WorldWideScience

Sample records for catawba nuclear station

  1. 77 FR 2766 - Facility Operating License Amendment from Duke Energy Carolinas, LLC., Catawba Nuclear Station...

    Science.gov (United States)

    2012-01-19

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Facility Operating License Amendment from Duke Energy Carolinas, LLC., Catawba Nuclear Station... and NPF-52 issued to Duke Energy Carolinas, LLC (the licensee), for operation of the Catawba...

  2. 76 FR 40754 - Duke Energy Carolinas, LLC Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station, Units...

    Science.gov (United States)

    2011-07-11

    ..., 50-270, And 50-287] Duke Energy Carolinas, LLC Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station, Units 1 and 2; Oconee Nuclear Station, Units 1, 2, and 3; Notice of Withdrawal of... From the Federal Register Online via the Government Publishing Office NUCLEAR...

  3. 76 FR 24538 - Duke Energy Carolinas, LLC; Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station...

    Science.gov (United States)

    2011-05-02

    ..., 50-270, and 50-287] Duke Energy Carolinas, LLC; Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station, Units 1 and 2; Oconee Nuclear Station, Units 1, 2, and 3; Notice of Withdrawal of... From the Federal Register Online via the Government Publishing Office NUCLEAR...

  4. 75 FR 43571 - Duke Energy Carolinas, LLC; Catawba Nuclear Station, Units 1 and 2; Environmental Assessment And...

    Science.gov (United States)

    2010-07-26

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Duke Energy Carolinas, LLC; Catawba Nuclear Station, Units 1 and 2; Environmental Assessment And..., issued to Duke Energy Carolinas, LLC (the licensee), for operation of the Catawba Nuclear Station,...

  5. 76 FR 39913 - Duke Energy Carolinas, LLC; Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station...

    Science.gov (United States)

    2011-07-07

    ... social security numbers, home addresses, or home phone numbers in their filings, unless an NRC regulation... the facility's digital computer and communications systems and networks are protected from...

  6. Isotopic Details of the Spent Catawba-1 MOX Fuel Rods at ORNL

    Energy Technology Data Exchange (ETDEWEB)

    Ellis, Ronald James [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-04-01

    The United States Department of Energy funded Shaw/AREVA MOX Services LLC to fabricate four MOX Lead Test Assemblies (LTA) from weapons-grade plutonium. A total of four MOX LTAs (including MX03) were irradiated in the Catawba Nuclear Station (Unit 1) Catawba-1 PWR which operated at a total thermal power of 3411 MWt and had a core with 193 total fuel assemblies. The MOX LTAs were irradiated along with Duke Energy s irradiation of eight Westinghouse Next Generation Fuel (NGF) LEU LTAs (ref.1) and the remaining 181 LEU fuel assemblies. The MX03 LTA was irradiated in the Catawba-1 PWR core (refs.2,3) during cycles C-16 and C-17. C-16 began on June 5, 2005, and ended on November 11, 2006, after 499 effective full power days (EFPDs). C-17 started on December 29, 2006, (after a shutdown of 48 days) and continued for 485 EFPDs. The MX03 and three other MOX LTAs (and other fuel assemblies) were discharged at the end of C-17 on May 3, 2008. The design of the MOX LTAs was based on the (Framatome ANP, Inc.) Mark-BW/MOX1 17 17 fuel assembly design (refs. 4,5,6) for use in Westinghouse PWRs, but with MOX fuel rods with three Pu loading ranges: the nominal Pu loadings are 4.94 wt%, 3.30 wt%, and 2.40 wt%, respectively, for high, medium, and low Pu content. The Mark-BW/MOX1 (MOX LTA) fuel assembly design is the same as the Advanced Mark-BW fuel assembly design but with the LEU fuel rods replaced by MOX fuel rods (ref. 5). The fabrication of the fuel pellets and fuel rods for the MOX LTAs was performed at the Cadarache facility in France, with the fabrication of the LTAs performed at the MELOX facility, also in France.

  7. 76 FR 4724 - Catawba Sox, LLC Formerly Known as Catawba Sox, Inc. Including Workers Whose Unemployment...

    Science.gov (United States)

    2011-01-26

    ... of Catawba Sox, LLC, formerly known as Catawba Sox, Inc., Newton, North Carolina. The notice was published in the Federal Register on August 2, 2010 (75 FR 45162). At the request of the State agency, the... Whose Unemployment Insurance UI) Wages Are Paid Through Ellis Hosiery Mill, LLC, Newton, NC;...

  8. Nuclear applications in manned space station

    Science.gov (United States)

    Brooksbank, W. A., Jr.; Sieren, G. J.

    1972-01-01

    The zirconium hydride reactor, coupled to a thermo-electric or Brayton conversion system, and the Pu 238 isotope/Brayton system, are considered to be the viable nuclear candidates for the modular space station electrical power system. The basic integration aspects of these nuclear electrical power systems are reviewed, including unique requirements imposed by the buildup and incremental utilization considerations of the modular station. Also treated are the various programmatic aspects of nuclear power system design and selection.

  9. Commentary: childhood cancer near nuclear power stations

    Directory of Open Access Journals (Sweden)

    Fairlie Ian

    2009-09-01

    Full Text Available Abstract In 2008, the KiKK study in Germany reported a 1.6-fold increase in solid cancers and a 2.2-fold increase in leukemias among children living within 5 km of all German nuclear power stations. The study has triggered debates as to the cause(s of these increased cancers. This article reports on the findings of the KiKK study; discusses past and more recent epidemiological studies of leukemias near nuclear installations around the world, and outlines a possible biological mechanism to explain the increased cancers. This suggests that the observed high rates of infant leukemias may be a teratogenic effect from incorporated radionuclides. Doses from environmental emissions from nuclear reactors to embryos and fetuses in pregnant women near nuclear power stations may be larger than suspected. Hematopoietic tissues appear to be considerably more radiosensitive in embryos/fetuses than in newborn babies. Recommendations for advice to local residents and for further research are made.

  10. Nuclear power generation modern power station practice

    CERN Document Server

    1971-01-01

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

  11. 75 FR 16523 - FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power Station; Exemption

    Science.gov (United States)

    2010-04-01

    ... COMMISSION FirstEnergy Nuclear Operating Company; Davis-Besse Nuclear Power Station; Exemption 1.0 Background FirstEnergy Nuclear Operating Company (FENOC, the licensee) is the holder of Facility Operating License... M.S. Fertel, Nuclear Energy Institute). The licensee's request for an exemption is...

  12. A Series Dissertation on Tianwan Nuclear Power Station--Summary of Tianwan Nuclear Power Station Project

    Institute of Scientific and Technical Information of China (English)

    Li Qiankun

    2006-01-01

    This is a summary in relation to the construction and operation of Tianwan Nuclear Power Station (the Project) at Lianyungang, Jiangsu Province, the People' s Republic of China. The breakdown specialty topic shall been given in times to come. In this report, the author attempted to give some general description of the Project, including the Project site' s general layout and geographical conditions. A description of its exposure to the elements is also provided, supported by some data made available to us. The key component parts of the Project are described, namely, the nuclear island which includes the reactor, steam generator and so on; the conventional island and the balance of plant. Wherever possible, the improvements to the reactor design over the operating V320 are highlighted, which result in the V428 reactor model. The supplier and contractor for the major equipment such as the reactor and the turbine is the Russian company, namely Atomstroyexport (ASE). There are third country suppliers who provide other equipment. For instance, Siemens supplies the full digital I&C system and Framatome ANP supplies the emergency diesel generators; the metal-clad switchgear cabinet by ABB of Australia; the main steam isolation valve unit by CCI AG of Switzerland. All these foreign suppliers are well known globally. Their experience and quality of the equipment supplied by them are well recognized by the people in the respective fields. As for the civil work and erection work, the most experienced and trustworthy local contractors have been selected. These contractors have proven their competence in similar contract work before. For the testing of the equipment, stringent and proper procedures which meet international standards are adopted. Finally, the author wished on this report could provide the world a safety and advanced Nuclear Project building in China.

  13. 77 FR 135 - Exelon Generation Company, LLC, Oyster Creek Nuclear Generating Station; Exemption

    Science.gov (United States)

    2012-01-03

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Exelon Generation Company, LLC, Oyster Creek Nuclear Generating Station; Exemption 1.0 Background...-16, which authorizes operation of the Oyster Creek Nuclear Generating Station (OCNGS). The...

  14. Pipe rupture incident of Hamaoka Nuclear Power Station Unit-1

    Energy Technology Data Exchange (ETDEWEB)

    Ono, Yushi; Nakagami, Motonori; Hayashi, Haruhisa; Ichikawa, Yoshihiro [Chubu Electric Power Co. Inc., Nagoya (Japan)

    2002-11-01

    At the Hamaoka Nuclear Power Station Unit-1 (540 MWe of electric output; BWR-4 type) of the Chubu Electric Power Co., Ltd., an incident of pipe rupture of residual heat removal system on steam condenser system occurred on November, 2001. This incident gave no effects on outer parts of the station, because safety system apparatuses in the station worked adequately from a standpoint of accidental phenomenon. On the other hand, on its forming processes, as it is no similar case at the nuclear power stations in and out of Japan, to securely carry out countermeasures for preventing a recurrence of the incidence, its cause was striven to elucidate thoroughly. This paper was introduced about contents and results on site surveys, and surveys such as tests, analysis, and so on performed for about a half year after the incident, for preventing a recurrence of similar incidents. (G.K.)

  15. 75 FR 8153 - Nebraska Public Power District; Cooper Nuclear Station Environmental Assessment and Finding of No...

    Science.gov (United States)

    2010-02-23

    ... COMMISSION Nebraska Public Power District; Cooper Nuclear Station Environmental Assessment and Finding of No... District (NPPD, the licensee), for operation of the Cooper Nuclear Station (CNS), located in Nemaha County... Statement for the Cooper Nuclear Station dated February 1973. Agencies and Persons Consulted In...

  16. 75 FR 52997 - Nebraska Public Power District; Cooper Nuclear Station; Exemption

    Science.gov (United States)

    2010-08-30

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Nebraska Public Power District; Cooper Nuclear Station; Exemption 1.0 Background Nebraska Public... authorizes operation of the Cooper Nuclear Station (CNS). The license provides, among other things, that...

  17. 75 FR 47856 - Nebraska Public Power District: Cooper Nuclear Station; Notice of Availability of the Final...

    Science.gov (United States)

    2010-08-09

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Nebraska Public Power District: Cooper Nuclear Station; Notice of Availability of the Final... operation for the Cooper Nuclear Station (CNS). CNS is located near Brownville, Nebraska, on the...

  18. 75 FR 10517 - Nebraska Public Power District, Cooper Nuclear Station; Exemption

    Science.gov (United States)

    2010-03-08

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Nebraska Public Power District, Cooper Nuclear Station; Exemption 1.0 Background Nebraska Public... authorizes operation of the Cooper Nuclear Station (CNS). The license provides, among other things, that...

  19. 75 FR 76055 - Nebraska Public Power District Cooper Nuclear Station; Notice of Issuance of Renewed Facility...

    Science.gov (United States)

    2010-12-07

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Docket No. 50-298; NRC-2008-0617] Nebraska Public Power District Cooper Nuclear Station; Notice of... operator of the Cooper Nuclear Station (CNS). Renewed facility operating license No. DPR-46...

  20. 78 FR 40519 - Cooper Nuclear Station; Application and Amendment to Facility Operating License Involving...

    Science.gov (United States)

    2013-07-05

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Cooper Nuclear Station; Application and Amendment to Facility Operating License Involving Proposed... No. DPR-46, issued to Nebraska Public Power District (the licensee), for operation of the...

  1. Operating Experience at the Aagesta Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Sandstroem, S. (ed.)

    1966-09-15

    Sweden's first nuclear power reactor Agesta, achieved criticality on July 17, 1963. Full power (65 MW{sub t}) was attained on March 20, 1964. Aagesta is a heavy water cooled and moderated pressure vessel reactor used for production of electricity as well as for district heating. The design, assembly and construction etc, of the reactor was described in detail in a staff report by AB Atomenergi, 'The Aagesta Nuclear Power Station' edited by B McHugh, which was published in September, 1964. In the book experiences from the commissioning and the first operation of the reactor were reported as well as findings from the extensive reactor physics studies made during this period. The report now presented is written by members of the operating team at Aagesta since its start. It reflects in general the experiences up to the end of 1965. The Aagesta Log, however, covers the period up to the normal summer stop 1966. The reactor has hitherto produced 506,000 MWh power of which 48,700 MWh have been electric power. In July 1965 the responsibility for the reactor operation was taken over by the Swedish State Power Board from AB Atomenergi, which company had started the reactor and operated it until the summer break 1965.

  2. Aquatic impacts from operation of three midwestern nuclear power stations: Fort Calhoun station, Unit No. 1 environmental appraisal report

    Energy Technology Data Exchange (ETDEWEB)

    El-Shamy, F.

    1981-10-01

    Fort Calhoun Station, Unit 1, is located on the west bank of the Missouri River in Washington County, Nebraska. The station, a nuclear powered generating facility producing 475 net megawatts, utilizes a once-through cooling design. The station influences the aquatic biota of the Missouri River vicinity in several ways. The heated discharges of the station were found to have no significant impacts to fish, periphyton, and benthic macroinvertebrates. Minor effects to phytoplankton were noted in warm summer months at the point of discharge. An estimated 227,900,000 fish larvae were entrained annually from the river's ichthyoplankton community, the majority identified as freshwater drum. Fort Calhoun Station impinged an estimated 170,882 fish annually, large numbers of which were freshwater drum and gizzard shad with potential losses to channel and flathead catfish. The station was shown to have little impact on the zooplankton community.

  3. 76 FR 79227 - Exemption Request Submitted by Oyster Creek Nuclear Generating Station; Exelon Generation Company...

    Science.gov (United States)

    2011-12-21

    ... COMMISSION Exemption Request Submitted by Oyster Creek Nuclear Generating Station; Exelon Generation Company... Generation Company, LLC (the licensee), for operation of the Oyster Creek Nuclear Generating Station (Oyster... for Oyster Creek and NUREG-1437, Vol. 1, Supplement 28, ``Generic Environmental Impact Statement...

  4. 75 FR 33656 - Exelon Generation Company, LLC Oyster Creek Nuclear Generating Station Environmental Assessment...

    Science.gov (United States)

    2010-06-14

    ... COMMISSION Exelon Generation Company, LLC Oyster Creek Nuclear Generating Station Environmental Assessment....2, as requested by Exelon Generation Company, LLC (the licensee), for operation of the Oyster Creek Nuclear Generating Station (Oyster Creek), located in Ocean County, New Jersey. Therefore, as required...

  5. 75 FR 33366 - Exelon Generation Company, LLC; Oyster Creek Nuclear Generating Station; Notice of Withdrawal of...

    Science.gov (United States)

    2010-06-11

    ... COMMISSION Exelon Generation Company, LLC; Oyster Creek Nuclear Generating Station; Notice of Withdrawal of..., application for amendment to Facility Operating License No. DPR-16 for the Oyster Creek Nuclear Generating Station (Oyster Creek), located in Ocean County, New Jersey. The proposed amendment would have revised...

  6. Construction of a nuclear power station in one's locality: attitudes and salience

    NARCIS (Netherlands)

    van der Pligt, J.; Eiser, J.R.; Spears, R.

    1986-01-01

    Examined the attitudes toward the building of a nuclear power station in one's locality by surveying 290 residents (mean age 47.5 yrs) of 3 small rural communities that were listed as possible locations for a new nuclear power station. Results show that a large majority of Ss opposed the building of

  7. 75 FR 33741 - Safety Zone; Tracey/Thompson Wedding, Lake Erie, Catawba Island, OH

    Science.gov (United States)

    2010-06-15

    ... SECURITY Coast Guard 33 CFR Part 165 RIN 1625-AA00 Safety Zone; Tracey/Thompson Wedding, Lake Erie, Catawba... zone is intended to restrict vessels from portions of Lake Erie during the Tracey/Thompson Wedding... and vessels during the setup, loading, and launching of the Tracey/Thompson Wedding Fireworks...

  8. 75 FR 33358 - Duke Energy Carolinas, LLC; McGuire Nuclear Station; Confirmatory Order (Effective Immediately)

    Science.gov (United States)

    2010-06-11

    ... Carolinas, LLC; McGuire Nuclear Station; Confirmatory Order (Effective Immediately) I Duke Energy Carolinas, LLC's (Duke Energy or Licensee) is the holder of License Nos. NPF-9 and NPF-17, issued by the Nuclear... Energy Nuclear Policy Manual, NSD 218.10.1, Revision 9, states in relevant part, that where...

