the north-east of the country. Ignalina NPP Unit 1 was commissioned in 1983, Unit 2 in 1987; the planned lifespan of each unit was 30 years. Construction of a ...

2008-01-01

404

Foreign wood fuel supply for power generation in the Netherlands. Final report  

Energy Technology Data Exchange (ETDEWEB)

In the Netherlands, the interest in biomass for electricity generation has increased, mainly due to environmental reasons. Currently, the Dutch energy sector is investigating technologies which can reduce CO{sub 2} emissions. The growth of biomass and its subsequent utilization for energy purposes circulates recycled atmospheric carbon and has no net discharge of CO{sub 2}. To reduce emissions from coal-fired power plants biomass co-firing options are investigated. After exhaustion of internal supplies of wood wastes and other residues an extra amount of 1.02 Mt{sub 20} would be needed. Two supply options exist: the use of internal energy crops and the import of biomass. Because production of energy crops in the Netherlands is a rather expensive option, biomass procurement and production outside the Netherlands is studied. Two countries were investigated for the possible import of biomass: Estonia and Uruguay. Estonia has ...

1995-08-01

405

Quarterly coal report, October--December 1997  

Energy Technology Data Exchange (ETDEWEB)

The Quarterly Coal Report (QCR) provides comprehensive information about US coal production, distribution, exports, imports, receipts, prices, consumption, and stocks to a wide audience, including Congress, Federal and State agencies, the coal industry, and the general public. Coke production, consumption, distribution, imports, and exports data are also provided. The data presented in the QCR are collected and published by the Energy Information Administration (EIA) to fulfill data collection and dissemination responsibilities. This report presents detailed quarterly data for october through December 1997 and aggregated quarterly historical data for 1991 through the third quarter of 1997. Appendix A displays, from 1991 on, detailed quarterly historical coal imports data, as specified in Section 202 of the energy Policy and Conservation Amendments Act of 1985 (Public Law 99-58). Appendix B gives selected quarterly tables converted to metric ...

1998-05-01

406

Government response to public consultation. Offshore natural gas storage and liquefied natural gas import facilities  

Energy Technology Data Exchange (ETDEWEB)

As its indigenous gas supplies decline, the UK will need to import more gas. In November 2006, the Department of Trade and Industry issued a consultation on revising the consent regime for offshore gas storage and offshore liquefied natural gas unloading. A total of 27 responses had been received by the closing date of 16 February 2007 from a variety of interest parties including developers and their representative organisations, consultants, environmental organisations, maritime organisations, heritage organisations and other public bodies. This report presents the Government's response to the views expressed by these respondents. The majority of respondents supported the Government's proposals to put in place new legislation to permit offshore gas storage activities. Many believed new legislation was necessary to provide the legal certainty necessary ro encourage offshore development and investment in such developments. ...

2007-05-15

407

Electric power monthly: October 1995, with data for July 1995  

Energy Technology Data Exchange (ETDEWEB)

The Electric Power Monthly (EPM) presents monthly electricity statistics for a wide audience including Congress, Federal and State agencies, the electric utility industry, and the general public. The purpose of this publication is to provide energy decisionmakers with accurate and timely information that may be used in forming various perspectives on electric issues that lie ahead. The Coal and Electric Data and Renewables Division; Office of Coal, Nuclear, Electric and Alternate Fuels, Energy Information Administration (EIA), Department of Energy prepares the EPM. This publication provides monthly statistics at the State, Census division, and US levels for net generation, fossil fuel consumption and stocks, quantity and quality of fossil fuels, cost of fossil fuels, electricity sales, revenue, and average revenue per kilowatthour of electricity sold. Data on net generation, fuel consumption, fuel ...

1995-10-19

408

Electric power monthly, December 1997 with data for September 1997  

Energy Technology Data Exchange (ETDEWEB)

The Electric Power Monthly (EPM) presents monthly electricity statistics for a wide audience including congress, Federal and State agencies, the electric utility industry, and the general public. The purpose of this publication is to provide energy decisionmakers with accurate and timely information that may be used in forming various perspectives on electric issues that lie ahead. This publication provides monthly statistics at the State, Census division, and US levels for net generation, fossil fuel consumption and stocks, quantity and quality of fossil fuels, cost of fossil fuels, electricity retail sales, associated revenue, and average revenue per kilowatthour of electricity sold. In addition, data on net generation, fuel consumption, fuel stocks, quantity and cost of fossil fuels are also displayed for the North American Electric Reliability Council (NERC) regions. The EIA publishes statistics in ...

1997-12-01

409

Temporal variations of fluoride concentration in Isparta public water system and health impact assessment (SW-Turkey)  

British Library Electronic Table of Contents (United Kingdom)

Water?rock interaction is one of the prime factors affecting the fluoride contents of surface and groundwater. If fluoride concentration of drinking water has been neglected, excess fluoride can cause serious dental and medical problems on human health, which is well known at Golcuk-Isparta region. In the research area, Egirdir lake, Golcuk lake and surrounding springs have been utilized as drinking water sources. Golcuk lake water and surrounding groundwaters have high fluoride content (1.4?4.6?mg/l), which is above the WHO standards. Fluoride is predominantly supplied by dissolution of fluoride within the fluormicas of volcanics during the circulation of water. Fluoride concentrations of waters have shown variations for dry and rainy seasons depending on the degree of interaction between...

2008-01-01

410

Life cycle assessment of electric mobility: answers and challenges?Zurich, April 6, 2011  

British Library Electronic Table of Contents (United Kingdom)

Introduction Alternative ways and means of transportation are necessary in order to reduce the environmental impacts of mobility. In the recent years, biofuels were first seen as a main option and then LCA showed also possible hazards of this development. Recently, public interest is rapidly shifting towards electromobility. Therefore it is necessary to also gain better knowledge about the environmental impacts of this technology. This includes a modelling of the pathways of the necessary increase in electricity supply and an appropriate modelling of battery manufacture. Summary of data presented At this forum most recent results of life cycle assessment studies of electric car driving compared to driving fossil- and agro-fuelled cars were presented. The environmental performance of indivi...

2011-01-01

411

Innovation in sustainable energy in the Netherlands. Availability of capital and required government support  

Energy Technology Data Exchange (ETDEWEB)

To make the Dutch energy system more sustainable as formulated in the objectives of the recently constituted Task Force Energietransitie (Energy Transition), additional investments by the government in sustainable energy are needed. One of the ideas is to start a public-private risk bearing fund that invests in Netherlands based innovation projects in the area of sustainable energy. The ingoing assumption is that there is a shortage of capital supply for innovation projects that are in between the Research and Development phase and the market introduction phase, and that the government can attract further commercial private capital by co-investing itself. The Ministry of Economic Affairs has asked Bain and Company to perform a due diligence on the validity of the in-going assumptions for raising such a Venture Capital fund. This report contains the key conclusions of the study performed in June and the first half of July of 2006.

2006-07-15

412

Surfactant studies for bench-scale operation. Quarterly technical progress report No. 1, 1 July-30 September 1992  

Energy Technology Data Exchange (ETDEWEB)

A phase 2 study was initiated to investigate surfactant-assisted coal liquefaction, with the objective of quantifying the enhancement in liquid yields and product quality. This publication covers the first quarter of work. The major accomplishments were: the refurbishment of the high-pressure, high-temperature reactor autoclave, the completion of four coal liquefaction runs with Pittsburgh No. 8 coal, two each with and without sodium lignosulfonate surfactant, and the development of an analysis scheme for the product liquid filtrate and filter cake. Initial results at low reactor temperatures show that the addition of the surfactant produces an improvement in conversion yields and an increase in lighter boiling point fractions for the filtrate.