  9. Local opposition to the construction of a nuclear power station: differential salience of impacts

    NARCIS (Netherlands)

    Eiser, J.R.; van der Pligt, J.; Spears, R.

    1988-01-01

    Surveyed attitudes among 290 residents of 3 villages in southwest England toward proposals to build a nuclear power station nearby. Ss were grouped according to being neutral or in favor of a new power station either locally or elsewhere (Group PN), against one locally but neutral or pro elsewhere (

  10. 76 FR 79228 - Combined Licenses at William States Lee III Nuclear Station Site, Units 1 and 2; Duke Energy...

    Science.gov (United States)

    2011-12-21

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Combined Licenses at William States Lee III Nuclear Station Site, Units 1 and 2; Duke Energy Carolinas, LLC AGENCY: Nuclear Regulatory Commission. ACTION: Draft environmental impact statement;...

  11. 78 FR 77508 - Duke Energy Carolinas, LLC; William States Lee III Nuclear Station, Units 1 and 2; Combined...

    Science.gov (United States)

    2013-12-23

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Duke Energy Carolinas, LLC; William States Lee III Nuclear Station, Units 1 and 2; Combined Licenses Application Review AGENCY: Nuclear Regulatory Commission. ACTION: Final environmental...

  12. 78 FR 11904 - Zion Nuclear Power Station, Units 1 and 2; ZionSolutions, LLC; Consideration of Indirect Transfer

    Science.gov (United States)

    2013-02-20

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Zion Nuclear Power Station, Units 1 and 2; ZionSolutions, LLC; Consideration of Indirect Transfer AGENCY: Nuclear Regulatory Commission. ACTION: Request for license transfer; opportunity to...

  13. Operating Nuclear Power Stations in a Regulated Cyber Security Environment

    Energy Technology Data Exchange (ETDEWEB)

    Dorman, E.

    2014-07-01

    The United States Nuclear Regulatory Commission (NRC) issued 10CFR73.54 to implement a regulated Cyber Security Program at each operating nuclear reactor facility. Milestones were implemented December 31, 2012 to mitigate the attack vectors for the most critical digital assets acknowledged by the industry and the NR C. The NRC inspections have begun. The nuclear Cyber Security Plan, implemented by the site Cyber Security Program (Program), is an element of the operating license at each facility. (Author)

  14. 78 FR 28005 - System Energy Resources, Inc.; Grand Gulf Nuclear Station; Order Approving Direct and Indirect...

    Science.gov (United States)

    2013-05-13

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION System Energy Resources, Inc.; Grand Gulf Nuclear Station; Order Approving Direct and Indirect Transfers of Early Site Permit and Approving Conforming Amendment I System Energy Resources, Inc. (SERI),...

  15. 77 FR 52765 - Dominion Nuclear Connecticut, Inc. Millstone Power Station, Unit 3; Exemption

    Science.gov (United States)

    2012-08-30

    ... Millstone Power Station Unit 1, a permanently defueled boiling water reactor nuclear unit, and Millstone...-water nuclear power reactors,'' requires that each power reactor meet the acceptance criteria for ECCS... Reactions at High Temperatures, III. Experimental and Theoretical Studies of the Zirconium-Water...

  16. Efforts toward enhancing seismic safety at Kashiwazaki Kariwa nuclear power station

    Energy Technology Data Exchange (ETDEWEB)

    Yamashita, Kazuhiko

    2010-09-15

    Kashiwazaki-Kariwa Nuclear Power Station, 8212MW, was struck by M6.8 quakes in July 2007. TEPCO has steadily been conducting restoration and post-earthquake equipment integrity assessment, aiming to make it a disaster-resistant power station. 2 units among 7 resumed commercial operation by June 2010. This earthquake has provided a great deal of knowledge and information useful for nuclear safety improvement. It has also served as a valuable reference for the IAEA in developing earthquake-related guidelines. TEPCO would like to share the knowledge and information thereby contributing to improving the safety of nuclear power generation. We will introduce some of our activities.

  17. 78 FR 41425 - In the Matter of Duke Energy Carolinas, LLC; (Oconee Nuclear Station, Units 1, 2, and 3...

    Science.gov (United States)

    2013-07-10

    ...; EA-13-010] In the Matter of Duke Energy Carolinas, LLC; (Oconee Nuclear Station, Units 1, 2, and 3... Energy Carolinas, LLC, Oconee Nuclear Station, 7800 Rochester Highway, Seneca, SC 29672. Filing is... From the Federal Register Online via the Government Publishing Office NUCLEAR...

  18. Natural Disasters and Safety Risks at Nuclear Power Stations

    Science.gov (United States)

    Tutnova, T.

    2012-04-01

    In the aftermath of Fukushima natural-technological disaster the global opinion on nuclear energy divided even deeper. While Germany, Italy and the USA are currently reevaluating their previous plans on nuclear growth, many states are committed to expand nuclear energy output. In China and France, where the industry is widely supported by policymakers, there is little talk about abandoning further development of nuclear energy. Moreover, China displays the most remarkable pace of nuclear development in the world: it is responsible for 40% of worldwide reactors under construction, and aims at least to quadruple its nuclear capacity by 2020. In these states the consequences of Fukushima natural-technological accident will probably result in safety checks and advancement of new reactor technologies. Thus, China is buying newer reactor design from the USA which relies on "passive safety systems". It means that emergency power generators, crucial for reactor cooling in case of an accident, won't depend on electricity, so that tsunami won't disable them like it happened in the case of Fukushima. Nuclear energy managed to draw lessons from previous nuclear accidents where technological and human factors played crucial role. But the Fukushima lesson shows that the natural hazards, nevertheless, were undervalued. Though the ongoing technological advancements make it possible to increase the safety of nuclear power plants with consideration of natural risks, it is not just a question of technology improvement. A necessary action that must be taken is the reevaluation of the character and sources of the potential hazards which natural disasters can bring to nuclear industry. One of the examples is a devastating impact of more than one natural disaster happening at the same time. This subject, in fact, was not taken into account before, while it must be a significant point in planning sites for new nuclear power plants. Another important lesson unveiled is that world nuclear

  19. Developing the concept of maintenance and repairs in projects of power units for new-generation nuclear power stations

    Science.gov (United States)

    Gurinovich, V. D.; Yanchenko, Yu. A.

    2012-05-01

    Results from conceptual elaboration of individual requirements for the system of maintenance and repairs that must be implemented in the projects of new-generation nuclear power stations are presented taking as an example the power unit project for a nuclear power station equipped with a standard optimized VVER reactor with enhanced information support (the so-called VVER TOI reactor). Implementation of these concepts will help to achieve competitiveness of such nuclear power stations in the domestic and international markets.

  20. 76 FR 73721 - Nine Mile Point Nuclear Station, LLC, Nine Mile Point Nuclear Station, Unit No. 2, Environmental...

    Science.gov (United States)

    2011-11-29

    ... Shine, and Solid Waste Nuclear power plants use waste treatment systems to collect, process, recycle..., spent ion exchange resin, and dry active waste (DAW). DAW includes paper, plastic, wood, rubber,...

  1. Decontamination of control rod housing from Palisades Nuclear Power Station.

    Energy Technology Data Exchange (ETDEWEB)

    Kaminski, M.D.; Nunez, L.; Purohit, A.

    1999-05-03

    Argonne National Laboratory has developed a novel decontamination solvent for removing oxide scales formed on ferrous metals typical of nuclear reactor piping. The decontamination process is based on the properties of the diphosphonic acids (specifically 1-hydroxyethane-1,1-diphosphonic acid or HEDPA) coupled with strong reducing-agents (e.g., sodium formaldehyde sulfoxylate, SFS, and hydroxylamine nitrate, HAN). To study this solvent further, ANL has solicited actual stainless steel piping material that has been recently removed from an operating nuclear reactor. On March 3, 1999 ANL received segments of control rod housing from Consumers Energy's Palisades Nuclear Plant (Covert, MI) containing radioactive contamination from both neutron activation and surface scale deposits. Palisades Power plant is a PWR type nuclear generating plant. A total of eight segments were received. These segments were from control rod housing that was in service for about 6.5 years. Of the eight pieces that were received two were chosen for our experimentation--small pieces labeled Piece A and Piece B. The wetted surfaces (with the reactor's pressurized water coolant/moderator) of the pieces were covered with as a scale that is best characterized visually as a smooth, shiny, adherent, and black/brown in color type oxide covering. This tenacious oxide could not be scratched or removed except by aggressive mechanical means (e.g., filing, cutting).

  2. Retrieval of Intermediate Level Waste at Trawsfyndd Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Wall, S.; Shaw, I.

    2002-02-25

    In 1996 RWE NUKEM Limited were awarded two contracts by BNFL Magnox Generation as part of the decommissioning programme for the Trawsfynydd power station. From the normal operations of the two Magnox reactors, intermediate level waste (ILW) had accumulated on site, this was Miscellaneous Activated Components (MAC) and Fuel Element Debris (FED). The objective of these projects is retrieval of the waste from storage vaults, monitoring, packaging and immobilization in a form suitable for on site storage in the medium term and eventual disposal to a waste repository. The projects involve the design, supply, commissioning and operation of equipment to retrieve, pack and immobilize the waste, this includes recovery from vaults in both reactor and pond locations and final decommissioning and removal of plant from site after completion of waste recovery.

  3. Avian radioecology on a nuclear power station site. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Levy, C.K.; Maletskos, C.J.; Youngstrom, K.A.

    1975-01-01

    A summary of a six-year avian radioecology study at the site of a nuclear power plant in Massachusetts is reported. A completed historical summary is followed by a description of mathematical models developed to calculate the effects on bird body burdens of various changes in environmental radionuclide levels. Examples are presented. Radionuclide metabolism studies in which acute doses of /sup 131/I and /sup 137/Cs were administered to four species of wild birds are presented. Radionuclides were administered both intravenously and orally; no apparent differences in uptake or elimination rates were observed between the two methods.

  4. In situ monitoring of animal micronuclei before the operation of Daya Bay Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Y.N. Cai; H.Y. He; L.M. Qian; G.C. Sun; J.Y. Zhao [Guangzhou College of Education, Guangzhou (China)

    1994-12-31

    Daya Bay Nuclear Power Station, a newly-built nuclear power station in southern mainland China, started its operation in 1993. We examined micro-nucleated cells of Invertibrate (Bivalves) and Vertibrate (Fish and Amphibia) in different spots within the 50km surroundings of the Power Station during 1986-1993. This paper reports the results of the investigation carried out in Dong Shan, a place 4.7km to the Power Station:Bivalves; Pteria martensil 5.1(1986),4.8(1988),4.8(1991),5,0(1993),Mytilus smardinus 4.7(1987),4.6(1988); Chamys nobilis 4.9(1987);4.9(1991),4.5(1992),4.5(1993). Fish; Therapon jarbua 0.48(1991),0.67(1992),0.47(1993). Amphibia; Bufo melanostictus 0.29 (1987), 0.34(1988),0.39(1992),0.39(1993). These results showed that the environmental situation, estimated by using the frequencies of micronucleated cells, was stable-there was no obvious chromosome damage in the animals studied. It was found that the incidence of micronucleated cells of Bivalves was higher than that of Fish and Amphibia, suggesting the epithelial cells to be more sensitive than peripheral erythrocytes to environmental genotoxic effects. The results of our studies for other spots will be reported afterward. These data can be used as the original background information to monitor the environment when the Nuclear Power Station is in operation.

  5. Construction and preoperational test of Kashiwasaki-Kariwa Nuclear Power Station Unit No. 6

    Energy Technology Data Exchange (ETDEWEB)

    Natsume, Nobuo; Noda, Hiroshi [Tokyo Electric Power Co. (Japan)

    1996-12-31

    Unit 6 of the Kashiwazaki-Kariwa nuclear power station of Tokyo Electric Power Company, the world`s first advanced boiling water reactor (ABWR), is progressing ahead of the originally established schedule since the start of its construction in September 1991, and commercial operation is scheduled to start before the end of 1996.

  6. 78 FR 40200 - Duke Energy Carolinas, LLC, Oconee Nuclear Station Units 1, 2, and 3; Independent Spent Fuel...

    Science.gov (United States)

    2013-07-03

    ... COMMISSION Duke Energy Carolinas, LLC, Oconee Nuclear Station Units 1, 2, and 3; Independent Spent Fuel...) for an exemption request submitted by Duke Energy Carolinas, LLC, on August 13, 2012 for the Oconee Nuclear Station Independent Spent Fuel Storage Facility (ISFSI). ] ADDRESSES: Please refer to Docket...

  7. Technology, Safety and Costs of Decommissioning Nuclear Reactors At Multiple-Reactor Stations

    Energy Technology Data Exchange (ETDEWEB)

    Wittenbrock, N. G.

    1982-01-01

    Safety and cost information is developed for the conceptual decommissioning of large (1175-MWe) pressurized water reactors (PWRs) and large (1155-MWe) boiling water reactors {BWRs) at multiple-reactor stations. Three decommissioning alternatives are studied: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). Safety and costs of decommissioning are estimated by determining the impact of probable features of multiple-reactor-station operation that are considered to be unavailable at a single-reactor station, and applying these estimated impacts to the decommissioning costs and radiation doses estimated in previous PWR and BWR decommissioning studies. The multiple-reactor-station features analyzed are: the use of interim onsite nuclear waste storage with later removal to an offsite nuclear waste disposal facility, the use of permanent onsite nuclear waste disposal, the dedication of the site to nuclear power generation, and the provision of centralized services. Five scenarios for decommissioning reactors at a multiple-reactor station are investigated. The number of reactors on a site is assumed to be either four or ten; nuclear waste disposal is varied between immediate offsite disposal, interim onsite storage, and immediate onsite disposal. It is assumed that the decommissioned reactors are not replaced in one scenario but are replaced in the other scenarios. Centralized service facilities are provided in two scenarios but are not provided in the other three. Decommissioning of a PWR or a BWR at a multiple-reactor station probably will be less costly and result in lower radiation doses than decommissioning an identical reactor at a single-reactor station. Regardless of whether the light water reactor being decommissioned is at a single- or multiple-reactor station: • the estimated occupational radiation dose for decommissioning an LWR is lowest for SAFSTOR and highest for DECON • the estimated

  8. Computerized training program usage at the Fort Calhoun Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Ruzic, D.H.; Reed, W.H.; Lawton, R.K.; Fluehr, J.J.

    1987-01-01

    The increased US Nuclear Regulatory Commission and Institute of Nuclear Power Operations (INPO) interest in the nuclear power industry training programs resulted in the Omaha Public Power District staff at the Fort Calhoun Nuclear Power Station investigating the potential for computerizing their recently accredited training records, student training requirements, and the process of determining student certification status. Additional areas that were desirable were a computerized question data bank with random test generation, maintaining history of question usage, and tracking of the job task analysis process and course objectives. SCI Software's online personnel training information management system (OPTIM) was selected, subsequent to a bid evaluation, to provide these features while operating on the existing corporate IBM mainframe.

  9. 77 FR 11168 - In the Matter of Exelon Corporation; Constellation Energy Group, Inc.; Nine Mile Nuclear Station...

    Science.gov (United States)

    2012-02-24

    ... Exelon Corporation; Constellation Energy Group, Inc.; Nine Mile Nuclear Station, LLC; Nine Mile Point... Ventures), and Constellation Energy Nuclear Group, LLC (CENG), acting on behalf of itself, and the licensee... Committee of Constellation Energy Nuclear Group, LLC, shall prepare an Annual Report regarding the status...

  10. 78 FR 6839 - Duke Energy Carolinas, LLC, Oconee Nuclear Station, Units 1, 2, and 3 Denial of Amendment to...

    Science.gov (United States)

    2013-01-31

    ... From the Federal Register Online via the Government Publishing Office ] NUCLEAR REGULATORY COMMISSION Duke Energy Carolinas, LLC, Oconee Nuclear Station, Units 1, 2, and 3 Denial of Amendment to Facility Operating License AGENCY: Nuclear Regulatory Commission. ACTION: Denial; opportunity to request...

  11. Implicit attitudes toward nuclear power and mobile phone base stations: support for the affect heuristic.

    Science.gov (United States)

    Siegrist, Michael; Keller, Carmen; Cousin, Marie-Eve

    2006-08-01

    The implicit association test (IAT) measures automatic associations. In the present research, the IAT was adapted to measure implicit attitudes toward technological hazards. In Study 1, implicit and explicit attitudes toward nuclear power were examined. Implicit measures (i.e., the IAT) revealed negative attitudes toward nuclear power that were not detected by explicit measures (i.e., a questionnaire). In Study 2, implicit attitudes toward EMF (electro-magnetic field) hazards were examined. Results showed that cell phone base stations and power lines are judged to be similarly risky and, further, that base stations are more closely related to risk concepts than home appliances are. No differences between experts and lay people were observed. Results of the present studies are in line with the affect heuristic proposed by Slovic and colleagues. Affect seems to be an important factor in risk perception.

  12. Thermal-hydraulic tests of a recirculation cooling installation for the Rostov nuclear power station

    Science.gov (United States)

    Balunov, B. F.; Balashov, V. A.; Il'in, V. A.; Krayushnikov, V. V.; Lychakov, V. D.; Meshalkin, V. V.; Ustinov, A. N.; Shcheglov, A. A.

    2013-09-01

    Results obtained from thermal-hydraulic tests of the recirculation cooling installation used as part of the air cooling system under the containments of the Rostov nuclear power station Units 3 and 4 are presented. The operating modes of the installation during normal operation (air cooling on the surface of finned tubes), under the conditions of anticipated operational occurrences (air cooling and steam condensation from a steam-air mixture), and during an accident (condensation of pure steam) are considered. Agreement is obtained between the results of tests and calculations carried out according to the recommendations given in the relevant regulatory documents. A procedure of carrying out thermal calculation for the case of steam condensation from a steam-air mixture on the surface of fins is proposed. The possibility of efficient use of the recirculation cooling installation in the system for reducing emergency pressure under the containment of a nuclear power station is demonstrated.

  13. The effects of solar-geomagnetically induced currents on electrical systems in nuclear power stations

    Energy Technology Data Exchange (ETDEWEB)

    Subudhi, M. [Brookhaven National Lab., Upton, NY (United States); Carroll, D.P. [Florida Univ., Gainesville, FL (United States); Kasturi, S. [MOS, Inc., Melville, NY (United States)

    1994-01-01

    This report presents the results of a study to evaluate the potential effects of geomagnetically induced currents (GICs) caused by the solar disturbances on the in-plant electrical distribution system and equipment in nuclear power stations. The plant-specific electrical distribution system for a typical nuclear plant is modeled using the ElectroMagnetic Transient Program (EMTP). The computer model simulates online equipment and loads from the station transformer in the switchyard of the power station to the safety-buses at 120 volts to which all electronic devices are connected for plant monitoring. The analytical model of the plant`s electrical distribution system is studied to identify the transient effects caused by the half-cycle saturation of the station transformers due to GIC. This study provides results of the voltage harmonics levels that have been noted at various electrical buses inside the plant. The emergency circuits appear to be more susceptible to high harmonics due to the normally light load conditions. In addition to steady-state analysis, this model was further analyzed simulating various plant transient conditions (e.g., loss of load or large motor start-up) occurring during GIC events. Detail models of the plant`s protective relaying system employed in bus transfer application were included in this model to study the effects of the harmonic distortion of the voltage input. Potential harmonic effects on the uniterruptable power system (UPS) are qualitatively discussed as well.

  14. Numerical analysis of transient pressure variation in the condenser of a nuclear power station

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Xinjun; Zhou, Zijie; Song, Zhao [Xi' an Jiaotong University, Xi' an (China); Lu, Qiankui; Li, Jiafu [Dong Fang Turbine Co., Ltd, Deyang (China)

    2016-02-15

    To research the characteristics of the transient variation of pressure in a nuclear power station condenser under accident condition, a mathematical model was established which simulated the cycling cooling water, heat transfer and pressure in the condenser. The calculation program of transient variation characteristics was established in Fortran language. The pump's parameter, cooling line's organization, check valve's feature and the parameter of siphonic water-collecting well are involved in the cooling water flow's mathematical model. The initial conditions of control volume are determined by the steady state of the condenser. The transient characteristics of a 1000 MW nuclear power station's condenser and cooling water system were examined. The results show that at the condition of plant-power suspension of pump, the cooling water flow rate decreases rapidly and refluxes, then fluctuates to 0. The variation of heat transfer coefficient in the condenser has three stages: at start it decreases sharply, then increases and decreases, and keeps constant in the end. Under three conditions (design, water and summer), the condenser pressure goes up in fluctuation. The time intervals between condenser's pressure signals under three conditions are about 26.4 s, which can fulfill the requirement for safe operation of nuclear power station.

  15. Simulation of Temperature, Nutrients, Biochemical Oxygen Demand, and Dissolved Oxygen in the Catawba River, South Carolina, 1996-97

    Science.gov (United States)

    Feaster, Toby D.; Conrads, Paul A.; Guimaraes, Wladmir B.; Sanders, Curtis L.; Bales, Jerad D.

    2003-01-01

    Time-series plots of dissolved-oxygen concentrations were determined for various simulated hydrologic and point-source loading conditions along a free-flowing section of the Catawba River from Lake Wylie Dam to the headwaters of Fishing Creek Reservoir in South Carolina. The U.S. Geological Survey one-dimensional dynamic-flow model, BRANCH, was used to simulate hydrodynamic data for the Branched Lagrangian Transport Model. Waterquality data were used to calibrate the Branched Lagrangian Transport Model and included concentrations of nutrients, chlorophyll a, and biochemical oxygen demand in water samples collected during two synoptic sampling surveys at 10 sites along the main stem of the Catawba River and at 3 tributaries; and continuous water temperature and dissolved-oxygen concentrations measured at 5 locations along the main stem of the Catawba River. A sensitivity analysis of the simulated dissolved-oxygen concentrations to model coefficients and data inputs indicated that the simulated dissolved-oxygen concentrations were most sensitive to watertemperature boundary data due to the effect of temperature on reaction kinetics and the solubility of dissolved oxygen. Of the model coefficients, the simulated dissolved-oxygen concentration was most sensitive to the biological oxidation rate of nitrite to nitrate. To demonstrate the utility of the Branched Lagrangian Transport Model for the Catawba River, the model was used to simulate several water-quality scenarios to evaluate the effect on the 24-hour mean dissolved-oxygen concentrations at selected sites for August 24, 1996, as simulated during the model calibration period of August 23 27, 1996. The first scenario included three loading conditions of the major effluent discharges along the main stem of the Catawba River (1) current load (as sampled in August 1996); (2) no load (all point-source loads were removed from the main stem of the Catawba River; loads from the main tributaries were not removed); and (3

  16. International Remote Monitoring Project Embalse Nuclear Power Station, Argentina Embalse Remote Monitoring System

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, Sigfried L.; Glidewell, Donnie D.; Bonino, Anibal; Bosler, Gene; Mercer, David; Maxey, Curt; Vones, Jaromir; Martelle, Guy; Busse, James; Kadner, Steve; White, Mike; Rovere, Luis

    1999-07-21

    The Autoridad Regulatoria Nuclear of Argentina (ARN), the International Atomic Energy Agency (IAEA), ABACC, the US Department of Energy, and the US Support Program POTAS, cooperated in the development of a Remote Monitoring System for nuclear nonproliferation efforts. This system was installed at the Embalse Nuclear Power Station last year to evaluate the feasibility of using radiation sensors in monitoring the transfer of spent fuel from the spent fuel pond to dry storage. The key element in this process is to maintain continuity of knowledge throughout the entire transfer process. This project evaluated the fundamental design and implementation of the Remote Monitoring System in its application to regional and international safeguard efficiency. New technology has been developed to enhance the design of the system to include storage capability on board sensor platforms. This evaluation has led to design enhancements that will assure that no data loss will occur during loss of RF transmission of the sensors.

  17. 75 FR 7628 - Davis-Besse Nuclear Power Station; Notice of Consideration of Issuance of Amendment to Facility...

    Science.gov (United States)

    2010-02-22

    ... COMMISSION Davis-Besse Nuclear Power Station; Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a... determination that the amendment request involves no significant hazards consideration. Under the...

  18. Shoot regeneration from petioles and leaves of Vitis X labruscana 'Catawba'.

    Science.gov (United States)

    Cheng, Z M; Reisch, B I

    1989-10-01

    Shoot regeneration and normal plants were obtained from leaf and petiole explants derived from in vitro grown shoots of Vitis X labruscana 'Catawba'. Regeneration was induced in the presence of both 6-benzylaminopurine and indole-3-butyric acid; combinations of 2,4-dichlorophenoxyacetic acid or 2-naphthoxyacetic acid with 6-benzylaminopurine did not permit regeneration from leaf explants. Up to 15% of leaf and 70% of petiole explants regenerated shoots on media with 5.0-10.0 μM BA and 0.1-0.5 μM IBA. Incubation in the dark was required to obtain regeneration. About 50% of shoots developed normally following transfer to light. An average of one shoot regenerated from leaf explants and 3.3 shoots regenerated per petiole explant. Regeneration from petioles and leaves was always from the basipetal end. The interaction of 6-benzylaminopurine with indole-3-butyric acid was also examined.

  19. Cooling tower restoration in the joint nuclear power station Neckar 1; Kuehlturmsanierung im Gemeinschaftskernkraftwerk Neckar 1

    Energy Technology Data Exchange (ETDEWEB)

    Ernst, G. [Karlsruhe Univ. (T.H.) (Germany). Inst. fuer Technische Thermodynamik; Braeuning, G. [Karlsruhe Univ. (T.H.) (Germany). Inst. fuer Technische Thermodynamik; Dekker, G. [Marley Kuehlturm GmbH, Duesseldorf (Germany). Bereich Vertrieb neuer Kuhlturm-Anlagen

    1996-11-01

    Since the starting operation of the Power Station GKN I (Joint Nuclear Power Station Neckar I) in the year 1976, the cell cooler of the plant was, except for those cases in which continuous-flow cooling was possible, continually in operation. Aim of the restoration, after an operational time of 17 years, is a further constructional and thermal service life of about 15 to 20 years. (orig.) [Deutsch] Seit der Inbetriebnahme des Kraftwerkes GKN I im Jahr 1976 war der Zellenkuehler der Anlage bis auf die Faelle, in denen Durchlaufkuehlung moeglich war, ununterbrochen in Betrieb. Ziel der Sanierung nach ueber 17jaehriger Betriebszeit ist eine weitere bauliche und thermische Nutzungsdauer von etwa 15 bis 20 Jahren. (orig.)

  20. 78 FR 45987 - Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to...

    Science.gov (United States)

    2013-07-30

    ... COMMISSION Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to... COLs were issued to Southern Nuclear Operating Company, Inc., and Georgia Power Company, Oglethorpe... Search.'' For problems with ADAMS, please contact the NRC's Public Document Room (PDR) reference staff...

  1. 78 FR 45989 - Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to...

    Science.gov (United States)

    2013-07-30

    ... COMMISSION Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to... COLs were issued to Southern Nuclear Operating Company, Inc., and Georgia Power Company, Oglethorpe..., select ``ADAMS Public Documents'' and then select ``Begin Web-based ADAMS Search.'' For problems...

  2. 75 FR 43572 - Duke Energy Carolinas, LLC, McGuire Nuclear Station, Units 1 and 2; Environmental Assessment and...

    Science.gov (United States)

    2010-07-26

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Duke Energy Carolinas, LLC, McGuire Nuclear Station, Units 1 and 2; Environmental Assessment and... No. NPF-17, issued to Duke Energy Carolinas, LLC (the licensee), for operation of the McGuire...

  3. Radiation exposure to the orbiting lunar station and lunar surface related to reusable nuclear shuttle operations

    Science.gov (United States)

    Hutchinson, P. I.

    1972-01-01

    The radiation environment created by the Reusable Nuclear Vehicle (RNS) in performing its normal mission functions while in the lunar vicinity and the impact of that environment on the Orbiting Lunar Station (OLS) and/or the lunar surface are examined. Lunar surface exposures from the operating reactor were evaluated for both the arrival and departure burns and while there is little probability that manned bases would lie along the paths in which measurable exposures would be recorded, the analyses do indicate the need to consider this possibility in planning such operations. Conclusions supported by the analyses and recommended operational constraints for the RNS are presented.

  4. Personnel exposure control system with auto thermoluminescence dosimeter in Shimane Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Matsubayashi, Hideo; Ochi, Susumu (Chugoku Electric Power Co. Inc., Hiroshima (Japan))

    1982-03-01

    In the past, film badges and pocket dosimeters were put on the persons who entered a controlled area in a nuclear power station to measure the external radiation exposure. For these, read out error or mistake, delay in taking out the result, trouble for monitoring many persons, etc. were problems. To solve these problems, the auto thermoluminescence dosimeter (ATLD) system has been introduced in Shimane Nuclear Power Station in place of pocket dosimeters since the second half of fiscal 1978. The outline of the system and the composition and software of the TLD automatic readout system are described. For the control of access to controlled areas, workers are forced to pass the check point where watchmen check everyone's ID card, and subjected to the check-up with the TLD automatic readout device. The checking items in the case of entering the areas are: (1) confirmation of licensee, (2) confirmation of the term of validity for the medical examination on ionizing radiation, (3) checking for exposure dose compared to the controlled exposure level, (4) confirmation of time limit to stay in controlled areas, and (5) TLD element annealing condition. The checking items in the case of leaving the areas are: (1) checking for identifying the TLD element that the personnel has brought in, (2) exposure dose compared to the controlled exposure level, (3) time for which the personnel stayed in controlled areas.

  5. Program for the thermal design and simulation of the operation of a steam condenser for thermal and nuclear power stations and its application to the condenser at the Cofrentes nuclear power station

    Energy Technology Data Exchange (ETDEWEB)

    Garcia Bartual, R.; Pallares Huici, E.

    A program is being developed for an IBM-PC or AT computer based on a calculation system which synthesises the heat transfer process which takes place in the steam condensors at conventional thermal power stations. The program incorporates a useful tool capable of representing characteristic operating curves for a given condensor. Describes its application to the steam condenser at the Cofrentes nuclear power station. 4 refs., 5 tabs., 8 figs.

  6. Report of examination of the ruptured pipe at the Hamaoka Nuclear Power Station Unit-1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-12-01

    In order to investigate root cause of the pipe rupture, which took place at the Hamaoka Nuclear Power Station Unit-1 of Chubu Electric Power Company on November 7, 2001, a task force was established within the Nuclear and Industrial Safety Agency (NISA) and initiated a detailed investigation of the ruptured pipe. The Japan Atomic Energy Research Institute (JAERI) was asked from the Ministry of Education, Culture, Sports, Science and Technology (MEXT) in response to the request from NISA to cooperate as an independent neutral organization with NISA and perform an examination of the ruptured pipe independently from Chubu Electric Power Company. JAERI accepted the request by considering the fact that JAERI is an integrated research institution for nuclear research and development, a prime research institution for nuclear safety research, a research institution with experience of root-cause investigation of various nuclear incidents and accidents of domestic as well as overseas, and a research institution provided with advanced examination facilities necessary for examination of the ruptured pipe. The JAERI examination group was formed at the Tokai Research Establishment and conducted detailed and thorough examination of the pieces taken from the ruptured pipe primarily in the Reactor Fuel Examination Facility (RFEF) with the use of tools such as scanning electron microscopes and other equipments. Purpose of examination was to provide technical information in order to identify causes of the pipe rupture through examination of the pieces taken from the ruptured region of the pipe. The following findings and conclusion were made as the result of the present examination. (1) Wall thickness of the pipe was significantly reduced in the ruptured region. (2) Dimple pattern resulting from ductile fracture by shearing was observed in the fracture surfaces of nearly all of the pieces and no indication of fatigue crack growth was found. (3) Microstructure showed a typical carbon

  7. 77 FR 66484 - PSEG Nuclear LLC; Hope Creek Generating Station and Salem Generating Station, Units 1 and 2...

    Science.gov (United States)

    2012-11-05

    ... for Nuclear Power Plant Personnel,'' endorses the Nuclear Energy Institute (NEI) report, NEI 06-11, Revision 1, ``Managing Personnel Fatigue at Nuclear Power Plants,'' with clarifications, additions and... emergency, the licensee is immediately subject to the scheduling requirements of 10 CFR 26.205(c) and...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1999-12-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-03-01

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

  10. The assessment of external photon dose rate in the vicinity of nuclear power stations. An intercomparison of different monitoring systems

    DEFF Research Database (Denmark)

    Thompson, I.M.G.; Bøtter-Jensen, L.; Lauterbach, U.;

    1993-01-01

    to a nuclear power station. The responses of each of these detectors to the natural radiation and to the radiation from the power station are given. Estimations by three of the dose rate instruments of the air kerma from all the radiation components are intercompared with the results from three different types...... of thermoluminescence dosemeter. The results clearly demonstrate that accurate estimations of doses in the environment arising from a nuclear facility can only be obtained if the responses of the detectors used to the different radiation components at that location are accurately evaluated. By correcting the measured...