1992-12-01

413

Practical technological benefits of SRE decommissioning  

Energy Technology Data Exchange (ETDEWEB)

The decommissioning of the Sodium Reactor Experiment is essentially complete. Contaminated materials, equipment, and soil were removed, decreasing the residual radioactivity to levels acceptable for future unrestricted use of the site. The fuel was removed and declad, tooling and techniques to support the decommissioning were developed, bulk sodium and residual sodium films were removed, coolant systems were dismantled, the reactor vessel was dissected, the interior surfaces of the facilities were decontaminated, and waste materials were packaged and shipped to burial sites. Radiation exposure to workers and the public was within the guidelines and as low as reasonably achievable. In performing the project, new decontamination techniques were tested, decontamination equipment was evaluated, and waste disposal methods were developed.

1982-01-01

414

Exploring research of factors affecting public acceptance of nuclear energy. Result of a survey at Suginami ward, Tokyo  

Energy Technology Data Exchange (ETDEWEB)

The purpose of this research is to clarify how psychological factor's impact on public acceptance of nuclear energy varies with people's degree of knowledge. For this purpose, we carried out questionnaire survey about nuclear energy at Suginami ward, Tokyo. After collecting data, we applied factor analysis to the data, and found 4 factors: Trust in the Authorities, Superiority of Nuclear Power Generation, Benefit for Nuclear Power Plants' Siting Areas, and Risk Perception about Nuclear Technology. In addition, using multiple regression analysis, we evaluated the impact of the 4 factors on 2 issues: the decision for or against nuclear policy and the reaction to nuclear power plant siting. Consequently, we found the change of impact of all 4 factors on the 2 issues. Especially, the impact of the 4 factors to the reaction to nuclear power plant siting was ...

2003-03-01

415

Exploring research of factors affecting public acceptance of nuclear energy. Result of a survey at Suginami ward, Tokyo  

International Nuclear Information System (INIS)

The purpose of this research is to clarify how psychological factor's impact on public acceptance of nuclear energy varies with people's degree of knowledge. For this purpose, we carried out questionnaire survey about nuclear energy at Suginami ward, Tokyo. After collecting data, we applied factor analysis to the data, and found 4 factors: Trust in the Authorities, Superiority of Nuclear Power Generation, Benefit for Nuclear Power Plants' Siting Areas, and Risk Perception about Nuclear Technology. In addition, using multiple regression analysis, we evaluated the impact of the 4 factors on 2 issues: the decision for or against nuclear policy and the reaction to nuclear power plant siting. Consequently, we found the change of impact of all 4 factors on the 2 issues. Especially, the impact of the 4 factors to the reaction to nuclear power plant siting was drastically changed by ...

2003-03-01

416

Paul Scherrer Institute Scientific Report 2000. Volume IV: Nuclear Energy and Safety  

Energy Technology Data Exchange (ETDEWEB)

Nuclear energy related research in Switzerland is concentrated at PSI's Nuclear Energy and Safety Research Department (NES). The activities of the department are concentrated on three main domains of: Safety and related problems of operating plants; safety features of future reactor and fuel cycles; waste management. Comprehensive assessments of energy systems are carried out in cooperation with PSI's General Energy Research Department. Many of the programs are part of collaborations with universities, industry, or international organisations. Progress in 2000 in these topical areas is described in this report. A list of scientific publications in 2000 is also provided.

2001-03-01

417

Neutron cross section measurements using the Oak Ridge Electron Linear Accelerator  

Energy Technology Data Exchange (ETDEWEB)

During this reporting period the work supported by the US Department of Energy Grant No. DE-FG02-87ER40326.A005 has resulted in two publications and two papers presented at professional meetings. The neutron scattering measurement for this budget period has been completed along with scattering measurements for carbon {sup 88}Sr, {sup 40}Ar, {sup 90}Zr, {sup 208}Pb, {sup 40}Ca and {sup 28}Si. The carbon scattering yield serves to define the detector efficiencies. The silicon sample was available and is of importance in both nuclear physics and reactor physics.

1992-06-01

418

LOBI/B-R1M, Loop for Blowdown Investigation, PWR Single-Ended Cold-Leg Break Experiment B EXP.B  

International Nuclear Information System (INIS)

1 - Description of test facility: The LOBI facility is a 1/700 scale model of a four loop PWR and has two primary loops, the intact loop representing three loops and the broken loop representing one loop of a four-loop PWR. The reactor pressure vessel model contains an electrically heated rod-bundle with 64 rods and a heated length of 3.9 m. The nominal heating power is 5.3 MW. The downcomer is of annular shape. An upper head simulator is connected to the vessel. Each of the two primary loops contains a pump and a steam generator. The different mass flows in the loops are established by the pump speeds, since the two pumps are identical. Heat is removed from the steam generators by a secondary system. ECC water can be supplied from two accumulators, one for each loop. Cold or hot leg as well as combined injection can be simulated. The LOBI test facility is the only high pressure integral test facility within the European ...

419

Computer Network Security: Best Practices for Alberta School Jurisdictions.  

Science.gov (United States)

This paper provides a snapshot of the computer network security industry and addresses specific issues related to network security in public education. The following topics are covered: (1) security policy, including reasons for establishing a policy, risk assessment, areas to consider, audit tools; (2) workstations, including physical security, protecting workstation components, and computer viruses; (3) the local network, including the OSI (Open Systems Interconnection) reference model, protocols, network segmentation, network management, network sniffing, and data encryption; (4) servers, including UNIX and other server operating systems; (5) remote access, including technologies, remote access servers, protocols, and authentication/authorization; (6) crackers and hackers, including threats and hacking tools/techniques; (7) Internet firewalls, including functions, issues and problems, types, rules, logs, firewall ...

1999-02-01

420

DOE supports market-based pricing in case before FERC  

Energy Technology Data Exchange (ETDEWEB)

The Department of Energy has used its seldom-used statutory authority and filed comments with the Federal Energy Regulatory Commission urging support for Public Service Company of Indiana's request that the FERC allow it to sell up to 450 megawatts of firm power to eligible wholesale purchasers at negotiated or market-based rates in exchange for open transmission access for other generators.

1990-04-12

421

Coal uses and upgrading processes  

Energy Technology Data Exchange (ETDEWEB)

The paper discusses the status of coal as a raw material and energy source. After referring to coal preparation and the costs it involves the author deals with coal/liquid suspensions and their fueling uses. Access is given to different aspects concerning the use of coal for electric power and heat generation. They include pollution abatement measures, economic analyses and fuel engineering in the case of coal. Further sections are dedicated to upgrading procedures such as the gasification, liquefaction and coking of coal. A bibliography informs the reader about further publications available on the subject. (HAG).

1986-04-01

422

All wired up and ready to go  

Energy Technology Data Exchange (ETDEWEB)

Electric cars have long been seen as science fiction. This may be changing. As the 1990s began, several companies chose to launch publicity campaigns for electric vehicles. In California, experimental programmes are gaining momentum, in the context of LA's appalling air pollution problems and tightening clean air standards. Supporters claim that electric motive power is a key to solving several environmental problems involving atmospheric pollution. These claims are examined. (author).

1990-01-01

423

Interaction among competitive producers in the electricity market: An iterative market model for the strategic management of thermal power plants  

International Nuclear Information System (INIS)

The liberalization of the electricity sector requires utilities to develop sound operation strategies for their power plants. In this paper, attention is focused on the problem of optimizing the management of the thermal power plants belonging to a strategic producer that competes with other strategic companies and a set of smaller non-strategic ones in the day-ahead market. The market model suggested here determines an equilibrium condition over the selected period of analysis, in which no producer can increase profits by changing its supply offers given all rivals' bids. Power plants technical and operating constraints are considered. An iterative procedure, based on the dynamic programming, is used to find the optimum production plans of each producer. Some combinations of power plants and number of producers are analyzed, to simulate for instance the decommissioning of old ...