  11. Second periodic safety review of Angra Nuclear Power Station, unit 1

    Energy Technology Data Exchange (ETDEWEB)

    Martins, Carlos F.O.; Crepaldi, Roberto; Freire, Enio M., E-mail: ottoncf@tecnatom.com.br, E-mail: emfreire46@gmail.com, E-mail: robcrepaldi@hotmail.com [Tecnatom do Brasil Engenharia e Servicos Ltda, Rio de Janeiro, RJ (Brazil); Campello, Sergio A., E-mail: sacampe@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil)

    2015-07-01

    This paper describes the second Periodic Safety Review (PSR2-A1) of Angra Nuclear Power Station, Unit 1, prepared by Eletrobras Eletronuclear S.A. and Tecnatom do Brasil Engenharia e Servicos Ltda., during Jul.2013-Aug.2014, covering the period of 2004-2013. The site, in Angra dos Reis-RJ, Brazil, comprises: Unit 1, (640 MWe, Westinghouse PWR, operating), Unit 2 (1300 MWe, KWU/Areva, operating) and Unit 3 (1405 MWe, KWU/Areva, construction). The PSR2-A1 attends the Standards 1.26-Safety in Operation of Nuclear Power Plants, Brazilian Nuclear Regulatory Commission (CNEN), and IAEA.SSG.25-Periodic Safety Review of Nuclear Power Plants. Within 18 months after each 10 years operation, the operating organization shall perform a plant safety review, to investigate the evolution consequences of safety code and standards, regarding: Plant design; structure, systems and components behavior; equipment qualification; plant ageing management; deterministic and probabilistic safety analysis; risk analysis; safety performance; operating experience; organization and administration; procedures; human factors; emergency planning; radiation protection and environmental radiological impacts. The Review included 6 Areas and 14 Safety Parameters, covered by 33 Evaluations.After document evaluations and discussions with plant staff, it was generated one General and 33 Specific Guide Procedures, 33 Specific and one Final Report, including: Description, Strengths, Deficiencies, Areas for Improvement and Conclusions. An Action Plan was prepared by Electronuclear for the recommendations. It was concluded that the Unit was operated within safety standards and will attend its designed operational lifetime, including possible life extensions. The Final Report was submitted to CNEN, as one requisite for renewal of the Unit Permanent Operation License. (author)

  12. Upgrade of the SPIRAL identification station for high-precision measurements of nuclear β decay

    Energy Technology Data Exchange (ETDEWEB)

    Grinyer, G.F., E-mail: grinyer@ganil.fr [Grand Accélérateur National d' Ions Lourds (GANIL), CEA/DSM-CNRS/IN2P3, Bvd Henri Becquerel, 14076 Caen (France); Thomas, J.C. [Grand Accélérateur National d' Ions Lourds (GANIL), CEA/DSM-CNRS/IN2P3, Bvd Henri Becquerel, 14076 Caen (France); Blank, B. [Centre d’Études Nucléaires de Bordeaux Gradignan, Université Bordeaux 1, UMR 5797, CNRS/IN2P3, Chemin de Solarium, BP 120, 33175 Gradignan (France); Bouzomita, H. [Grand Accélérateur National d' Ions Lourds (GANIL), CEA/DSM-CNRS/IN2P3, Bvd Henri Becquerel, 14076 Caen (France); Austin, R.A.E. [Astronomy and Physics Department, Saint Mary' s University, Halifax, Nova Scotia, Canada B3H 3C3 (Canada); Ball, G.C. [TRIUMF, 4004 Wesbrook Mall, Vancouver, British Columbia, Canada V6T 2A3 (Canada); Bucaille, F.; Delahaye, P. [Grand Accélérateur National d' Ions Lourds (GANIL), CEA/DSM-CNRS/IN2P3, Bvd Henri Becquerel, 14076 Caen (France); Finlay, P. [Instituut voor Kern- en Stralingsfysica, K.U. Leuven, Celestijnenlaan 200D, B-3001 Leuven (Belgium); Frémont, G. [Grand Accélérateur National d' Ions Lourds (GANIL), CEA/DSM-CNRS/IN2P3, Bvd Henri Becquerel, 14076 Caen (France); Gibelin, J. [LPC-Caen, ENSICAEN, Université de Caen, CNRS/IN2P3, Caen (France); Giovinazzo, J. [Centre d’Études Nucléaires de Bordeaux Gradignan, Université Bordeaux 1, UMR 5797, CNRS/IN2P3, Chemin de Solarium, BP 120, 33175 Gradignan (France); and others

    2014-03-21

    The low-energy identification station at SPIRAL (Système de Production d'Ions Radioactifs Accélérés en Ligne) has been upgraded for studying the β decays of short-lived radioactive isotopes and to perform high-precision half-life and branching-ratio measurements for superallowed Fermi and isospin T=1/2 mirror β decays. These new capabilities, combined with an existing Paul trap setup for measurements of β–ν angular-correlation coefficients, provide a powerful facility for investigating fundamental properties of the electroweak interaction through nuclear β decays. A detailed description of the design study, construction, and first results obtained from an in-beam commissioning experiment on the β{sup +} decays {sup 14} O and {sup 17}F are presented.

  13. Evaluation of activated nuclides for Fugen Nuclear Power Station's decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Shiratori, Yoshitake; Kawagoe, Shinji; Matsui, Yuji; Higashiura, Norikazu [Japan Nuclear Cycle Development Inst., Tsuruga Head Office, Tsuruga, Fukui (Japan); Iwasaki, Seiji [Nuclear Energy System Inc., Tokyo (Japan)

    2002-09-01

    The density and amount of radioactive nuclides in equipment or concrete including the reactor core need to be evaluated for the decommissioning of the Fugen Nuclear Power Station. To prepare for decommissioning, measurement and evaluation of the neutron flux density have been executed mainly during the reactor operation, because neutron flux density is measured under that condition. Activation evaluation is mainly executed by the calculation method, and the results are checked by the sampling measurements. All of the equipments is divided into three parts, inner core part, shielding part, outer shielding part. The neutron flux distribution of two former parts can be evaluated by calculation, but the last part cannot; it is evaluated by measuring the activation foil for many points. These evaluation methods are checked by a small number of sampling measurements. (author)

  14. Environmental radiological studies downstream from Rancho Seco Nuclear Power Generating Station

    Energy Technology Data Exchange (ETDEWEB)

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

    1985-03-22

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

  15. A modernized high-pressure heater protection system for nuclear and thermal power stations

    Science.gov (United States)

    Svyatkin, F. A.; Trifonov, N. N.; Ukhanova, M. G.; Tren'kin, V. B.; Koltunov, V. A.; Borovkov, A. I.; Klyavin, O. I.

    2013-09-01

    Experience gained from operation of high-pressure heaters and their protection systems serving to exclude ingress of water into the turbine is analyzed. A formula for determining the time for which the high-pressure heater shell steam space is filled when a rupture of tubes in it occurs is analyzed, and conclusions regarding the high-pressure heater design most advisable from this point of view are drawn. A typical structure of protection from increase of water level in the shell of high-pressure heaters used in domestically produced turbines for thermal and nuclear power stations is described, and examples illustrating this structure are given. Shortcomings of components used in the existing protection systems that may lead to an accident at the power station are considered. A modernized protection system intended to exclude the above-mentioned shortcomings was developed at the NPO Central Boiler-Turbine Institute and ZioMAR Engineering Company, and the design solutions used in this system are described. A mathematical model of the protection system's main elements (the admission and check valves) has been developed with participation of specialists from the St. Petersburg Polytechnic University, and a numerical investigation of these elements is carried out. The design version of surge tanks developed by specialists of the Central Boiler-Turbine Institute for excluding false operation of the high-pressure heater protection system is proposed.

  16. The International Remote Monitoring Project -- First results of the Argentina nuclear power station field trial

    Energy Technology Data Exchange (ETDEWEB)

    Bonino, A.; Pizarro, L.; Perez, A. [Ente Nacional Regulador Nuclear, Buenos Aires (Argentina); Schoeneman, J.L.; Dupree, S.A.; Martinez, R.L. [Sandia National Labs., Albuquerque, NM (United States); Maxey, C. [Oak Ridge National Lab., TN (United States)

    1995-12-31

    As part of the International Remote Monitoring Project field trials, during the month of March, 1995 a Remote Monitoring System (RMS) was installed at the Embalse Nuclear Power Station in Embalse, Argentina. This system monitors the status of four typical Candu spent fuel dry storage silos. The monitoring equipment for each silo consists of analog temperature and gamma radiation sensors and digital motion and electronic fiber-optic seals connected to a wireless Authenticate Item Monitoring System (AIMS). All sensor data are authenticated and transmitted via RF link to Receiver Processor Units (RPU) coupled to Remote Monitoring System equipment located in a nearby IAEA/ENREN inspector office. One of these RPUs is connected to Remote Monitoring equipment capable of information transmission (via commercial telephone links) to Data Review Stations (DRS) at ENREN laboratories in Buenos Aires, Argentina, and at Sandia National Laboratories, Albuquerque, New Mexico. The other RPU is used for on-site data storage and analysis. It is anticipated that this information will soon be transmitted to a DRS at the ABACC facility in Rio de Janeiro, Brazil. During these trials site data will be collected and analyzed periodically from Buenos Aires, Albuquerque, and Rio de Janeiro. Installation detail and data analysis will be presented in this paper.

  17. Structural integrity analysis of the degraded drywell containment at the Oyster Creek Nuclear generating station.

    Energy Technology Data Exchange (ETDEWEB)

    Petti, Jason P.

    2007-01-01

    This study examines the effects of the degradation experienced in the steel drywell containment at the Oyster Creek Nuclear Generating Station. Specifically, the structural integrity of the containment shell is examined in terms of the stress limits using the ASME Boiler and Pressure Vessel (B&PV) Code, Section III, Division I, Subsection NE, and examined in terms of buckling (stability) using the ASME B&PV Code Case N-284. Degradation of the steel containment shell (drywell) at Oyster Creek was first observed during an outage in the mid-1980s. Subsequent inspections discovered reductions in the shell thickness due to corrosion throughout the containment. Specifically, significant corrosion occurred in the sandbed region of the lower sphere. Since the presence of the wet sand provided an environment which supported corrosion, a series of analyses were conducted by GE Nuclear Energy in the early 1990s. These analyses examined the effects of the degradation on the structural integrity. The current study adopts many of the same assumptions and data used in the previous GE study. However, the additional computational recourses available today enable the construction of a larger and more sophisticated structural model.

  18. 78 FR 45575 - Duke Energy Carolinas, LLC; Oconee Nuclear Station Units 1, 2, and 3; Independent Spent Fuel...

    Science.gov (United States)

    2013-07-29

    ... COMMISSION [Docket Nos.: 72-1004, 72-40, 50-269, 50-270, 50-287; and NRC-2013- 0135] Duke Energy Carolinas, LLC; Oconee Nuclear Station Units 1, 2, and 3; Independent Spent Fuel Storage Installation AGENCY... response to a request submitted by Duke Energy Carolinas, LLC., on August 13, 2012, for the Oconee...

  19. 75 FR 67784 - STP Nuclear Operating Company South Texas Project Electric Generating Station, Units 3 and 4...

    Science.gov (United States)

    2010-11-03

    ... Water Act Section 402(p) Texas Pollutant Discharge Elimination System (TPDES) general permit for... surface water quality. BMPs would be ] described in a Stormwater Pollution Prevention Plan (SWPPP) that... COMMISSION STP Nuclear Operating Company South Texas Project Electric Generating Station, Units 3 and...

  20. 78 FR 79017 - Zion Solutions, LLC; Zion Nuclear Power Station, Units 1 and 2; Exemption From Certain Physical...

    Science.gov (United States)

    2013-12-27

    ... COMMISSION Zion Solutions, LLC; Zion Nuclear Power Station, Units 1 and 2; Exemption From Certain Physical... shut down facility and responsibility for its decommissioning was transferred to ZionSolutions (ZS), a subsidiary of EnergySolutions. ZS was established solely for the purpose of acquiring and decommissioning...

  1. 75 FR 14634 - Dominion Nuclear Connecticut, Inc.; Millstone Power Station, Unit Nos. 1, 2, and 3; Environmental...

    Science.gov (United States)

    2010-03-26

    ...-49, issued to Dominion Nuclear Connecticut, Inc. (DNC or the licensee) for operation of Millstone... with certain new requirements contained in 10 CFR 73.55 by the March 31, 2010, deadline. DNC has... beyond the date required by 10 ] CFR part 73, for certain alarm station requirements. DNC has...

  2. 77 FR 49463 - Southern California Edison, San Onofre Nuclear Generating Station, Units 2 and 3; Application and...

    Science.gov (United States)

    2012-08-16

    ... Edison Company (SCE, the licensee) for operation of the San Onofre Nuclear Generating Station (SONGS... request (LAR) for SONGS, Units 2 and 3, dated July 29, 2011, requesting approval to convert the Current... Technical Specifications (STS) for Combustion Engineering Plants, NUREG-1432. In 1996, SONGS was the...

  3. Addressing Obsolescence in Operating Power Stations by Implementation of Safety Related Digital Upgrades Paper for Spanish Nuclear Society

    Energy Technology Data Exchange (ETDEWEB)

    Legrand, R.

    2014-07-01

    Obsolescence of Instrumentation and Controls is a major problem facing operating Nuclear Power Stations globally. AREVA is the only supplier that has supported the successful licensing, engineering, procurement, installation and commissioning of a full-scope digital Instrumentation and Control (I and C) Protection System in the United States. (Author)

  4. Field measurements of beta ray energy spectra in CANDU nuclear generating stations

    Energy Technology Data Exchange (ETDEWEB)

    Horowitz, Y.S. (Ben-Gurion Univ. of the Negev, Beersheba (Israel). Dept. of Physics); Hirning, C.R. (Ontario Hydro, Whitby, ON (Canada)); Yuen, P.S.; Aikens, M.S. (AECL Research, Chalk River, ON (Canada). Chalk River Labs.)

    1994-01-01

    Field measurements of beta ray energy spectra have been carried out at various locations in CANDU nuclear generating stations operated by Ontario Hydro. The beta ray energy spectrometer consists of a 5 cm diameter x 2 cm thick BC-404 plastic scintillator situated behind a 100 [mu]m thick, totally depleted, silicon detector. Photon events are rejected by requiring a coincidence between the two detectors. The spectrometer is capable of measuring electron energies from 125 keV to 3.5 MeV. Beta ray energy spectra have been measured for uncontaminated and contaminated fueling machine components, fueling machine swipes and a reactor containment vault. The degree of protection afforded by various articles of protective clothing has also been investigated for the various fueling machine components. Monte Carlo calculations have been used to estimate beta factors for 100 mg.cm[sup -2] and 240 mg.cm[sup -2] LiF-TLD chips, which are used as 'skin-and 'extremity' dosemeters in the Ontario Hydro Radiation Dosimetry Programme. (Author).

  5. Application of seismic isolation technology to computer system in nuclear power stations

    Energy Technology Data Exchange (ETDEWEB)

    Gunyasu, Kenzou; Takamatsu, Naotaka; Fujimoto, Shigeru; Fukui, Hidehiro (Toshiba Corp., Kawasaki, Kanagawa (Japan))

    1994-08-01

    In the current aseismatic design, the rigid structures that withstand earthquakes by own strength have been adopted. However recently, seismically isolated structures were devised, and begin to be applied to buildings and others. It is characterized by that the basic structures as the object of seismic isolation are not changed, and by using special seismic isolators, the structures are made flexible to avoid the resonance with the eminent period of earthquakes and reduce the earthquake force acting on the structures. As the concrete example of seismic isolation, in Japan, seismically isolated floors have been introduced for the computer centers of banks. Also in nuclear power stations, the application of seismic isolation to computer systems has been considered. The function, constitution, structure and the method of increasing the aseismatic capability of computer system are explained. The function required for seismic isolation floors, the seismic isolation structure of rolling type composed of coil springs, dampers and ball bearings, its principle of action, and the vibration test on the seismic isolation floor are reported. (K.I.).