2006-12-01

424

Southern receiver system: Environmental impact assessment status report: Conawapa to Winnipeg Power Transmission Complex  

Energy Technology Data Exchange (ETDEWEB)

The Conawapa-Winnipeg Power Transmission Complex includes five interrelated transmission and conversion facilities. This booklet describes work done on the upgrade of the southern receiver system, one component of the complex. The southern receiver system is composed of a network of high voltage transmission lines and station facilities. The booklet includes a description of the upgrade, the project setting, short and long-term effects and impact management, and the next steps to be taken in the process, including the regulatory process and public consultation.

1992-01-01

425

Bibliography on augmentation of convective heat and mass transfer  

International Nuclear Information System (INIS)

Heat transfer augmentation has developed into a major specialty area in heat transfer research and development. A bibliography of world literature on augmentation is presented. The literature is classified into passive augmentation techniques, which require no external power, and active techniques, which do require external power. The fourteen techniques are grouped in terms of their application to the various modes of heat transfer. Mass transfer is included for completeness. Key words are included with each citation for technique/mode identification. The total number of publications cited is 1,967, including 75 surveys of various techniques and 42 papers on performance evaluation of passive techniques. Patents are not included as they will be the subject of a future topical report.

1979-01-01

426

General formulation of neutron noise for fast reactor systems  

Energy Technology Data Exchange (ETDEWEB)

A general space- and energy-dependent formalism is developed in order to analyze zero-power neutron noise experiments in fast reactor systems. A generalized dispersion equation is combined with theoretical expressions for the experimentally measured power spectral density and variance-to-mean ratio which makes it possible to express these quantities in terms of a double moment of the Laplace and Fourier transformed Green's function of a slowing-down operator rather than those of the full Boltzmann operator. Several spatial approximations are analyzed in the context of the general formalism. In each case, the power spectral density and variance-to-mean ratio are written in terms of an appropriate fast reactor dispersion law for the medium which can be calculated from the solution to a simple slowing-down equation. The resultant expression for the power ...

1982-01-01

427

Steam generator tube performance: experience with water-cooled nuclear power reactors during 1979  

International Nuclear Information System (INIS)

The performance of steam generator tubes in water-cooled nuclear power reactors has been reviewed for 1979. Tube failures occurred at 38 of the 93 reactors surveyed. Causes of these failures and procedures designed to deal with them are described. The defect rate was twice that in 1978 but still lower than the two previous years. Methods being employed to detect defects include increasing use of multifrequency eddy-current testing and a trend to full-length inspection of all tubes. To reduce the incidence of tube failures by corrosion, plant operators are turning to full-flow condensate demineralization and more leak-resistant condenser tubes. (author).

1994-10-18

428

Reference equilibrium core with central flux irradiation facility for Pakistan research reactor-1  

International Nuclear Information System (INIS)

In order to assess various core parameters a reference equilibrium core with Low Enriched Uranium (LEU) fuel for Pakistan Research Reactor (PARR-1) was assembled. Due to increased volume of reference core, the average neutron flux reduced as compared to the first higher power operation. To get a higher neutron flux an irradiation facility was created in centre of the reference equilibrium core where the advantage of the neutron flux peaking was taken. Various low power experiments were performed in order to evaluate control rods worth and neutron flux mapping inside the core. The neutron flux inside the central irradiation facility almost doubled. With this arrangement reactor operation time was cut down from 72 hours to 48 hours for the production of the required specific radioactivity. (author)

2008-07-01

429

Electronic imaging system for neutron radiography at a low power research reactor  

Energy Technology Data Exchange (ETDEWEB)

This paper describes an electronic imaging system for producing real time neutron radiography from a low power research reactor, which will allow inspections of samples with high efficiency, in terms of measuring time and result analysis. This system has been implanted because of its potential use in various scientific and industrial areas where neutron radiography with photographic film could not be applied. This real time system is installed in neutron radiography facility of Argonauta nuclear research reactor, at the Instituto de Engenharia Nuclear of the Comissao Nacional de Energia Nuclear, in Brazil. It is adequate to perform real time neutron radiography of static and dynamic events of samples.

2010-08-15

430

Electronic imaging system for neutron radiography at a low power research reactor  

International Nuclear Information System (INIS)

This paper describes an electronic imaging system for producing real time neutron radiography from a low power research reactor, which will allow inspections of samples with high efficiency, in terms of measuring time and result analysis. This system has been implanted because of its potential use in various scientific and industrial areas where neutron radiography with photographic film could not be applied. This real time system is installed in neutron radiography facility of Argonauta nuclear research reactor, at the Instituto de Engenharia Nuclear of the Comissao Nacional de Energia Nuclear, in Brazil. It is adequate to perform real time neutron radiography of static and dynamic events of samples.

2010-08-01

431

Clean combustion of solid fuels  

International Nuclear Information System (INIS)

A chemical-looping process is proposed for the clean combustion of solid fuels for electric power or heat generation. The process is based on coal gasification with CO_2 to produce CO. The CO then reduces CaSO_4, which is used as an oxygen carrier, in a separate reactor to give CaS and CO_2. A portion of the CO_2 is recycled for the gasification stage and the rest can be sent for sequestration. The CaS is sent to another reactor for oxidation with air and to generate heat or power. The overall thermal effect is the same as direct combustion, but separation of CO_2 and other pollutants, such as sulphur, is achieved. In comparison with conventional chemical-looping combustion of natural gas, much less water is present in the CO_2 product, and hence the loss of heat energy and corrosion of the fuel-reactor system can be reduced.

2008-01-01

432

Decommissioning of U.S. uranium production facilities  

Energy Technology Data Exchange (ETDEWEB)

From 1980 to 1993, the domestic production of uranium declined from almost 44 million pounds U{sub 3}O{sub 8} to about 3 million pounds. This retrenchment of the U.S. uranium industry resulted in the permanent closing of many uranium-producing facilities. Current low uranium prices, excess world supply, and low expectations for future uranium demand indicate that it is unlikely existing plants will be reopened. Because of this situation, these facilities eventually will have to be decommissioned. The Uranium Mill Tailings and Radiation Control Act of 1978 (UMTRCA) vests the U.S. Environmental Protection Agency (EPA) with overall responsibility for establishing environmental standards for decommissioning of uranium production facilities. UMTRCA also gave the U.S. Nuclear Regulatory Commission (NRC) the responsibility for licensing and regulating uranium production and related activities, including decommissioning. Because there are many issues associated with ...

1995-02-01

433

Utilization of geothermal energy in the USSR  

International Nuclear Information System (INIS)

This paper reports that at present geothermal energy is utilized in the USSR mostly for district heating, and for industrial and agricultural purposes. The populations of 7 towns have district heating that is supplied by thermal waters. The population supplied totals about 125,000 people. The total area of greenhouses is 850,000 m"2. Electric energy generated at geothermal power stations still remains negligible with the installed capacity of the single Pauzhetka station (Kamchatka) being 11 MW. another station at Mutnovka is currently under construction and is expected to be producing 50 MW by 1992 and 200 MW by 1998. The proven geothermal resources in the USSR provide hope for a significant increase in the utilization of the earth's deep heat in the near future.

1990-08-20

434

High voltage cable in municipal electricity supply  

Energy Technology Data Exchange (ETDEWEB)

The author explains current developments in high voltage cable technology and subsequently describes problems inherent in its application, from the users viewpoint, in municipal electricity supply. The planning of a high voltage cable network and the selection of a specific type of cable are not only dependent on the typical properties of various cables but to a major degree also on the feasible laying technique, the power transmitted, the costs, the stellation treatment of the high voltage network, the acceptance requirement, the inductive influence from telecommunication cable, thermal influences from the environment, eventual safeguards from mechanical and chemical damage to the network, frequency of failure and surveillance and breakdown location. In conclusion, the author portrays potential developments in the fields of high and maximum voltage cable from the perspectives of today.

1980-12-22

435

Fundamental limits on beam stability at the advanced photon source  

International Nuclear Information System (INIS)

Orbit correction is now routinely performed at the few-micron level in the Advanced Photon Source (APS) storage ring. Three diagnostics are presently in use to measure and control both AC and DC orbit motions: broad-band turn-by-turn rf beam position monitors (BPMs), narrow-band switched heterodyne receivers, and photoemission-style x-ray beam position monitors. Each type of diagnostic has its own set of systematic error effects that place limits on the ultimate pointing stability of x-ray beams supplied to users at the APS. Limiting sources of beam motion at present are magnet power supply noise, girder vibration, and thermal timescale vacuum chamber and girder motion. This paper will investigate the present limitations on orbit correction, and will delve into the upgrades necessary to achieve true sub-micron beam stability.

1998-12-10

436

The socio-economic effects of the use of forest chips from logging residues and small-sized trees in energy production; case study; Pienpuuhakkeen ja hakkuutaehdehakkeen energiakaeytoen sosioekonomiset vaikutukset; case-tarkastelu -osaprojekti  

Energy Technology Data Exchange (ETDEWEB)

The aim of this case study is to analyse the socio-economic effects of forest fuel supply and use chains. Two of the four cases are rural district heating plants. In Perho, the co-operative organisation of forest owners maintains the fuel supply and operates the plant. In Ruukki, the local forestry association supplies forest chips to the plant. These medium-scale plants use small-sized trees from young thinning stands as their main fuel. The trees are felled manually. The other two cases are large power plants. Alholmens Kraft's new power plant in Pietarsaari aim to use 250 000 solid-m3 of forest chips annually. The logging residues are hauled to the plant as bales using traditional timber harvesting equipment or as bulk material. At young thinning stands the trees are harvested using an accumulating feller buncher. The Toppila I and II power plants in ...

2003-07-01

437

Study on tritium activity build-up in moderator and primary heat transport systems in 540 MWe reactor  

International Nuclear Information System (INIS)

Tarapur Atomic Power Station unit-4 is first 540 MWe pressurized heavy water reactor. Heavy water is used as the coolant and moderator. With reactor operation tritium is formed by absorption of neutron by Deuterium atoms. Experience in the 220 MWe indicates that tritium is main contributor to the internal dose of radiation workers. Study on Tritium build up in Primary Heat Transport (PHT) and Moderator (MOD) system was carried out at the initial stage of the operation of the unit-3 and 4. This paper brings out tritium activity buildup in the PHT and MOD systems and its comparison with 220 MWe reactors. This paper helps in estimation of the internal dose contribution to the radiation workers at TAPS 3 and 4. (author)

2006-11-13

438

Study on tritium activity build-up in moderator and primary heat transport (PHT) systems in 540 MWe reactor  

International Nuclear Information System (INIS)

Tarapur Atomic Power Station unit-4 is first 540 MWe pressurized heavy water reactor. Heavy water is used as the coolant and moderator. With reactor operation tritium is formed by absorption of neutron by deuterium atoms. Experience in the 220 MWe indicates that tritium is main contributor to the internal dose of radiation workers. Study on tritium build up in Primary Heat Transport (PHT) and Moderator (MOD) system was carried out at the initial stage of the operation of the unit-4. This paper brings out tritium activity buildup in the PHT and MOD systems and its comparison with 220 MWe reactors. This paper helps in estimation of the internal dose contribution to the radiation workers at TAPS 3 and 4. (author)

2005-11-23

439

Solar thermal cracking of methane in a particle-flow reactor for the co-production of hydrogen and carbon  

British Library Electronic Table of Contents (United Kingdom)

An experimental investigation on the thermal decomposition of CH4 into C and H2 was carried out using a 5kW particle-flow solar chemical reactor tested in a solar furnace in the 1300-1600K range. The reactor features a continuous flow of CH4 laden with mm-sized carbon black particles, confined to a cavity receiver and directly exposed to concentrated solar irradiation of up to 1720 suns. The reactor performance was examined for varying operational parameters, namely the solar power input, seed particle volume fraction, gas volume flow rate, and CH4 molar concentration. Methane conversion and hydrogen yield exceeding 95% were obtained at residence times of less than 2.0s. A solar-to-chemical energy conversion efficiency of 16% was experimentally reached, and a maximum value of 31% was numer...

2009-01-01

440

Preliminary investigation of the /sup 252/Cf-source-driven noise analysis method of subcriticality measurement in LWR fuel storage and initial loading applications  

Energy Technology Data Exchange (ETDEWEB)

The ability of the /sup 252/Cf-source-driven neutron noise analysis method to measure subcriticality has been demonstrated in a variety of experimental configurations of fissile materials. Calculations for an approximately 4-m-dia configuration of light water reactor (LWR) fuel elements indicated the feasibility of measuring the subcriticality of large, loosely coupled arrays of LWR fuel elements by this same method. These analysis suggested application to the initial loading of both pressurized and boiling water reactors, zero-power testing of reactors (such as shutdown margin measurements after initial loading), light water reactor refueling, and safe storage of LWR spent fuel. In the fuel storage application, direct measurement of subcriticality in the actual fuel storage facilities provides the parameter which is directly related to criticality safety.

1984-01-01

441

Oak Ridge Research Reactor. Quarterly report, July, August, and September 1984  

Energy Technology Data Exchange (ETDEWEB)

The ORR operated at an average power level of 29.7 MW for 85.3% of the time during this period. The reactor was shut down on fifteen occasions, nine of which were unscheduled. Reactor downtime needed for refueling and checks was normal. The reactor remained available for operation 88.3% of the time. Special tests completed during the quarter included: (1) transfer of LEU fuel elements CLE-202 and NLE-201 from core positions B-9 and B-2 to core positions C-5 and C-6 for continued operation; and (2) calculation of maximum heat flux in LEU elements CLE-201 and NLE-202 in core positions A-2 and A-8. In-service inspections included inspections of ORR decay tank, primary heat exchanger No. 4, and the 24-in. strainer.

1985-03-01

442

A Detailed Investigation on Human-Related Unplanned Reactor Trip Events in Korea  

International Nuclear Information System (INIS)

Human errors have been reported as one of the most significant causes of major events in nuclear power plants (NPPs). For example, Kim and Park found that about 23% of the major events that occurred at NPPs in Republic of Korea from 1986 to 2006 were caused by human errors. For this reason, a detailed analysis on human errors is an important task for increasing the safety of NPPs. Kim and Choi?2 analyzed 100 human-related unplanned reactor trip events in the Republic of Korea from 1986 to 2006 to consider the type of human errors based on the simple path model for human-induced unplanned reactor trips developed by Kim and Park. In this paper, we will investigate and perform a detailed analysis of the data to identify human-related unplanned reactor trip trends

2010-10-01

443

Reduced-aspect-ratio stellarator reactors  

Energy Technology Data Exchange (ETDEWEB)

The extent to which the size of a modular stellarator reactor may be reduced is investigated by means of an analytic model of the reactor. The various means employed include varying the blanket/shield thickness, the power output and the wall loading. An optimum design is found, the major radius of which tends to be insensitive to changes in these quantities, although a decrease in the power output leads to a rather smaller decrease in reactor dimensions, as would be expected. Varying the plasma beta at fixed (iota/2..pi..)/sup 2/epsilon or, alternatively, increasing the rotational transform per field period, may, however, allow configurations with fewer field periods to be accessed which have a substantially smaller major radius than the 'standard case' adopted. The magnetics of various configurations required by the model are checked by field line following and ...

1984-01-01

444

Neutron capture therapy beam on the LVR-15 reactor  

Energy Technology Data Exchange (ETDEWEB)

Several configurations of moderating and shielding materials have been designed and measured on the LVR-15 reactor for boron neutron capture therapy (BNCT) purposes. To determine the neutron and gamma ray space-energy distributions in the cylindrical geometry, the two-dimensional code DOT with the coupled neutron-gamma data library DLC-36 was used. The experimental verification of the beam parameters was performed in the LVR-15 reactor thermal column empty space with layers of graphite, aluminium, alumina, lead and bismuth. Attention was paid to establishing techniques and instrumentation for monitoring the neutron and gamma ray dose and beam quality. The thermal and epithermal flux densities were measured by activation foils, the neutron spectrum was determined with a Bonner spectrometer and gamma ray background with a scintillation spectrometer. The distribution of thermal neutrons in the human head phantom was mapped with a small ...