  6. Radiation dose reduction efficiency of buildings after the accident at the Fukushima Daiichi Nuclear Power Station.

    Directory of Open Access Journals (Sweden)

    Satoru Monzen

    Full Text Available Numerous radionuclides were released from the Fukushima Daiichi Nuclear Power Station (F1-NPS in Japan following the magnitude 9.0 earthquake and tsunami on March 11, 2011. Local residents have been eager to calculate their individual radiation exposure. Thus, absorbed dose rates in the indoor and outdoor air at evacuation sites in the Fukushima Prefecture were measured using a gamma-ray measuring devices, and individual radiation exposure was calculated by assessing the radiation dose reduction efficiency (defined as the ratio of absorbed dose rate in the indoor air to the absorbed dose rate in the outdoor air of wood, aluminum, and reinforced concrete buildings. Between March 2011 and July 2011, dose reduction efficiencies of wood, aluminum, and reinforced concrete buildings were 0.55 ± 0.04, 0.15 ± 0.02, and 0.19 ± 0.04, respectively. The reduction efficiency of wood structures was 1.4 times higher than that reported by the International Atomic Energy Agency. The efficiency of reinforced concrete was similar to previously reported values, whereas that of aluminum structures has not been previously reported. Dose reduction efficiency increased in proportion to the distance from F1-NPS at 8 of the 18 evacuation sites. Time variations did not reflect dose reduction efficiencies at evacuation sites although absorbed dose rates in the outdoor air decreased. These data suggest that dose reduction efficiency depends on structure types, levels of contamination, and evacuee behaviors at evacuation sites.

  7. 田湾核电站核安全文化建设%The Cultivation and Development of Nuclear Safety Culture in Tianwan Nuclear Power Station

    Institute of Scientific and Technical Information of China (English)

    毛志新

    2015-01-01

    The cultivation and development of nuclear safety culture in Tianwan Nuclear Power Station go through four stages: cognition, promotion, continuous improvement and commitment to excellence, establishing a Tianwan characteristic nuclear safety culture, which is carrying through traits of a healthy nuclear safety culture, building an image of the Tianwan people, insisting on zero tolerance, and strengthen the sense of responsibility. In addition, following PDCA circulation pattern, regular safety culture assessmentin nuclear power station is carried out, areas to be improved are identified, closed-loop control is achieved. After years of efforts, with the abstraction of the safety concept, safety culture mechanism and system construction, safety culture training and publicity, etc. In Tianwan nuclear power station, the station has obtained remarkable results, ensured excellence of nuclear safety culture, so that the level of nuclear safety and operating performance are improved.%田湾核电核安全文化建设经过了认知、提升、持续改进和追求卓越4个阶段,形成了"贯彻健康核安全文化特征,打造中核田湾人形象,坚持零容忍,强化责任心"的具有田湾特色的核安全文化.另外,做到遵循PDCA循环模式,评估活动常态化,定期对电站的核安全文化进行评估,找出待改进的领域,从而改进提升,达到闭环控制的目的.田湾核电站多年在安全理念提炼、安全文化制度和体系建设、安全文化培训和宣传等方面不断努力,保证卓越的核安全文化落地,从而提升核电站的核安全水平和运行业绩.

  8. Comparison of MELCOR modeling techniques and effects of vessel water injection on a low-pressure, short-term, station blackout at the Grand Gulf Nuclear Station

    Energy Technology Data Exchange (ETDEWEB)

    Carbajo, J.J.

    1995-06-01

    A fully qualified, best-estimate MELCOR deck has been prepared for the Grand Gulf Nuclear Station and has been run using MELCOR 1.8.3 (1.8 PN) for a low-pressure, short-term, station blackout severe accident. The same severe accident sequence has been run with the same MELCOR version for the same plant using the deck prepared during the NUREG-1150 study. A third run was also completed with the best-estimate deck but without the Lower Plenum Debris Bed (BH) Package to model the lower plenum. The results from the three runs have been compared, and substantial differences have been found. The timing of important events is shorter, and the calculated source terms are in most cases larger for the NUREG-1150 deck results. However, some of the source terms calculated by the NUREG-1150 deck are not conservative when compared to the best-estimate deck results. These results identified some deficiencies in the NUREG-1150 model of the Grand Gulf Nuclear Station. Injection recovery sequences have also been simulated by injecting water into the vessel after core relocation started. This marks the first use of the new BH Package of MELCOR to investigate the effects of water addition to a lower plenum debris bed. The calculated results indicate that vessel failure can be prevented by injecting water at a sufficiently early stage. No pressure spikes in the vessel were predicted during the water injection. The MELCOR code has proven to be a useful tool for severe accident management strategies.

  9. Analysis of fish diversion efficiency and survivorship in the fish return system at San Onofre Nuclear Generating Station

    OpenAIRE

    Love, Milton S.; Sandhu, Meenu; Stein, Jeffrey; Herbinson, Kevin T.; Moore, Robert H; Mullin, Michael; Stephens, John S.

    1989-01-01

    This study examined the efficiency of fish diversion and survivorship of diverted fishes in the San Onofre Nuclear Generating Station Fish Return System in 1984 and 1985. Generally, fishes were diverted back to the ocean with high frequency, particularly in 1984. Most species were diverted at rates of 80% or more. Over 90% of the most abundant species, Engraulis mordax, were diverted. The system worked particularly well for strong-swimming forms such as Paralobrax clothratus, Atherinopsis cal...

  10. Measurements of beta ray spectra in CANDU nuclear generating stations using a silicon detector coincidence telescope

    Energy Technology Data Exchange (ETDEWEB)

    Horowitz, Y.S.; Weizman, Y. [Ben-Gurion Univ. of the Negev, Beersheba (Israel). Dept. of Physics; Hirning, C.R. [Ontario Hydro, Whitby, ON (Canada). Health Physics Dept.

    1996-12-31

    The measurement of beta ray spectra at various work locations inside nuclear generating stations operated by Ontario Hydro is described. The measurements were carried out using an advanced coincidence telescope spectrometer using silicon detectors only. The spectrometer is capable of measuring electron energies over the range 60 keV- 2500 keV with close to 100% coincidence efficiency. Photon rejection is carried out by requiring a coincidence between either two or three silicon detectors. Monte Carlo calculations were then used to estimate beta correction factors for the LiF:Mg,Ti elements used in the Ontario Hydro thermoluminescence dosemeters. Averaging over all the measured beta correction factors for the `skin` chip (100 mg.cm{sup -2}) results in a value of 2.73 {+-} 0.77 and for the extremity dosemeter (240 mg.cm{sup -2}) an average value of 4.42 {+-} 1.17 is obtained. These values are 57% and 120% greater, respectively, than the current values used by Ontario Hydro. In addition, beta correction factors for nine representative spectra were calculated for 40 mg.cm{sup -2} chips and 20 mg.cm{sup -2} chips and the results demonstrate the benefits of decreased dosemeter thickness. The average value of the beta correction factor, as well as the spread in the beta correction factor, decreases dramatically from 4.8 {+-} 2.1 (240 mg.cm{sup -2}) to 1.29 ``1.2`` +-`` 0.1 (20 mg.cm{sup -2}). (author).

  11. Results of the first year of operation at Embalse Nuclear Power Station in Argentina

    Energy Technology Data Exchange (ETDEWEB)

    Bonino, A.; Pizarro, L.; Higa, Z. [Ente Nacional Regulador Nuclear, Buenos Aires (Argentina); Dupree, S.A.; Schoeneman, J.L. [Sandia National Labs., Albuquerque, NM (United States)

    1996-07-16

    As a part of the International Remote Monitoring Project, during March 1995, a Remote Monitoring System (RMS) was installed at the Embalse Nuclear Power Station in Embalse, Argentina. This system monitors the status of four typical Candu spent fuel dry storage silos. The monitoring equipment for each silo consists of analog sensors for temperature and gamma radiation measurement; digital sensors for motion detection; and electronic fiber-optic seals. The monitoring system for each silo is connected to a wireless Authenticate Item Monitoring System (AIMS). This paper describes the operation of the RMS during the first year of the trial and presents the results of the signals reported by the system compared with the on site inspections conducted by the regulatory bodies, ABACC, IAEA, ENREN. As an additional security feature, each sensor periodically transmits authenticated State-of-Health (SOH) messages. This feature provides assurance that all sensors are operational and have not been tampered with. The details of the transmitted information and the incidents of loss of SOH, referred to as Missing SOH Event, and the possible causes which produced the MSOHE are described. The RMS at the embalse facility uses gamma radiation detectors in a strong radiation field of spent fuel dry storage silos. The detectors are Geiger Muller tubes and Silicon solid state diodes. The study of the thermal drift of electronics in GM detectors and the possible radiation damage in silicon detectors is shown. Since the initial installation, the system has been successfully interrogated from Buenos Aires and Albuquerque. The experience gained, and the small changes made in the hardware in order to improve the performance of the system is presented.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1976-08-10

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

  13. 78 FR 45984 - Yankee Atomic Electric Company, Yankee Nuclear Power Station

    Science.gov (United States)

    2013-07-30

    ..., Project Manager, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission..., and part 50 of Title 10 of the Code of Federal Regulations (10 CFR), allows YAEC to possess and store..., Division of Spent Fuel Storage and Transportation, Office of Nuclear Material Safety and...

  14. 76 FR 48184 - Exelon Nuclear, Peach Bottom Atomic Power Station, Unit 1; Exemption From Certain Security...

    Science.gov (United States)

    2011-08-08

    ... a permanently shut down nuclear reactor facility. PBAPS Unit 1 was a high-temperature, gas-cooled... nuclear power reactors against radiological sabotage,'' paragraph (b)(1) states, ``The licensee shall... its objective to provide high assurance that activities involving special nuclear material are...

  15. Formation of a nuclear reactor's molten core bath in a crucible-type corium catcher for a nuclear power station equipped with VVER reactors

    Science.gov (United States)

    Beshta, S. V.; Vitol', S. A.; Granovskii, V. S.; Kalyago, E. K.; Kovtunova, S. V.; Krushinov, E. V.; Sulatskaya, M. B.; Sulatskii, A. A.; Khabenskii, V. B.; Al'Myashev, V. I.; Gusarov, V. V.

    2011-05-01

    Results from a calculation study on analyzing the formation of a melt bath in a crucible-type catcher for the conditions of a severe accident at a nuclear power station equipped with VVER-1000 reactors are presented. It is shown that the heat loads exerted on the water-cooled walls of the corium catcher shell are limited to a permissible level at which the necessary margins to nucleate boiling crisis and to destruction are ensured under the conditions of thermal and mechanical loading of the shell. An important role of sacrificial material in the efficient operation of the corium catcher is pointed out.

  16. How Space Radiation Risk from Galactic Cosmic Rays at the International Space Station Relates to Nuclear Cross Sections

    Science.gov (United States)

    Lin, Zi-Wei; Adams, J. H., Jr.

    2005-01-01

    Space radiation risk to astronauts is a major obstacle for long term human space explorations. Space radiation transport codes have thus been developed to evaluate radiation effects at the International Space Station (ISS) and in missions to the Moon or Mars. We study how nuclear fragmentation processes in such radiation transport affect predictions on the radiation risk from galactic cosmic rays. Taking into account effects of the geomagnetic field on the cosmic ray spectra, we investigate the effects of fragmentation cross sections at different energies on the radiation risk (represented by dose-equivalent) from galactic cosmic rays behind typical spacecraft materials. These results tell us how the radiation risk at the ISS is related to nuclear cross sections at different energies, and consequently how to most efficiently reduce the physical uncertainty in our predictions on the radiation risk at the ISS.

  17. Evaluation of environmental data relating to selected nuclear power plant sites. The Zion Nuclear Power Station site

    Energy Technology Data Exchange (ETDEWEB)

    Murarka, I.P.; Policastro, A.; Daniels, E.; Ferrante, J.; Vaslow, F.

    1976-11-01

    Environmental monitoring data for the years 1972 through 1975 pertaining to the Zion Station, which began commercial operation in 1974, were analyzed by the most practical qualitative and quantitative methods. Thermal plume, water chemistry and aquatic biota data were evaluated and the results are presented. The results showed no significant immediate deleterious effects, thus confirming preoperational predictions. Although the plant has not operated long enough to reveal long-term deleterious effects, the present indications do not lead to a concerned prediction that any are developing. The data utilized, the methods of analysis, and the results obtained are presented in detail, along with recommendations for improving monitoring techniques.

  18. Analysis of data from sensitive U.S. monitoring stations for the Fukushima Dai-ichi nuclear reactor accident.

    Science.gov (United States)

    Biegalski, S R; Bowyer, T W; Eslinger, P W; Friese, J A; Greenwood, L R; Haas, D A; Hayes, J C; Hoffman, I; Keillor, M; Miley, H S; Moring, M

    2012-12-01

    The March 11, 2011 9.0 magnitude undersea megathrust earthquake off the coast of Japan and subsequent tsunami waves triggered a major nuclear event at the Fukushima Dai-ichi nuclear power station. At the time of the event, units 1, 2, and 3 were operating and units 4, 5, and 6 were in a shutdown condition for maintenance. Loss of cooling capacity to the plants along with structural damage caused by the earthquake and tsunami resulted in a breach of the nuclear fuel integrity and release of radioactive fission products to the environment. Fission products started to arrive in the United States via atmospheric transport on March 15, 2011 and peaked by March 23, 2011. Atmospheric activity concentrations of (131)I reached levels of 3.0×10(-2) Bqm(-3) in Melbourne, FL. The noble gas (133)Xe reached atmospheric activity concentrations in Ashland, KS of 17 Bqm(-3). While these levels are not health concerns, they were well above the detection capability of the radionuclide monitoring systems within the International Monitoring System of the Comprehensive Nuclear-Test-Ban Treaty.

  19. Evaluation of the prompt alerting systems at four nuclear power stations

    Energy Technology Data Exchange (ETDEWEB)

    Towers, D.A.; Anderson, G.S.; Keast, D.N.; Kenoyer, J.L.; Desrosiers, A.E.

    1982-09-01

    This report presents evaluations of the prompt notification siren systems at the following four US nuclear power facilities: Trojan, Three Mile Island, Indian Point, and Zion. The objective of these evaluations was to provide examples of an analytical procedure for predicting siren-system effectiveness under specific conditions in the 10-mile emergency planning zone (EPZ) surrounding nuclear power plants. This analytical procedure is discussed in report No. PNL-4227.

  20. Aging of nuclear station diesel generators: Evaluation of operating and expert experience: Phase 1, Study

    Energy Technology Data Exchange (ETDEWEB)

    Hoopingarner, K.R.; Vause, J.W.; Dingee, D.A.; Nesbitt, J.F.

    1987-08-01

    Pacific Northwest Laboratory evaluated operational and expert experience pertaining to the aging degradation of diesel generators in nuclear service. The research, sponsored by the US Nuclear Regulatory Commission (NRC), identified and characterized the contribution of aging to emergency diesel generator failures. This report, Volume I, reviews diesel-generator experience to identify the systems and components most subject to aging degradation and isolates the major causes of failure that may affect future operational readiness. Evaluations show that as plants age, the percent of aging-related failures increases and failure modes change. A compilation is presented of recommended corrective actions for the failures identified. This study also includes a review of current, relevant industry programs, research, and standards. Volume II reports the results of an industry-wide workshop held on May 28 and 29, 1986 to discuss the technical issues associated with aging of nuclear service emergency diesel generators.

  1. 77 FR 50533 - Dominion Nuclear Connecticut, Inc.; Millstone Power Station, Unit 3

    Science.gov (United States)

    2012-08-21

    ... the ECCS for reactors that have fuel rods fabricated either with Zircaloy or ZIRLO\\TM\\. Appendix K to... systems for light-water nuclear power reactors,'' and Appendix K to 10 CFR Part 50, ``ECCS Evaluation Models,'' to allow the use of Optimized ZIRLO\\TM\\ fuel rod cladding in future core reload...

  2. 75 FR 52045 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Unit 3; Environmental...

    Science.gov (United States)

    2010-08-24

    ...- water nuclear power reactors,'' and 10 CFR part 50, appendix K, ``ECCS Evaluation Models,'' for Facility... Assessment Identification of the Proposed Action: The proposed action would permit the use of fuel rods with... exemption would allow up to eight lead fuel assemblies (LFAs) manufactured by Westinghouse with fuel...

  3. 77 FR 62539 - Dominion Nuclear Connecticut, Inc.; Millstone Power Station, Unit 2, Revocation of Exemption

    Science.gov (United States)

    2012-10-15

    ... Background Dominion Nuclear Connecticut, Inc., (DNC or the licensee) is the holder of Facility Operating... granted DNC's request. \\1\\ Agencywide Document Access and Management System (ADAMS) Accession No... circumstances were present. Therefore, the Commission granted DNC an exemption from the requirements of 10...