1992-01-01

445

Neutron capture therapy beam on the LVR-15 reactor  

International Nuclear Information System (INIS)

Several configurations of moderating and shielding materials have been designed and measured on the LVR-15 reactor for boron neutron capture therapy (BNCT) purposes. To determine the neutron and gamma ray space-energy distributions in the cylindrical geometry, the two-dimensional code DOT with the coupled neutron-gamma data library DLC-36 was used. The experimental verification of the beam parameters was performed in the LVR-15 reactor thermal column empty space with layers of graphite, aluminium, alumina, lead and bismuth. Attention was paid to establishing techniques and instrumentation for monitoring the neutron and gamma ray dose and beam quality. The thermal and epithermal flux densities were measured by activation foils, the neutron spectrum was determined with a Bonner spectrometer and gamma ray background with a scintillation spectrometer. The distribution of thermal neutrons in the human head phantom was mapped with a small ...

1991-10-01

446

Development of Improved Burnable Poisons for Commercial Nuclear Power Reactors  

Energy Technology Data Exchange (ETDEWEB)

Burnable poisons are used in nuclear reactors to produce a more level distribution of power in the reactor core and to reduce to necessity for a large control system. An ideal burnable poison would burn at the same rate as the fuel. In this study, separation of neutron-absorbing isotopes was investigated in order to eliminate isotopes that remain as absorbers at the end of fuel life, thus reducing useful fuel life. The isotopes Gd-157, Dy-164, and Er-167 were found to have desirable properties. These isotopes were separated from naturally occurring elements by means of plasma separation to evaluate feasibility and cost. It was found that pure Gd-157 could save approximately $6 million at the end of four years. However, the cost of separation, using the existing facility, made separation cost- ineffective. Using a magnet with three times the field strength is expected to reduce the cost by a factor of ten, making ...

2003-09-30

447

Railgun. Challenge to ultra-high speed; Railgun. Chokosoku eno chosen  

Energy Technology Data Exchange (ETDEWEB)

A railgun has an armature driven between two rail-like conductors. In other words, it is a linear drive device system that drives airframes by using the Lorentz`s force. The system is expected as a next-generation high-speed transport means, or as a means to create such ultimate fields as ultra-high pressures, ultra-high temperatures, and ultra-ferromagnetic fields. This paper is a report on investigations on the relevant technological trends as surveyed by the investigation committee at the Institute of Electrical Engineers of Japan using research reports published inside and outside the country. The reported themes cover explanations from the construction to the pulse power supply that forms the core of the technology, problems in switching, recent status of research and development, and to application fields. Compatibility in the high-level electrical and mechanical performances demanded in the railgun is not as easy as has been anticipated ...

1995-09-12

448

Software for production scheduling in hydro systems  

Energy Technology Data Exchange (ETDEWEB)

The report presents an integrated software system developed at the Norwegian Electric Power Research Institute (EFI), for production scheduling, maintenance handling, network security analysis, inflow forecasting, and load forecasting. The integrated software is being developed with focus on hydro-dominated power supply systems. In specific terms it is expected that application of the software will improve the operational decisions, and make the planning process more effective. The optimal scheduling of hydro resources poses severe computational problems in system operations planning. This necessitates problem decomposition. In the EFI approach, planning is split into three main levels: long-term, mid-term and short-term planning. The long-term planning aims at evaluating the seasonal and pluriannual handling of regional storages in view of firm power supply obligations, inflow ...

1991-02-01

449

Global Warming and California's Electricity Supply  

Science.gov (United States)

This fact sheet summarizes the potential impact of climate change as it relates to California's electricity supply. ...

450

Radiation factors specifying safety in reactor compartments handling in the process of decommissioning nuclear-powered submarines  

International Nuclear Information System (INIS)

The main problems arising in decommissioning nuclear-powered submarines (NPS) relate to choosing a concept of handling reactor compartments followed by handling technology development. Reactor compartments (RC) are characterized with extremely space-saving or integral layout of large-size power equipment and systems, restricted access for dismantling, high radiation dose rates in a number of bays of RC. The above RC features pose a problem to find optimum option of RC utilization which on the one hand would be the most cost efficient, and the safest as possible on the other, i.e. dose commitments of personnel involved should be minimum, and effect on population and environment should be negligible. The main radiation factors specifying safety in RC handling at any decommissioning stage are as follows: (1) total radioactivity integrated in reactor facility (RF); (2) distribution of ...

1996-03-10

451

Performance of SPNDs used in control and safety systems  

International Nuclear Information System (INIS)

Large sized reactor such as 540 MWe Pressurised Heavy Water Reactor (PHWR) requires continuous in core monitoring of local flux in order to provide effective control and protection. About 198 self powered neutron detectors (SPNDs) of the straight individually replaceable type are distributed in the reactor core. For purposes of reactor regulation, 42 prompt responding cobalt SPNDs called zone control detectors (ZCDs) are housed in vertical flux units (VFUs) and these are uniformly distributed in 14 power zones. The in core detectors used for spatial control by ZCCs do not accurately represent average zone power as they sense the flux over a small volume. Flux mapping system (FMS) comprising of 102 vanadium SPNDs in 26 VFUs, provide accurate measure of neutron flux, even though they have slow response to change in neutron flux levels. For ...

2006-11-13

452

Arid sites stakeholder participation in evaluating innovative technologies: VOC-Arid Site Integrated Demonstration  

Energy Technology Data Exchange (ETDEWEB)

Developing and deploying innovative environmental cleanup technologies is an important goal for the U.S. Department of Energy (DOE), which faces challenging remediation problems at contaminated sites throughout the United States. Achieving meaningful, constructive stakeholder involvement in cleanup programs, with the aim of ultimate acceptance of remediation decisions, is critical to meeting those challenges. DOE`s Office of Technology Development sponsors research and demonstration of new technologies, including, in the past, the Volatile Organic Compounds Arid Site Integrated Demonstration (VOC-Arid ID), hosted at the Hanford Site in Washington State. The purpose of the VOC-Arid ID has been to develop and demonstrate new technologies for remediating carbon tetrachloride and other VOC contamination in soils and ground water. In October 1994 the VOC-Arid ID became a part of the Contaminant Plume Containment and Remediation Focus Area (Plume Focus Area). The VOC ...

1995-05-01

453

Application of the porous media model for the LWR process components  

Energy Technology Data Exchange (ETDEWEB)

Full text of publication follows: A porous media solution PORFLO has been developed for the 3-dimensional two-phase flow by describing the process facility in Cartesian or cylindrical coordinates. The local porosity fraction is applied for distinguishing the fluid filled volumes from the solid structures. The solid structure contribute the two-phase flow through the wall friction, flow area and heat transfer. Optionally the solid structure may contain primary liquid of steam generators, steam in the higher temperature and pressure to be condensed or electrical heating power. By using these optional boundary conditions three different process facilities have been analysed. The thermohydraulic solution based on 5-equation approach, where the conservation equations are solved for the liquid and gas (vapour) mass, mixture momentum (giving the velocity only for the mixture), liquid and gas energy, is described shortly. In addition to that the ...

2005-07-01

454

WASHINGTON UNIVERSITY - NASA Technical Reports Server  

Science.gov (United States)

Although private schools are available, universal basic education is generally regarded as involving certain benefits which are, external to ...

455

Untitled - NASA Technical Report Server (NTRS)  

Science.gov (United States)

Joint Committee on Atomic Energy. Comgress of the United States. Washington, D. C.. 1 - Chief, Life Sciences Division. A m y Research Office ...