  4. 77 FR 39746 - Dominion Nuclear Connecticut, Inc. Millstone Power Station, Unit 2; Environmental Assessment and...

    Science.gov (United States)

    2012-07-05

    ...,'' for Facility Operating License No. DPR-65 issued to Dominion Nuclear Connecticut, Inc. (DNC or the.... Environmental Assessment Identification of the Proposed Action DNC proposed that the NRC grant exemptions to... certain requirements of 10 CFR part 50, appendix R, Section III.G.2. DNC proposed a number of OMAs in...

  5. 77 FR 12885 - Millstone Power Station, Units 1, 2 and 3, Dominion Nuclear Connecticut, Inc.; Exemption

    Science.gov (United States)

    2012-03-02

    ... Background Dominion Nuclear Connecticut, Inc. (DNC or the licensee) is the holder of Facility Operating... pursuant to 10 CFR 26.9, DNC, doing business as Dominion, requested an exemption from the requirements of... otherwise in the public interest. Therefore, the Commission hereby grants DNC an exemption from...

  6. 78 FR 77726 - Exelon Generation Company, LLC Three Mile Island Nuclear Station, Unit 1

    Science.gov (United States)

    2013-12-24

    ... facility is subject to all rules, regulations, and orders of the Nuclear Regulatory Commission (NRC) now or... facility is subject to all rules, regulations, and orders of the NRC now or hereafter in effect. The.../indexing reference temperatures. The licensee proposes to use ASME Code Case N-629 and the...

  7. Seismic structural fragility investigation for the San Onofre Nuclear Generating Station, Unit 1 (Project I); SONGS-1 AFWS Project

    Energy Technology Data Exchange (ETDEWEB)

    Wesley, D.A.; Hashimoto, P.S.

    1982-04-01

    An evaluation of the seismic capacities of several of the San Onofre Nuclear Generating Station, Unit 1 (SONGS-1) structures was conducted to determine input to the overall probabilistic methodology developed by Lawrence Livermore National Laboratory. Seismic structural fragilities to be used as input consist of median seismic capacities and their variabilities due to randomness and uncertainty. Potential failure modes were identified for each of the SONGS-1 structures included in this study by establishing the seismic load-paths and comparing expected load distributions to available capacities for the elements of each load-path. Particular attention was given to possible weak links and details. The more likely failure modes were screened for more detailed investigation.

  8. Nuclear anomalies in exfoliated buccal epithelial cells of petrol station attendants in Udaipur, Rajasthan

    Directory of Open Access Journals (Sweden)

    Rashmi Metgud

    2015-01-01

    Full Text Available Aim: The petroleum derivatives consist of a complex mixture of chemical compounds one among which is benzene. Petrol station workers who pump fuel to vehicles absorb the products of fuel fumes and the products of combustion. Materials and Methods: To study the occupational exposure to petroleum derivatives such as benzene, exfoliated buccal cells from 40 petrol station attendants and 40 age-matched control subjects were examined for micronuclei, binucleation, karyorrhexis and karyolysis frequency by using feulgen and Giemsa stains. Statistical evaluation was performed with ANOVA test. Results: In the present study, inter-comparison of mean values for micronuclei, binucleation, karyorrhexis and karyolysis using Fuelgen stain between smokers of study and control group, as well as between smokers and non-smokers of study and control group revealed statistically highly significant results with P value 0.00002 and 0.0001 respectively. Whereas inter comparison between non-smokers of study and control group using Feulgen stain and inter comparison between smokers of study and control group, using Giemsa stain revealed statistically significant results with P value 0.0034 and 0.0004, respectively. Conclusion: This study revealed that the studied individuals belong to a risk group and should periodically undergo biological monitoring and proper care.

  9. Groundwater Monitoring Strategy for Nuclear Power Station of American Nuclear Regulatory Commission and Its Implications%美国核电厂地下水监控技术路线及借鉴

    Institute of Scientific and Technical Information of China (English)

    覃春丽; 徐月平; 陈超峰; 上官志洪

    2014-01-01

    In this paper ,NRC’ s groundwater monitoring strategy for nuclear power station is summarized . This strategy combines model development with site monitoring and has been well validated ,Meanwhile ,cur-rent situation of groundwater monitoring at nuclear power station in our country is schematically reported in or-der to provide references to establish and perfect groundwater monitoring at China ’s nuclear power stations .%介绍了美国核管理委员会对核电厂的地下水监控技术路线。该技术路线将数学模型与现场监测相结合,并得到良好的实践验证。简要分析了我国核电厂地下水监控的现状。

  10. [Discirculatory encephalopathy in liquidators of the Chernobyl nuclear power station: a twenty-year study].

    Science.gov (United States)

    Podsonnaia, I V; Shumakher, G I; Golovin, V A

    2009-01-01

    A comparative twenty-year study of 536 liquidators of the Chernobyl nuclear disaster and 436 patients without radiation anamnesis has been carried out. Discirculatory encephalopathy (DE) was more often developed in subjects exposed to radiation at the age 30 years. Compared to individuals from the general population, it is characterized by the earlier onset, malignant progression, rapid increase of signs of cerebral affection during the first two years after exposure to radiation, stability of clinical symptoms during the following 5-6 years and further progressive cerebral decompensation with early autonomic dysfunction, psychoorganic syndrome, epilepsy. Moreover, severe stroke is a common complication of DE in liquidators.

  11. Comparison and evaluation of nuclear power plant options for geosynchronous power stations

    Science.gov (United States)

    Williams, J. R.

    1975-01-01

    The suitability of eleven types of nuclear fission reactors in combination with five potential energy conversion systems for use in geosynchronous power plants is evaluated. Gas turbine, potassium Rankine liquid metal MHD, and thermionic energy conversion systems are considered. The existing technology of reactors in near-term, intermediate-term, and long-term classes is discussed, together with modifications for use in large-scale power production in space. Unless the temperature is high enough for MHD, reactors which heat gases are generally more suitable for use with gas turbines. Those which heat liquid metals will be more useful for potassium Rankine or liquid metal MHD conversion systems.

  12. The accident at TEPCO's Fukushima-Daiichi Nuclear Power Station: What went wrong and what lessons are universal?

    Science.gov (United States)

    Omoto, Akira

    2013-12-01

    After a short summary of the nuclear accident at the Fukushima Daiichi Nuclear Power Station, this paper discusses “what went wrong” by illustrating the problems of the specific layers of defense-in-depth (basic strategy for assuring nuclear safety) and “what lessons are universal.” Breaches in the multiple layers of defense were particularly significant in respective protection (a) against natural disasters (first layer of defense) as well as (b) against severe conditions, specifically in this case, a complete loss of AC/DC power and isolation from the primary heat sink (fourth layer of defense). Confusion in crisis management by the government and insufficient implementation of offsite emergency plans revealed problems in the fifth layer of defense. By taking into consideration managerial and safety culture that might have relevance to this accident, in the author's view, universal lessons are as follows: Resilience: the need to enhance organizational capabilities to respond, monitor, anticipate, and learn in changing conditions, especially to prepare for the unexpected. This includes increasing distance to cliff edge by knowing where it exists and how to increase safety margin. Responsibility: the operator is primarily responsible for safety, and the government is responsible for protecting public health and environment. For both, their right decisions are supported by competence, knowledge, and an understanding of the technology, as well as humble attitudes toward the limitations of what we know and what we can learn from others. Social license to operate: the need to avoid, as much as possible regardless of its probability of occurrence, the reasonably anticipated environmental impact (such as land contamination), as well as to build public confidence/trust and a renewed liability scheme.

  13. "Life without nuclear power": A nuclear plant retirement formulation model and guide based on economics. San Onofre Nuclear Generating Station case: Economic impacts and reliability considerations leading to plant retirement

    Science.gov (United States)

    Wasko, Frank

    Traditionally, electric utilities have been slow to change and very bureaucratic in nature. This culture, in and of itself, has now contributed to a high percentage of United States electric utilities operating uneconomical nuclear plants (Crooks, 2014). The economic picture behind owning and operating United States nuclear plants is less than favorable for many reasons including rising fuel, capital and operating costs (EUCG, 2012). This doctoral dissertation is specifically focused on life without nuclear power. The purpose of this dissertation is to create a model and guide that will provide electric utilities who currently operate or will operate uneconomical nuclear plants the opportunity to economically assess whether or not their nuclear plant should be retired. This economic assessment and stakeholder analysis will provide local government, academia and communities the opportunity to understand how Southern California Edison (SCE) embraced system upgrade import and "voltage support" opportunities to replace "base load" generation from San Onofre Nuclear Generating Station (SONGS) versus building new replacement generation facilities. This model and guide will help eliminate the need to build large replacement generation units as demonstrated in the SONGS case analysis. The application of The Nuclear Power Retirement Model and Guide will provide electric utilities with economic assessment parameters and an evaluation assessment progression needed to better evaluate when an uneconomical nuclear plant should be retired. It will provide electric utilities the opportunity to utilize sound policy, planning and development skill sets when making this difficult decision. There are currently 62 nuclear power plants (with 100 nuclear reactors) operating in the United States (EIA, 2014). From this group, 38 are at risk of early retirement based on the work of Cooper (2013). As demonstrated in my model, 35 of the 38 nuclear power plants qualify to move to the economic

  14. Organohalogen products from chlorination of cooling water at nuclear power stations

    Energy Technology Data Exchange (ETDEWEB)

    Bean, R.M.

    1983-10-01

    Eight nuclear power units at seven locations in the US were studied to determine the effects of chlorine, added as a biocide, on the composition of cooling water discharge. Water, sediment and biota samples from the sites were analyzed for total organic halogen and for a variety of organohalogen compounds. Haloforms were discharged from all plants studied, at concentrations of a few ..mu..g/L (parts-per-billion). Evidence was obtained that power plants with cooling towers discharge a significant portion of the haloforms formed during chlorination to the atmosphere. A complex mixture of halogenated phenols was found in the cooling water discharges of the power units. Cooling towers can act to concentrate halogenated phenols to levels approaching those of the haloforms. Examination of samples by capillary gas chromatography/mass spectrometry did not result in identification of any significant concentrations of lipophilic base-neutral compounds that could be shown to be formed by the chlorination process. Total concentrations of lipophilic (Bioabsorbable) and volatile organohalogen material discharged ranged from about 2 to 4 ..mu..g/L. Analysis of sediment samples for organohalogen material suggests that certain chlorination products may accumulate in sediments, although no tissue bioaccumulation could be demonstrated from analysis of a limited number of samples. 58 references, 25 figures, 31 tables.

  15. MEASUREMENTS OF THE CONFINEMENT LEAKTIGHTNESS AT THE KOLA NUCLEAR POWER STATION (UNIT 2) IN RUSSIA

    Energy Technology Data Exchange (ETDEWEB)

    GREENE,G.A.; GUPPY,J.G.

    1998-08-01

    This is the final report on the INSP project entitled, ``Kola Confinement Leaktightness'' conducted by BNL under the authorization of Project Work Plan WBS 1.2.2.1. This project was initiated in February 1993 to assist the Russians to reduce risks associated with the continued operation of older Soviet-designed nuclear power plants, specifically the Kola VVER-440/230 Units 1 and 2, through upgrades in the confinement performance to reduce the uncontrolled leakage rate. The major technical objective of this-project was to improve the leaktightness of the Kola NPP VVER confinement boundaries, through the application of a variety of sealants to penetrations, doors and hatches, seams and surfaces, to the extent that current technology permitted. A related objective was the transfer, through training of Russian staff, of the materials application procedures to the staff of the Kola NPP. This project was part of an overall approach to minimizing uncontrolled releases from the Kola NPP VVER440/230s in the event of a serious accident, and to thereby significantly mitigate the consequences of such an accident. The US provided materials, application technology, and applications equipment for application of sealant materials, surface coatings, potting materials and gaskets, to improve the confinement leaktightness of the Kola VVER-440/23Os. The US provided for training of Russian personnel in the applications technology.

  16. Investigating the knowledge and preparedness of proximal residents to a general-emergency event at the Koeberg Nuclear Power Station

    Directory of Open Access Journals (Sweden)

    Alberto P. Francioli

    2016-01-01

    Full Text Available Ward 23 in the City of Cape Town South Africa is situated within 16 km of Koeberg Nuclear Power Station (KNPS. Massive investments were made to provide the 13 800 residents of Ward 23 with information on emergency preparedness and evacuation procedures in case of a general-emergency event at KNPS. However, it is not known whether these efforts to inform and prepare the proximal residents for a general emergency have been effective or not. The objective of this study was to investigate the level of knowledge of and preparedness for an emergency exhibited by residents of Ward 23. Data was collected through the distribution of semi-structured questionnaires to 204 residents at the study site to ascertain their views on the provision and accessibility of emergency information and to find out whether they utilised this information to prepare themselves. The results revealed that the majority of interviewed residents had very poor knowledge concerning emergency procedures, and few had made any effort to prepare themselves. The majority of better-informed and prepared residents tended to reside closer to KNPS. The poor levels of knowledge and preparedness are attributed to residents’ lack of awareness concerning the availability of information, misconceptions regarding a nuclear hazard and a general emergency event or a lack of incentive to inform themselves due to a perceived high sense of security and the improbability of such an event occurring. To improve resident knowledge and preparedness, efforts should be made to advertise the availability and importance of such emergency information and enhance incentives for residents to inform themselves.

  17. Source Term Analysis for the Nuclear Power Station Goesgen-Daeniken; Quelltermanalysen fuer das Kernkraftwerk Goesgen-Daeniken

    Energy Technology Data Exchange (ETDEWEB)

    Hosemann, J.P.; Megaritis, G.; Guentay, S.; Hirschmann, H.; Luebbesmeyer, D.; Lieber, K.; Jaeckel, B.; Birchley, J.; Duijvestijn, G

    2001-08-01

    Analyses are performed for three accident scenarios postulated to occur in the Goesgen Nuclear Power Plant, a 900 MWe Pressurised Water Reactor of Siemens design. The scenarios investigated comprise a Station Blackout and two separate cases of small break loss-of-coolant accident which lead, respectively, to high, intermediate and low pressure conditions in the reactor system. In each case the accident assumptions are highly pessimistic, so that the sequences span a large range of plant states and a damage phenomena. Thus the plant is evaluated for a diversity of potential safety challenges. A suite of analysis tools are used to examine the reactor coolant system response, the core heat-up, melting, fission product release from the reactor system, the transport and chemical behaviour of those fission products in the containment building, and the release of radioactivity (source term) to the environment. Comparison with reference values used by the licensing authority shows that the use of modern analysis tools and current knowledge can provide substantial reduction in the estimated source term. Of particular interest are insights gained from the analyses which indicate opportunities for operators to reduce or forestall the release. (author)

  18. Recommendations on selecting the closing relations for calculating friction pressure drop in the loops of nuclear power stations equipped with VVER reactors

    Science.gov (United States)

    Alipchenkov, V. M.; Belikov, V. V.; Davydov, A. V.; Emel'yanov, D. A.; Mosunova, N. A.

    2013-05-01

    Closing relations describing friction pressure drop during the motion of two-phase flows that are widely applied in thermal-hydraulic codes and in calculations of the parameters characterizing the flow of water coolant in the loops of reactor installations used at nuclear power stations and in other thermal power systems are reviewed. A new formula developed by the authors of this paper is proposed. The above-mentioned relations are implemented in the HYDRA-IBRAE thermal-hydraulic computation code developed at the Nuclear Safety Institute of the Russian Academy of Sciences. A series of verification calculations is carried out for a wide range of pressures, flowrates, and heat fluxes typical for transient and emergency operating conditions of nuclear power stations equipped with VVER reactors. Advantages and shortcomings of different closing relations are revealed, and recommendations for using them in carrying out thermal-hydraulic calculations of coolant flow in the loops of VVER-based nuclear power stations are given.

  19. Evaluation of the Submerged Demineralizer System (SDS) flowsheet for decontamination of high-activity-level water at the Three Mile Island Unit 2 Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Campbell, D. O.; Collins, E. D.; King, L. J.; Knauer, J. B.

    1980-07-01

    This report discusses the Submerged Demineralizer System (SDS) flowsheet for decontamination of the high-activity-level water at the Three Mile Island Unit 2 Nuclear Power Station was evaluated at Oak Ridge National Laboratory in a study that included filtration tests, ion exchange column tests, and ion exchange distribution tests. The contaminated waters, the SDS flowsheet, and the experiments made are described. The experimental results were used to predict the SDS performance and to indicate potential improvements.

  20. 芜湖建设核电站可行性分析%On the Feasibility of Wuhu Nuclear Power Station

    Institute of Scientific and Technical Information of China (English)

    杨莹

    2013-01-01

      核电是一种清洁、安全、潜在价值高的新能源,升值空间大同时风险成本也较高。通过对芜湖核电站建设工程的选址条件考察、预期效益估计、风险分析,得出以下结论:芜湖符合核电站选址标准;核电站工程符合芜湖长期发展战略,为芜湖带来的预期效益高于预期风险;针对核电站的风险存在,应通过加强管理、改良技术、增强意识、严格监测等方式降低风险成本。%Nuclear power is a new , clean and safe energy source with high potential value , which has large value -added room , and high risk cost at the same time.By investigating the location ,estimating the expected benefits and analyzing the risks of Wuhu nuclear power station , it is concluded that the siting criteria of nuclear power station is in accord with the long-term development strategy in Wuhu ,and brings Wuhu expected benefits over expected risk .Considering the risks that exists in nuclear power station, it is necessary for us to reduce the risk cost by enhancing management , improving technology adopted , strengthening the regulation of the power station .operation.

  1. Improved sampling and analytical techniques for characterization of very-low-level radwaste materials from commercial nuclear power stations

    Energy Technology Data Exchange (ETDEWEB)

    Robertson, D.E. [Pacific Northwest Labs., Richland, WA (United States); Robinson, P.J. [Electric Power Research Inst., Palo Alto, CA (United States)

    1989-11-01

    This paper summarizes the unique sampling methods that were utilized in a recently completed project sponsored by the Electric Power Research Institute (EPRI) to perform accurate and precise radiological characterizations of several very-low-level radwaste materials from commercial nuclear power stations. The waste types characterized during this project included dry active waste (DAW), oil, secondary-side ion exchange resin, and soil. Special precautions were taken to insure representative sampling of the DAW. This involved the initial direct, quantitative gamma spectrometric analyses of bulk quantities (208-liter drums) of DAW utilizing a specially constructed barrel scanner employing a collimated intrinsic germanium detector assembly. Subsamples of the DAW for destructive radiochemical analyses of the difficult-to-measure 10CF61 radionuclides were then selected which had the same isotopic composition (to within {+-}25%) as that measured for the entire drum of DAW. The techniques for accomplishing this sampling are described. Oil samples were collected from the top, middle and bottom sections of 208-liter drums for radiochemical analyses. These samples were composited to represent the entire drum of oil. The accuracy of this type of sampling was evaluated by comparisons with direct, quantitative assays of a number of the drums using the barrel scanning gamma-ray spectrometer. The accuracy of sampling drums of spent secondary-side ion exchange resin was evaluated by comparing the radionuclide contents of grab samples taken from the tops of the drums with direct assays performed with the barrel scanner. The results of these sampling evaluations indicated that the sampling methods used were generally adequate for providing a reasonably representative subsample from bulk quantities of DAW, oil, and resin. The study also identified a number of potential pitfalls, in sampling of these materials.

  2. Sorption (Kd) measurements on cinder block and grout in support of dose assessments for Zion Nuclear Station decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Milian L.; Sullivan T.

    2014-06-24

    The Zion Nuclear Power Station is being decommissioned. ZionSolutions proposes to leave much of the below grade structures in place and to fill them with a backfill to provide structural support. Backfills under consideration include “clean” concrete demolition debris from the above grade parts of the facility, a flowable grout, cinder block construction debris and sand. A previous study (Yim, 2012) examined the sorption behavior of five nuclides (Fe-55, Co-60, Ni-63, Sr-85, and Cs-137) on concrete and local soils. This study, commissioned by ZionSolutions and conducted by the Brookhaven National Laboratory (BNL) examines the sorption behavior on cinder block and grout materials. Specifically, this study measured the distribution coefficient for four radionuclides of concern using site-groundwater and cinder block from the Zion site and a flowable grout. The distributions coefficient is a measure of the amount of the radionuclide that will remain sorbed to the solid material that is present relative to the amount that will remain in solution. A high distribution coefficient indicates most of the radionuclide will remain on the solid material and will not be available for transport by the groundwater. The radionuclides examined in this set of tests were Co-60, Ni-63, Sr-85, and Cs-137. Tests were performed following ASTM C1733-10, Standard Test Methods for Distribution Coefficients of Inorganic Species by the Batch Method. Sr-85 was used in the testing as an analogue for Sr-90 because it behaves similarly with respect to sorption and has a gamma emission that is easier to detect than the beta emission from Sr-90.

  3. Activities of radionuclides in the Pacific coastal area of Fukushima since the TEPCO Fukushima Daiichi Nuclear Power Station accident - Activities of radionuclides in the coast area off Fukushima after TEPCO's Fukushima Daiichi Nuclear Power Station accident

    Energy Technology Data Exchange (ETDEWEB)

    Aono, Tatsuo; Fukuda, Miho; Yoshida, Satoshi [National Institute of Radiological Sciences, 263-8555, Chiba (Japan); Sohtome, Tadahiro; Mizuno, Takuji [Fukushima Prefecture Fisheries Experimental Station, 970-0316, Fukushima (Japan); Igarashi, Satoshi [Fukushima Prefecture Fisheries Experimental Station, 970-0316, Fukushima (Japan); Fukushima Prefecture Sea-Farming Association, 970-8044, Fukushima (Japan); Ito, Yukari; Kanda, Jota; Ishimaru, Takashi [Tokyo University of Marine Science and Technology, 108-0075, Tokyo (Japan)

    2014-07-01

    The accident of TEPCO's Fukushima Daiichi Nuclear Power Station (FDNPS) has caused the release of the huge quantities of radionuclide by the 2011 Great East Japan Earthquake and Tsunami, and then the serious problems gave rise to pollution in marine environment widely in the coast area off Fukushima. Monitoring of radioactivity in seawater and biota are important for understanding the dispersion of radionuclides and the effects of radioecology in the marine environment around the coast of Fukushima and the Pacific. The activities of Cs-134 and Cs-137 in seawater decreased exponentially and then were almost same levels before the accident around off Fukushima after about three years from the accident. However, the high activities of radio caesium (Cs) have been monitored in marine biota off Fukushima. The aims of the present study were to examine the temporal changes in radioactivity and to clarify the variation factor and the effect of radioecology in marine biota. Cs-134 and Cs-137, and Ag-110m, were released by this accident, determined in biota sample such as the plankton, fish and benthos, although it is well-known that molluscs and crustaceans concentrate silver in visceral parts. However, Sr-90 was not detected and the activities of plutonium were almost same level before this accident in the marine biota around off Fukushima. Concentration ratios of Cs (CR-Cs) in marine organism were from 2.6 E+1 in the muscle part of squid to 1.0 E+4 in the viscera of clam. The large differences in CR-Cs by the parts of marine organism were not observed. It is suggested that rapid change in the activities of radio Cs and silver in seawater, resuspension of particles from sediments and food chain effects led to high radionuclide activities in marine biota after this accident. CR-Cs in plankton was also calculated with the activities in seawater, which were collected around sampling area during this monitoring period. These resulting values ranged from 5.8 E+1 to 7.8 E+2

  4. International challenge to predict the impact of radioxenon releases from medical isotope production on a comprehensive nuclear test ban treaty sampling station

    Energy Technology Data Exchange (ETDEWEB)

    Eslinger, Paul W.; Bowyer, Ted W.; Achim, Pascal; Chai, Tianfeng; Deconninck, Benoit; Freeman, Katie; Generoso, Sylvia; Hayes, Philip; Heidmann, Verena; Hoffman, Ian; Kijima, Yuichi; Krysta, Monika; Malo, Alain; Maurer, Christian; Ngan, Fantine; Robins, Peter; Ross, J. Ole; Saunier, Olivier; Schlosser, Clemens; Schöppner, Michael; Schrom, Brian T.; Seibert, Petra; Stein, Ariel F.; Ungar, Kurt; Yi, Jing

    2016-06-01

    Abstract The International Monitoring System (IMS) is part of the verification regime for the Comprehensive Nuclear-Test-Ban-Treaty Organization (CTBTO). At entry-into-force, half of the 80 radionuclide stations will be able to measure concentrations of several radioactive xenon isotopes produced in nuclear explosions, and then the full network may be populated with xenon monitoring afterward (Bowyer et al., 2013). Fission-based production of 99Mo for medical purposes also releases radioxenon isotopes to the atmosphere (Saey, 2009). One of the ways to mitigate the effect of emissions from medical isotope production is the use of stack monitoring data, if it were available, so that the effect of radioactive xenon emissions could be subtracted from the effect from a presumed nuclear explosion, when detected at an IMS station location. To date, no studies have addressed the impacts the time resolution or data accuracy of stack monitoring data have on predicted concentrations at an IMS station location. Recently, participants from seven nations used atmospheric transport modeling to predict the time-history of 133Xe concentration measurements at an IMS station in Germany using stack monitoring data from a medical isotope production facility in Belgium. Participants received only stack monitoring data and used the atmospheric transport model and meteorological data of their choice. Some of the models predicted the highest measured concentrations quite well (a high composite statistical model comparison rank or a small mean square error with the measured values). The results suggest release data on a 15 min time spacing is best. The model comparison rank and ensemble analysis suggests that combining multiple models may provide more accurate predicted concentrations than any single model. Further research is needed to identify optimal methods for selecting ensemble members and those methods may depend on the specific transport problem. None of the submissions based only

  5. The risk of leukaemia in young children from exposure to tritium and carbon-14 in the discharges of German nuclear power stations and in the fallout from atmospheric nuclear weapons testing.

    Science.gov (United States)

    Wakeford, Richard

    2014-05-01

    Towards the end of 2007, the results were published from a case-control study (the "KiKK Study") of cancer in young children, diagnosed nuclear power stations in western Germany. The study found a tendency for cases of leukaemia to live closer to the nearest nuclear power station than their matched controls, producing an odds ratio that was raised to a statistically significant extent for residence within 5 km of a nuclear power station. The findings of the study received much publicity, but a detailed radiological risk assessment demonstrated that the radiation doses received by young children from discharges of radioactive material from the nuclear reactors were much lower than those received from natural background radiation and far too small to be responsible for the statistical association reported in the KiKK Study. This has led to speculation that conventional radiological risk assessments have grossly underestimated the risk of leukaemia in young children posed by exposure to man-made radionuclides, and particular attention has been drawn to the possible role of tritium and carbon-14 discharges in this supposedly severe underestimation of risk. Both (3)H and (14)C are generated naturally in the upper atmosphere, and substantial increases in these radionuclides in the environment occurred as a result of their production by atmospheric testing of nuclear weapons during the late 1950s and early 1960s. If the leukaemogenic effect of these radionuclides has been seriously underestimated to the degree necessary to explain the KiKK Study findings, then a pronounced increase in the worldwide incidence of leukaemia among young children should have followed the notably elevated exposure to (3)H and (14)C from nuclear weapons testing fallout. To investigate this hypothesis, the time series of incidence rates of leukaemia among young children risk of leukaemia in young children following the peak of above-ground nuclear weapons testing, or that incidence rates are

  6. Short-term pressure and temperature MSLB response analyses for large dry containment of the Maanshan nuclear power station

    Energy Technology Data Exchange (ETDEWEB)

    Dai, Liang-Che, E-mail: lcdai@iner.gov.tw; Chen, Yen-Shu; Yuann, Yng-Ruey

    2014-12-15

    Highlights: • The GOTHIC code is used for the PWR dry containment pressure and temperature analysis. • Boundary conditions are hot standby and 102% power main steam line break accidents. • Containment pressure and temperature responses of GOTHIC are similar with FSAR. • The capability of the developed model to perform licensing calculation is assessed. - Abstract: Units 1 and 2 of the Maanshan nuclear power station are the typical Westinghouse three-loop PWR (pressurized water reactor) with large dry containments. In this study, the containment analysis program GOTHIC is adopted for the dry containment pressure and temperature analysis. Free air space and sump of the PWR dry containment are individually modeled as control volumes. The containment spray system and fan cooler unit are also considered in the GOTHIC model. The blowdown mass and energy data of the main steam line break (hot standby condition and various reactor thermal power levels) are tabulated in the Maanshan Final Safety Analysis Report (FSAR) 6.2 which could be used as the boundary conditions for the containment model. The calculated containment pressure and temperature behaviors of the selected cases are in good agreement with the FSAR results. In this study, hot standby and 102% reactor thermal power main steam line break accidents are selected. The calculated peak containment pressure is 323.50 kPag (46.92 psig) for hot standby MSLB, which is a little higher than the FSAR value of 311.92 kPag (45.24 psig). But it is still below the design value of 413.69 kPag (60 psig). The calculated peak vapor temperature inside the containment is 187.0 °C (368.59 F) for 102% reactor thermal power MSLB, which is lower than the FSAR result of 194.42 °C (381.95 F). The effects of the containment spray system and fan cooler units could be clearly observed in the GOTHIC analysis. The calculated containment pressure and temperature behaviors of the selected cases are in good agreement with the FSAR

  7. Fossil-fuelled and nuclear power stations. Pt. 2; Strom- und waermeerzeugende Anlagen auf fossiler und nuklearer Grundlage. T. 2

    Energy Technology Data Exchange (ETDEWEB)

    Wehowsky, P. [Siemens AG Unternehmensbereich KWU, Erlangen (Germany). Abt. 9414; Leidemann, W. [Siemens AG Unternehmensbereich KWU, Erlangen (Germany). Abt. 9414; Lezuo, A. [Siemens AG Unternehmensbereich KWU, Erlangen (Germany). Abt. 9414; Seifritz, W.; Fischedick, M. [Stuttgart Univ. (Germany). Inst. fuer Energiewirtschaft und Rationelle Energieanwendung (IER); Herrmann, D. [Stuttgart Univ. (Germany). Inst. fuer Energiewirtschaft und Rationelle Energieanwendung (IER); Pfeifer, T. [Stuttgart Univ. (Germany). Inst. fuer Energiewirtschaft und Rationelle Energieanwendung (IER); Fahl, U. [Stuttgart Univ. (Germany). Inst. fuer Energiewirtschaft und Rationelle Energieanwendung (IER); Voss, A. [Stuttgart Univ. (Germany). Inst. fuer Energiewirtschaft und Rationelle Energieanwendung (IER); Barnert, H. [Forschungszentrum Juelich GmbH (Germany). Inst. fuer Sicherheitsforschung und Reaktortechnik; Singh, J. [Forschungszentrum Juelich GmbH (Germany). Inst. fuer Sicherheitsforschung und Reaktortechnik

    1994-12-01

    This report contains technical descriptions of systems for electric power and/or heat supply. The data sheets for industrial-scale fossil and nuclear power plants were mainly provided by Siemens AG/KWU. IER Stuttgart supplied the text describing the status and prospects of electric power and heat generation technology as well as the data sheets for small-scale CHP systems. The data sheets for HTR reactors were provided by the Institut fuer Sicherheitsforschung und Reaktortechnik (ISR) of Forschungszentrum Juelich, while the data sheets for nuclear heating stations and revolutionary new reactor concepts were obtained from Prof. W. Seifritz, Windisch (CH). Electric power supply and district heating is a central issue in the future development of the electric power industry, owing to the fact that the generated end use energy sources are emission-free and suited for a wide range of applications and will be used to an increasing extent in the future. High-efficiency centralized conversion systems offer a good chance of reducing specific fuel consumption and conversion-related emissions by means of technical measures. Finally, the desired end use energy sources can be generated from highly different fuels and primary energy sources which differ considerably with regard to their cost, range, and specific emissions. This means that a step-by-step modification of the primary energy base will not only be an important contribution to economic efficiency and reliability of supply but will also provide good options for achieving emission-free energy supply. (orig./KOW) [Deutsch] Der vorliegende Bericht 4.06 enthaelt Technikbeschreibungen von Anlagen zur Elektroenergie- und/oder Waermeerzeugung. Die Datenblaetter zu fossilen und nuklearen Anlagen grosser Leistung wurden ueberwiegend durch die Siemens AG/KWU erarbeitet. Vom IER Stuttgart stammen die vorangestellte textliche Beschreibung zu Stand und Entwicklungsperspektiven der Elektroenergie- und Waermeerzeugungstechnik sowie

  8. Fossil-fuelled and nuclear power stations. Pt. 1; Strom- und waermeerzeugende Anlagen auf fossiler und nuklearer Grundlage. T. 1

    Energy Technology Data Exchange (ETDEWEB)