456

The Theater JFACC Construct: Creating Disunity of Command ...  

Science.gov (United States)

... WHS- Washington Headquarters Service ... paper will advocate assignment of a Commander, Air Force Forces for all Joint Task Forces conducting ...

2009-04-01

457

State Cancer Profiles Home Page  

Science.gov (United States)

Washington West Virginia Wisconsin Wyoming Cancer --- Choose a Cancer Site --- All Cancer Sites Bladder Brain & ONS Breast (Female) Breast (Female in situ) Cervix Childhood...

2011-10-15

458

Research Activities in the Spokane, Washington, Field Office...  

Science.gov (United States)

other chemical applications include use in water softeners, detergents, and food additives. The development of phosphate resources as a leasable commodity provides income to...

2011-08-20

459

Recurrence Intervals for Great Earthquakes of the Past 3,500 Years at Northeastern Willapa Bay, Washington  

Science.gov (United States)

Plate-boundary earthquakes have occurred repeatedly in the past several thousand years at the Cascadia subduction zone, where they are widely recorded ... ...

460

ROUNDUP - Johnson Space Center - NASA  

Science.gov (United States)

Sep 12, 1975 ... POCKET CALCULATORS. Jose P. Olivares 35, Robert B. Clowns and ... of pocket calculators and has an- Washington to arrive by Nov. 20. ...

461

REDUCTION OF INORGANIC COMPOUNDS WITH MOLECULAR HYDROGEN BY MICROCOCCUS LACTILYTICUS II.  

UK PubMed Central (United Kingdom)

Woolfolk, C. A. (University of Washington, Seattle). Reduction of inorganic compounds with molecular hydrogen by Micrococcus lactilyticus. II. Stoichiometry with inorganic...Full Text Available

1962-10-01

462

Multinational C2 Experiments Supported by C2 Systems and ...  

Science.gov (United States)

... WHS- Washington Headquarters Service ... but also with respect to other Joint, National and ... unit of action (UA) combat team or task force is organized ...

2003-06-01

463

Influence: Maximizing Effects to Create Long-Term Stability  

Science.gov (United States)

... WHS- Washington Headquarters Service. ... The dynamic Joint Special Operations Task Force -- Philippines (JSOTF-P) has evolved and ...

2010-05-03

464

Hypsography - ALEXANDRIA Quad  

Science.gov (United States)

HYPSOGRAPHY FOR THE FOLLOWING QUADS ALEXANDRIA, FALLS CHURCH, WASHINGTON WEST, MOUNT VERNON, ROCKVILLE, SENECA AND VIENNA. COVERAGE CONTAINS ATTRIBUTES DEFINING OWNERSHIP....

465

How Can Political Campaign Strategy be Adopted to Support ...  

Science.gov (United States)

... WHS- Washington Headquarters Service ... present a framework based on political campaigns theory for both the Joint Task Force Commander down ...

2010-10-27

466

HPLC Phytoplankton Pigment Measurements ... - Ocean Color - NASA  

Science.gov (United States)

CHORS, SDSU. OCRT Meeting (Washington, D.C., 14-16 Apr 2004). HPLC Phytoplankton Pigment Measurements: Continuation of Climate Quality Data Records ...

467

Foundational Principles for Organizing a Joint Force Staff  

Science.gov (United States)

... Chiefs of Staff, Joint Operation Planning and Execution System (JOPES) Volume I, Planning and Procedures, CJCSM 3122.01A (Washington, DC ...

2009-03-18

468

Download - NASA History Office  

Science.gov (United States)

Jan 14, 2004 ... presented to the nation at NASA Headquarters, Washington, D.C., ...... Board/Air Force Scientific Advisory Board Joint Task Force on ...

469

Deja vu: The Unified Command Plan of the Future Revisited  

Science.gov (United States)

... WHS- Washington Headquarters Service. ... The standing Joint Task Force concept should be used more to provide warfighter forces and ...

2011-05-19

470

Defense.gov News Article: Exercise Preps 82nd Airborne ...  

Science.gov (United States)

... Exercise Preps 82nd Airborne Division Staff for Afghanistan Deployment. By Donna Miles American Forces Press Service. WASHINGTON, Nov. ...

471

Automated Pharmacy Patient Medication Profiling System  

UK PubMed Central (United Kingdom)

The Systems Development Group and the Pharmacy Service of the Washington D.C. VAMC are involved in automating the administrative and clinical data requirements of a satellite out-patient pharmacy....Full Text Available

1981-11-04

472

2010 Secretary Clinton's Remarks  

Science.gov (United States)

DC -11/29/10 Remarks to the Press on Release of Purportedly Confidential Documents by Wikileaks; Secretary of State Hillary Rodham Clinton; Treaty Room; Washington, DC -11/29/10...

2011-09-18

473

Data Center Energy Benchmarking: Part 4 - Case Study on aComputer-testing Center (No. 21)  

Energy Technology Data Exchange (ETDEWEB)

The data center in this study had a total floor area of 8,580 square feet (ft{sup 2}) with one-foot raised-floors. It was a rack lab with 440 racks, and was located in a 208,240 ft{sup 2} multi-story office building in San Jose, California. Since the data center was used only for testing equipment, it was not configured as a critical facility in terms of electrical and cooling supply. It did not have a dedicated chiller system but served by the main building chiller plant and make-up air system. Additionally, it was served by a single electrical supply with no provision for backup power. The data center operated on a 24 hour per day, year-round cycle, and users had all hour full access to the data center facility. The study found that data center computer load accounted for 23% of the overall building electrical load, while the total power consumption attributable to the data center including allocated ...

2007-08-01

474

Operational reactor physics analysis codes (ORPAC)  

International Nuclear Information System (INIS)

Full text: Research reactors have been playing a multi dimensional role in areas of nuclear fuel cycle programme, radio-isotope productions, neutron beam research etc. To ensure an efficient, smooth and safe operation of a nuclear research reactor, many reactor physics evaluations are required on routine basis. As part of reactor core management the important activities are maintaining core reactivity status, core power distribution, xenon estimations, safety evaluation of in-pile irradiation samples and experimental assemblies and assessment of nuclear safety in fuel handling/storage. In-pile irradiation requires a prior estimation of the reactivity load due to the sample, heating rate and the activity developed in it during irradiation. For the safety of the personnel handling irradiated samples the dose rate at the surface of shielded flask housing the irradiated sample should be ...

475

The application of MOX fuel in light water nuclear power plant  

International Nuclear Information System (INIS)

MOX fuel has been one of the mature nuclear fuels which can be used in light water nuclear power plant now. The development status in this domain in foreign countries, the major influence of MOX fuel on reactor performance and the countermeasures are introduced in this paper. The application of MOX fuel in China's PWR is discussed in the end. (authors)

2008-12-01

476

Quality assurance program requirements (operation)  

International Nuclear Information System (INIS)

Apppendix B of 10 CFR Part 50 establishes quality assurance requirements for the operation of nuclear power plant safety-related structures, systems and components. This Guide describes an acceptable method for complying with these regulations with regard to overall quality assurance program requirements for the operation phase of nuclear power plants. Input to this Guide has been provided by the Advisory Committee on Reactor Safeguards.

477

Irradiation data for the MFA-1 and MFA-2 tests in the FFTF  

Energy Technology Data Exchange (ETDEWEB)

This report provides key information on the irradiation environment of the MONJU fuel tests MFA-1 and MFA-2 in the Fast Flux Test Facility (FFTF). This information includes the fission powers, neutron fluxes, sodium temperatures and sodium flow rates in MFA-I, MFA-2 and adjacent assemblies. It also includes MFA-1 and MFA-2 compositions as a function of exposure. The work was performed at the request of Power Reactor and Nuclear Fuels Corporation (PNC) of Japan.

1997-04-24

478

Hot Particles Research for Nuclear Power Plant in Wolsung  

Energy Technology Data Exchange (ETDEWEB)

The evaluation of the hazard posed to the skin by very small radioactive sources (diameter < 1mm) has become popularly known as the 'hot particle' problem in European and American nuclear reactor facilities. In this study, research to detect hot particle was performed in Wolsung Nuclear power plant (NPP) in Korea.

2007-10-15

479

Hot Particles Research for Nuclear Power Plant in Wolsung  

International Nuclear Information System (INIS)

The evaluation of the hazard posed to the skin by very small radioactive sources (diameter < 1mm) has become popularly known as the 'hot particle' problem in European and American nuclear reactor facilities. In this study, research to detect hot particle was performed in Wolsung Nuclear power plant (NPP) in Korea.

2007-10-01

480

Geodesy problems in nuclear power plant construction  

Energy Technology Data Exchange (ETDEWEB)

The special geodetic problems encountered during the construction of the Paks nuclear power plants are treated. The main building with its hermetically connected components including the reactor, the steam generators, the circulation pumps etc. impose special requirements on the control net of datum points. The geodesy tasks solved during the construction of the main building are presented in details.

1981-01-01

481

48 CFR 8.404 - Use of Federal Supply Schedules.  

Science.gov (United States)

...2010-10-01 2010-10-01 false Use of Federal Supply Schedules. 8.404 Section 8.404 Federal...REGULATION ACQUISITION PLANNING REQUIRED SOURCES OF SUPPLIES AND SERVICES Federal Supply Schedules 8.404 Use of Federal Supply...

2010-10-01

482

Solar thermal aircraft  

Energy Technology Data Exchange (ETDEWEB)

A solar thermal powered aircraft powered by heat energy from the sun. A heat engine, such as a Stirling engine, is carried by the aircraft body for producing power for a propulsion mechanism, such as a propeller. The heat engine has a thermal battery in thermal contact with it so that heat is supplied from the thermal battery. A solar concentrator, such as reflective parabolic trough, is movably connected to an optically transparent section of the aircraft body for receiving and concentrating solar energy from within the aircraft. Concentrated solar energy is collected by a heat collection and transport conduit, and heat transported to the thermal battery. A solar tracker includes a heliostat for determining optimal alignment with the sun, and a drive motor actuating the solar concentrator into optimal alignment with the sun based on a determination by the heliostat.

2007-09-18

483

Progress of negative-ion based NBI system for JT-60U  

Energy Technology Data Exchange (ETDEWEB)

The operation of the negative ion based NBI system for JT-60U has been progressed since 1996. Most of the efforts in the operation for increasing beam power and energy have been concentrated to get over the troubles, caused by surge energy at the moment of the accelerator break-down, in the ion sources and high voltage power supplies. The ion source for the N-NBI, so far, has accelerated negative ion beams of 14.3 A at 380 keV with deuterium and 18.5 A at 360 keV with hydrogen against the target of 22 A. The neutral beam power injected into JT-60U has already reached 5.2 MW at 350 keV for 0.7 sec with deuterium. (author)

1998-07-01

484

Private power in the country -- a chronology  

Energy Technology Data Exchange (ETDEWEB)

The chronology of installing solar power in a rural area of Ontario is described. The installation took all of seven years, and was characterized by a lot of joy, but also a lot of heartache and hardship, all of which are chronicled in this article. The project started with four solar modules generating 300 watts, nickel cadmium batteries of 225 Ah, an inverter of 600 watt, and a three-cylinder 6.5 Kw water-cooled propane generator. Today, nearly seven years later, the installation consists of 18 solar modules supplying 1350 watts of power, lead-acid batteries of 2770 Ah, a 2500 watt inverter, a one cylinder, 5.5 kw propane-gasoline generator, a heated, underground generator house, complete with an amp-hour meter and MPPT charge controller.

2003-06-30

485

High-power rf-pulsed modulators for the Los Alamos free-electron laser  

Energy Technology Data Exchange (ETDEWEB)

In the rf-driven free-electron laser (FEL) at the Los Alamos National Laboratory, there are two pulsed-power rf modulators as sources for two tandem, side-coupled 20-MeV linear accelerators. The rf power used to control the cavity fields is supplied by two 5.5-MW modulating anode klystrons operating at a center frequency of 1300.2 MHz. The modulation of the 125 kV klystron is achieved by using a triode switch tube that provides a pulse width up to 300 ..mu..s and a pulse repetition rate up to 10 Hz. This paper describes the present configuration of these two duplicate systems and presents plans for meeting the requirements of future rf FEL experiments at Los Alamos. 12 refs., 5 figs.

1987-09-01

486

Development of a through-the-earth monitor system. Open file report (final) Oct 77-Dec 80  

Energy Technology Data Exchange (ETDEWEB)

The object of this program was to design and build a self-contained system for remote monitoring of the atmosphere in mines. The system developed uses the mine pager phone line as the primary communication channel and also has the capability of using 208 Hz in the ELF band for wireless transmission through the earth. The depth for through-the-earth transmission is expected to be about 80 to 90 meters in high conductivity soil and is limited by the noise level in the ELF band-pass filters. The underground components of the TEM System are energized by mine power through a battery charger-storage battery power supply. In the event of mine power failure the battery capacity is more than sufficient for 1 week's operation with interrogations every 4 hours.

1980-12-01

487

Benefit analysis and evaluation of pumped-storage plant in Taipower system  

Energy Technology Data Exchange (ETDEWEB)

The operation of pumped-storage plants (PSP) is based on the daily load variations of power demand. It performs power generation at peak load times during the day, and pumps water up into the reservoir during the off-peak times at night. In the Taipower system in Taiwan, there are two pumped storage plants with ten units. These had a total installed capacity of 2,602 MW or a 12 percent capacity at the end of 1995. The plants were able to reduce system generation costs and improve reliability. A Pumped-Storage Plant Benefit Analysis (PSPBA) program was established using the principle of economic dispatch in 1985. This paper explains the rules of the program, the analysis results of the past 10 years, and a a cost benefit evaluation. It was found that the advantages of PSP are not only in supplying the power for peak load, but also in decreasing the total fuel cost. 5 figs., 4 refs.

1995-12-31

488

Analysis on fuel economy and advanced systems of hybrid vehicles; Hibrid jidosha no nenpi kojo yoin to shorai tenbo  

Energy Technology Data Exchange (ETDEWEB)

Hybrid vehicles have two power supplies as engine and electric motor which are used most efficiently corresponding to objects respectively to attain energy-saving and low pollution. In this paper, factors concerning the fuel economy of hybrid vehicles and potential thereof are examined, and the possibility of reducing fuel cost by half is described. As possible modes of highly efficient hybrid vehicles, series hybrid vehicles (SHEV) of conventional internal combustion engine, parallel hybrid vehicles using EV in combination, series-parallel hybrid vehicles (SPHV), series type fuel cell type vehicles, ceramic engine-turbo compound power generating SPHV as well as SHEV, and ceramics gas turbine engine power generating SHEV are mentioned. 10 refs., 14 figs.

1997-09-01

489

The Power Industry Reform and the lesson from California Situation  

Energy Technology Data Exchange (ETDEWEB)

What kind of lesson do we get from California situation? The first is that the sufficient investment to the operational regulation should be prepared as a system. It is necessary to introduce the systems related to capacity, such as the capacity market system that makes retail suppliers secure the fixed rate of their running peak-load as reserve capacity and other system that secure the 5-year supply capacity by a contract, in which suppliers can pay the penalty if they purchase more capacity than in the contract. The second is that the supplementary measures should be systematized for the supply system not to be in a panic in a case of the shortage situation of equipment. The exchange authority should control the regular inspection program on generators to reduce the market control of the supply companies. Through the supplementary system, the increase of electricity price must make the demand decrease. According to the ...

2001-03-01

490

Second aquifer storage under discussion. The power supply system of the German Bundestag building in Berlin; Zweiter Aquifer-Speicher im Gespraech. Zur Energieversorgung der Gebaeude des Deutschen Bundestages in Berlin  

Energy Technology Data Exchange (ETDEWEB)

The contribution outlines the current status of the building construction projects for the German Bundestag in Berlin. The following subjects are discussed: Energetic quality of the building, energy supply concept, integrated energy supply system, electric CHP systems, cogeneration (vegetable oil), aquifer storage (heat storage, cold storage), solar energy (photovoltaic energy conversion, thermal solar energy use), economic and ecological aspects. (HW) [Deutsch] Der vorliegende Beitrag gibt einen Ueberblick ueber den aktuellen Stand des Bauvorhabens des Deutschen Bundestages in Berlin. In diesem Zusammenhang wird auf folgende Themen eingegangen: Energetische Gebaeudequalitaet, Energieversorgungskonzept, Energieverbund, stromgefuehrte BHKWs, Kraft-Waerme-Kopplung (Pflanzenoel), Aquiferspeicher (Waermespeicher, Kaeltespeicher), Sonnenergienutzung (Photovoltaik, thermische Solarenergienutzung), Wirtschaftlichkeit und Oekologie. (HW)

1996-12-01

491

Hybrid solution and pump-storage optimization in water supply system efficiency: A case study  

International Nuclear Information System (INIS)

Environmental targets and saving energy have become ones of the world main concerns over the last years and it will increase and become more important in a near future. The world population growth rate is the major factor contributing for the increase in global pollution and energy and water consumption. In 2005, the world population was approximately 6.5 billion and this number is expected to reach 9 billion by 2050 [United Nations, 2008. (www.un.org), accessed on July]. Water supply systems use energy for pumping water, so new strategies must be developed and implemented in order to reduce this consumption. In addition, if there is excess of hydraulic energy in a water system, some type of water power generation can be implemented. This paper presents an optimization model that determines the best hourly operation for 1 day, according to the electricity tariff, for a pumped storage system with water consumption and inlet discharge. Wind ...

2008-11-01

492

The role of natural circulation in the FFTF [Fast Flux Test Facility] passive safety tests  

International Nuclear Information System (INIS)

A series of tests were completed at the Fast Flux Test Facility to demonstrate the passive safety characteristics of liquid metal reactors with natural circulation flow. The first test consisted of transition from forced to natural circulation flow at an initial decay power of 0.3%. The second test represented an unprotected loss-of-flow transient to natural circulation from 50% power with the control rods prevented from scramming into the core. The third test was a steady-state, natural circulation condition with core fission powers up ato about 2.3%. Core sodium data and results of single and multi-channel computer models confirmed the reliability and effectiveness of natural circulation flow for liquid metal reactor safety.

1987-12-13

493

Characterization of Filter Elements for Service in a Coal Gasification Environment  

Energy Technology Data Exchange (ETDEWEB)

The Power Systems Development Facility (PSDF) is a joint Department of Energy/Industry sponsored engineering-scale facility for testing advanced coal-based power generation technologies. High temperature, high pressure gas cleaning is critical to many of these advanced technologies. Barrier filter elements that can operate continuously for nearly 9000 hours are required for a successful gas cleaning system for use in commercial power generation. Since late 1999, the Kellogg Brown & Root Transport reactor at the PSDF has been operated in gasification mode. This paper describes the test results for filter elements operating in the Siemens-Westinghouse particle collection device (PCD) with the Transport reactor in gasification mode. Operating conditions in the PCD have varied during gasification operation as described elsewhere in these proceedings (Martin et al, 2002).

2002-09-19

494

Hydraulic system for driving control rods  

International Nuclear Information System (INIS)

Purpose: To enable safety reactor shut down upon occurrence of an abnormal excess pressure in a hydraulic control unit. Constitution: The actuation pressure for a pressure switch that generates a scram signal is set lower than the release pressure set to a pressure release valve. Thus, if the pressure of nitrogen gas in a nitrogen container increases such as upon exposure of the hydraulic control unit to a high temperature, the pressure switch is actuated at first to generate the scram signal and a scram valve is opened to supply water at high pressure to control rod drives under the driving force of the nitrogen gas at high pressure to rapidly insert the control element into the reactor and shut down it. If the pressure of the nitrogen gas still increases after the scram, the pressure release valve is opened to release the nitrogen gas at high temperature to the atmosphere. Since the scram is attained before the actuation ...

1980-11-07

495

The technique and preliminary results of LEU U-Mo full-size IRT type fuel testing in the MIR reactor  

Science.gov (United States)

In March 2007 in-pile testing of LEU U-Mo full-size IRT type fuel elements was started in the MIR reactor. Four prototype fuel elements for Uzbekistan WWR SM reactor are being tested simultaneously - two of tube type design and two of pin type design. The dismountable irradiation devices were constructed for intermediate reloading and inspection of fuel elements during reactor testing. The objective of the test is to obtain the experimental results for determination of more reliable design and licensing fuel elements for conversion of the WWR SM reactor. The heat power of fuel elements is measured on-line by thermal balance method. The distribution of fission density and burn-up of uranium in the volume of elements are calculated by using the MIR reactor MCU code (Monte-Carlo) model. In this paper the design of fuel elements, the technique, main parameters and ...

2008-07-15

496

Progress of the DUPIC Fuel Compatibility Analysis (IV) - Fuel Performance  

International Nuclear Information System (INIS)

This study describes the mechanical compatibility of the direct use of spent pressurized water reactor (PWR) fuel in Canada deuterium uranium (CANDU) reactors (DUPIC) fuel, when it is loaded into a CANDU reactor. The mechanical compatibility can be assessed for the fuel management, primary heat transport system, fuel channel, and the fuel handling system in the reactor core by both the experimental and analytic methods. Because the physical dimensions of the DUPIC fuel bundle adopt the CANDU flexible (CANFLEX) fuel bundle design which has already been demonstrated for a commercial use in CANDU reactors, the experimental compatibility analyses focused on the generation of material property data and the irradiation tests of the DUPIC fuel, which are used for the computational analysis. The intermediate results of the mechanical compatibility analysis have shown that the integrity of ...

1995-06-04

497

Fast Flux Test Facility reactor initial criticality predictions and measurements  

International Nuclear Information System (INIS)

The Fast Flux Test Facility (FFTF) was designed to test fast-reactor fuels and other nonfuel materials. In its 37 reactor cycles of operations, the FFTF reactor has performed very well and successfully completed all the irradiation testings with an operating efficiency factor as high as 98%. Since FFTF is an experimental reactor, its core loading changed from cycle to cycle. Depending on the number of test assemblies in the core and their location, the core loading can change significantly from an essentially homogeneous core loading to a relatively nonhomogeneous or even highly localized heterogeneous loading. Consequently, the core reload design and initial criticality analyses were required for each operating cycle. The zero power initial critical control rod bank height was predicted before each reactor startup. The initial critical prediction depends on the ...

1992-06-07

498

Conceptual Framework of Economic Evaluation on SMRs  

International Nuclear Information System (INIS)

Korea Atomic Energy Research Institute(KAERI) launched a project to develop an integral reactor in 1996. The reactor called as System Integrated Modular Advanced Reactor(SMART) which is a kind of small modular reactors (SMRs). Since the early 1990s, there has been renewed interest in the development and application of small and medium sized integral reactors. 2009 assessment by the IAEA under its Innovative Nuclear Power Reactor and Fuel Cycle (INPRO) program concluded that there could be 96 SMRs in operation around the world by 2030 in its 'high' case, and 43 units in the 'low' case, none of them in the USA. The reason of the increased demand mostly comes from the fact that SMRs are thought to be more suitable for developing countries with small electrical grid capacity, insufficient infrastructure and limited investment capability than ...

2010-10-01