    Wehovsky, P [Siemens AG Unternehmensbereich KWU, Erlangen (Germany). Abt. 9414; Leidemann, W. [Siemens AG Unternehmensbereich KWU, Erlangen (Germany). Abt. 9414; Lezuo, A. [Siemens AG Unternehmensbereich KWU, Erlangen (Germany). Abt. 9414; Seifritz, W.; Fischedick, M. [Stuttgart Univ. (Germany). Inst. fuer Energiewirtschaft und Rationelle Energieanwendung (IER); Herrmann, D. [Stuttgart Univ. (Germany). Inst. fuer Energiewirtschaft und Rationelle Energieanwendung (IER); Pfeifer, T. [Stuttgart Univ. (Germany). Inst. fuer Energiewirtschaft und Rationelle Energieanwendung (IER); Fahl, U. [Stuttgart Univ. (Germany). Inst. fuer Energiewirtschaft und Rationelle Energieanwendung (IER); Voss, A. [Stuttgart Univ. (Germany). Inst. fuer Energiewirtschaft und Rationelle Energieanwendung (IER); Barnert, H. [Forschungszentrum Juelich GmbH (Germany). Inst. fuer Sicherheitsforschung und Reaktortechnik; Singh, J. [Stuttgart Univ. (Germany). Inst. fuer Energiewirtschaft und Rationelle Energieanwendung (IER)

    1994-12-01

    This report contains technical descriptions of systems for electric power and/or heat supply. The data sheets for industrial-scale fossil and nuclear power plants were mainly provided by Siemens AG/KWU. IER Stuttgart supplied the text describing the status and prospects of electric power and heat generation technology as well as the data sheets for small-scale CHP systems. The data sheets for HTR reactors were provided by the Institut fuer Sicherheitsforschung und Reaktortechnik (ISR) of Forschungszentrum Juelich, while the data sheets for nuclear heating stations and revolutionary new reactor concepts were obtained from Prof. W. Seifritz, Windisch (CH). Electric power supply and district heating is a central issue in the future development of the electric power industry, owing to the fact that the generated end use energy sources are emission-free and suited for a wide range of applications and will be used to an increasing extent in the future. High-efficiency centralized conversion systems offer a good chance of reducing specific fuel consumption and conversion-related emissions by means of technical measures. Finally, the desired end use energy sources can be generated from highly different fuels and primary energy sources which differ considerably with regard to their cost, range, and specific emissions. This means that a step-by-step modification of the primary energy base will not only be an important contribution to economic efficiency and reliability of supply but will also provide good options for achieving emission-free energy supply. (orig./KOW) [Deutsch] Der vorliegende Bericht 4.06 enthaelt Technikbeschreibungen von Anlagen zur Elektroenergie- und/oder Waermeerzeugung. Die Datenblaetter zu fossilen und nuklearen Anlagen grosser Leistung wurden ueberwiegend durch die Siemens AG/KWU erarbeitet. Vom IER Stuttgart stammen die vorangestellte textliche Beschreibung zu Stand und Entwicklungsperspektiven der Elektroenergie- und Waermeerzeugungstechnik sowie

  9. 压水堆核电站核三级屏蔽电泵试验鉴定程序%Testing of Nuclear Three-stage Shielded Electric Pump for Pressurized Water Reactor Nuclear Power Station

    Institute of Scientific and Technical Information of China (English)

    李作维; 孙悦; 薄大威

    2015-01-01

    This paper analyzes the necessity of obtaining the design/manufacture license of three generation nuclear power plants with two generation of pressurized water reactor nuclear power plant. Describe the function and structure of the three stage pump. Especially introduce the program and test method of the two generation of nuclear power station in three gener-ation pressurized water reactor nuclear power station.%分析了二代加压水堆核电站核三级屏蔽电泵取得民用核安全设备 (屏蔽泵) 设计/制造许可证的必要性, 对核三级屏蔽电泵的功能、 规格及结构进行了详细的阐述, 并重点针对二代加压水堆核电站核三级屏蔽电泵试验鉴定的程序及试验方法进行了介绍, 为核三级屏蔽电泵鉴定提供了依据.

  10. 75 FR 8149 - Arizona Public Service Company, et al. Palo Verde Nuclear Generating Station, Units 1, 2, and 3...

    Science.gov (United States)

    2010-02-23

    ... species. No impacts are expected to historic and cultural resources, or to socioeconomic resources... Nuclear Regulatory Commission. James R. Hall, Senior Project Manager, Plant Licensing Branch IV,...

  11. Design optimization of the Laguna Verde nuclear power station fuel recharge; Optimacion del diseno de recargas de combustible para la Central Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Cortes Campos, Carlos Cristobal [Instituto de Investigaciones Electricas, Cuernavaca (Mexico); Montes Tadeo, Jose Luis [Instituto Nacional de Investigaciones Nucleares (ININ), Salazar (Mexico)

    1991-12-31

    It is described, in general terms, the procedure that is followed to accomplish the optimization of the recharge design, and an example is shown where this procedure was applied for the analysis of the type BWR reactor of Unit No. 1 of the Laguna Verde Nuclear Power Station. [Espanol] Se describe en terminos generales el procedimiento que se sigue para realizar la optimacion del diseno de recargas, y se muestra un ejemplo en el que se utilizo dicho procedimiento para el analisis del reactor tipo BWR de la unidad 1, de la Central Laguna Verde (CLV).

  12. Research on Pump-induced Pulsation of the Principal Loops of Nuclear Power Stations%主回路泵致声振动分析

    Institute of Scientific and Technical Information of China (English)

    周莹; 蔡坤

    2015-01-01

    The reactor coolant pump is the core equipment of nuclear power stations. The pump-induced pulsations can cause the vibration of the main equipment’s components, which is regarded as one of the main reasons of fatigue failure of the components. In this paper, the effect of the pump-induced pulsation on the principal loop of a nuclear station was calculated and analyzed. Then, the feasibility of application of ACSTIC program to the acoustic vibration analysis of the principal loop was verified theoretically and numerically. Finally, the acoustic vibration performance of the principal loop of the nuclear power station was simulated by means of the ACSTIC program, and the harmonic vibration responses of the main equipment’s components were obtained. The result can be used for the fatigue analysis and evaluation of the main equipment’s components and the optimization of the design of main loops of nuclear power stations.%主泵是核电站主回路中的核心设备之一,它产生的压力脉动会导致主设备部件振动,是设备发生疲劳失效的主要原因之一。首先,对泵—声耦合对核电站主回路的作用进行分析计算,然后采用理论分析和数值分析相结合的方法验证ACSTIC程序进行声振动分析的适用性,最后采用ACSTIC声振动程序模拟核电厂主回路模型,计算主设备部件的谐振动响应值。计算结果可用于主设备部件的疲劳分析评定,也可用于主回路优化设计。

  13. Mechanical Properties and Microstructures of the HAZs of 11Cr F/M Steel for Gen-IV Nuclear Power Station

    Science.gov (United States)

    Li, Yongkui; Wang, Jian; Lu, Shanping; Rong, Lijian; Li, Dianzhong

    2015-02-01

    The weldability of a newly developed 11Cr ferritic/martensitic (F/M) steel to be used in Pb-Bi liquid cooled ADS for the fourth generation nuclear power station was studied by experiments and numerical simulation. In this work, an appropriate method for obtaining simulated heat-affected zones (HAZs) was developed. HAZs, including CG-HAZ, FG-HAZ, and IC-HAZ, were successfully simulated by Gleeble at heating rates of 209, 176, and 149 °C/s and peak temperatures of 1314, 1138, and 998 °C, respectively. Results of tension and impact tests indicated that the simulated HAZs had much higher strength and poorer toughness than the base metal. The poor toughness is caused by high carbon, silicon contents, and quenched martensitic microstructures. The tempering treatment is necessary for the developed steel before application in nuclear reactor.

  14. 75 FR 12312 - South Carolina Electric and Gas Company; Virgil C. Summer Nuclear Station, Unit 1; Exemption

    Science.gov (United States)

    2010-03-15

    ... emergency core cooling systems for light- water nuclear power reactors,'' requires, among other items, that: Each boiling or pressurized light-water nuclear power reactor fueled with uranium oxide pellets within... regulations of 10 CFR 50.46 and 10 CFR part 50, Appendix K, make no provision for use of fuel rods clad in...

  15. 76 FR 52357 - Exelon Generation Company, LLC; PSEG Nuclear, LLC; Peach Bottom Atomic Power Station, Unit 3...

    Science.gov (United States)

    2011-08-22

    ... Branch 1-2, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation, U.S. Nuclear... Power Ratio (SLMCPR) values. The SLMCPR is established to assure that at least 99.9% of the fuel rods in... Reactor Fuel,'' Revision 18. The basis of the SLMCPR calculation is to ensure that during normal...

  16. 78 FR 6145 - Virgil C. Summer Nuclear Station, Units 2 and 3; Application and Amendment to Facility Combined...

    Science.gov (United States)

    2013-01-29

    ... basemat shear reinforcement does not have an adverse impact on the response of the basemat and nuclear... development of headed shear reinforcement within the nuclear island basemat concrete. Before issuance of the... postulated accident conditions. The change of the requirements for anchoring basemat shear reinforcement...

  17. 77 FR 21815 - South Carolina Electric And Gas Company (Virgil C. Summer Nuclear Station Units 2 and 3); Order...

    Science.gov (United States)

    2012-04-11

    ... after about 70 hours, and in the Unit 3 reactor after about 36 hours, resulting in damage to the nuclear... high-temperature reaction of steam and zirconium fuel cladding generating hydrogen gas. This concern... the general design criteria (GDC) for nuclear power plants. All currently operating reactors...

  18. International challenge to predict the impact of radioxenon releases from medical isotope production on a comprehensive nuclear test ban treaty sampling station.

    Science.gov (United States)

    Eslinger, Paul W; Bowyer, Ted W; Achim, Pascal; Chai, Tianfeng; Deconninck, Benoit; Freeman, Katie; Generoso, Sylvia; Hayes, Philip; Heidmann, Verena; Hoffman, Ian; Kijima, Yuichi; Krysta, Monika; Malo, Alain; Maurer, Christian; Ngan, Fantine; Robins, Peter; Ross, J Ole; Saunier, Olivier; Schlosser, Clemens; Schöppner, Michael; Schrom, Brian T; Seibert, Petra; Stein, Ariel F; Ungar, Kurt; Yi, Jing

    2016-06-01

    The International Monitoring System (IMS) is part of the verification regime for the Comprehensive Nuclear-Test-Ban-Treaty Organization (CTBTO). At entry-into-force, half of the 80 radionuclide stations will be able to measure concentrations of several radioactive xenon isotopes produced in nuclear explosions, and then the full network may be populated with xenon monitoring afterward. An understanding of natural and man-made radionuclide backgrounds can be used in accordance with the provisions of the treaty (such as event screening criteria in Annex 2 to the Protocol of the Treaty) for the effective implementation of the verification regime. Fission-based production of (99)Mo for medical purposes also generates nuisance radioxenon isotopes that are usually vented to the atmosphere. One of the ways to account for the effect emissions from medical isotope production has on radionuclide samples from the IMS is to use stack monitoring data, if they are available, and atmospheric transport modeling. Recently, individuals from seven nations participated in a challenge exercise that used atmospheric transport modeling to predict the time-history of (133)Xe concentration measurements at the IMS radionuclide station in Germany using stack monitoring data from a medical isotope production facility in Belgium. Participants received only stack monitoring data and used the atmospheric transport model and meteorological data of their choice. Some of the models predicted the highest measured concentrations quite well. A model comparison rank and ensemble analysis suggests that combining multiple models may provide more accurate predicted concentrations than any single model. None of the submissions based only on the stack monitoring data predicted the small measured concentrations very well. Modeling of sources by other nuclear facilities with smaller releases than medical isotope production facilities may be important in understanding how to discriminate those releases from

  19. 核电站K3级充电器设备鉴定探究%Qualification Research of Nuclear Power Station K3 Charger

    Institute of Scientific and Technical Information of China (English)

    林建; 许本福; 张瑞明

    2013-01-01

      The paper analyses the differences between RCC-E and IEEE concerning the charger qualification. Based on the RCC-E,related standards and technical data,the paper introduces classification and qualification methods of Class 1E electrical equipment for nuclear power station,investigates in detail the K3 charger of nuclear power station,provides reference to the K3 charger localization.%  本文分析了RCC-E和IEEE标准对充电器设备鉴定要求的区别。基于RCC-E等相关标准和技术资料,本文介绍了核电站1E级电气设备分级和鉴定方法,对核电站K3级充电器设备鉴定进行了深入研究,为K3级充电器国产化提供了借鉴作用。

  20. Thermal-hydraulics, physical chemistry, and technology at nuclear power stations equipped with fast-neutron sodium-cooled reactors

    Science.gov (United States)

    Alekseev, V. V.; Efanov, A. D.; Kozlov, F. A.; Sorokin, A. P.

    2007-12-01

    Main results of investigations aimed at developing a verified system of computer codes that take into account the interrelation among nuclear-physical, thermal-hydraulic, physicochemical, thermal-mechanical, mass-transfer, and technological processes in nuclear power installations and at substantiating the models used as the core of these codes are presented together with the results of tests carried out to obtain data for verifying the codes.

  1. M310核电站非能动安全改进措施研究%Study on Passive Safety Improvement of M310 Nuclear Power Station

    Institute of Scientific and Technical Information of China (English)

    邹象; 郎明刚

    2015-01-01

    A severe accident model of typical M310 nuclear power station with MELCOR 1.8.5 code was constructed in this paper .Based on the model ,several passive safety measures were designed ,and their benefits of mitigating the accident caused by station blackout (SBO) were simulated .The calculating results show that the core makeup tank system , external reactor vessel cooling system and passive residual heat removal system can operate successfully in SBO , postpone the progression of the accident markedly , stabilize the M310 nuclear power station in a safe state and gain more time for manual intervention .%本文利用MELCOR1.8.5程序建立了典型的M310核电站的严重事故模型,基于该模型设计了多种非能动的缓解措施,针对由全厂断电诱发的严重事故,模拟研究了这些非能动安全措施的缓解效果。研究结果表明:在全厂断电事故下,堆芯补水箱系统、堆腔注水系统、非能动余热排出系统均能有效地投入使用,并显著地延缓事故的发展,将核电站稳定在一个安全的状态,为人工干预赢得更多时间。

  2. The nuclear techniques in function of improving the efficiency of the station of treatment of industrial waste in PETROBRAS; Las tecnicas nucleares en funcion de mejorar la eficiencia de la estacion de tratamiento de desechos industriales en PETROBRAS

    Energy Technology Data Exchange (ETDEWEB)

    Damera Martinez, Arnaldo; Ramos Espinosa, Kenia A. [Centro de Atencion a la Actividad Nuclear, Camaguey (Cuba)]. E-mail: damera@caonao.cmw.inf.cu; Pinto, Amenonia Ferreira; Barbalho, Andrea de Magalhaes [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Belo Horizonte, MG (Brazil); Derivet Zarzabal, Milagros [Instituto Cubano de Investigaciones Azucareras, La Habana (Cuba)

    2001-07-01

    The industry of the petroleum has become in the last decades, an user of the Nuclear Techniques. Due to the amplification of activities in some of the technical and economic characteristics of this industry the possibilities of application of the nuclear techniques in the oil sector are proportionally bigger and more important than in many other sectors of the economy. This work was carried out in the Station of Treatment of Industrial Wastes in PETROBRAS (Brazil). It has the objective of determinating the time of real residence of the misture of waste inside the separator by means of radioactive tracer, using the Tc-99m. This has a great economic and environmental importance, because when obtaining the time of residence experimentally in the separators, you can compare with those obtained theoretically, which allows to influence with more precision on the system, optimizing their operation, and diminishing the magnitude of its possible negative environmental impact. (author)

  3. Remote sensing monitoring of thermal discharge in Daya Bay Nuclear Power Station based on HJ-1 infrared camera

    Science.gov (United States)

    Zhu, Li; Yin, Shoujing; Wu, Chuanqing; Ma, Wandong; Hou, Haiqian; Xu, Jing

    2014-11-01

    In this paper, the method of monitoring coastal areas affected by thermal discharge of nuclear plant by using remote sensing techniques was introduced. The proposed approach was demonstrated in Daya Bay nuclear plant based on HJ-B IRS data. A single channel water temperature inversion algorithm was detailed, considering the satellite zenith angle and water vapor. Moreover the reference background temperature was obtained using the average environmental temperature method. In the case study of Daya Bay nuclear plant, the spatial distribution of thermal pollution was analyzed by taking into account the influence of tidal, wind and so on. According to the findings of this study, the speed and direction of the ebb tide, is not conducive to the diffusion of thermal discharge of DNNP. The vertically thermal diffusion was limited by the shallow water depth near the outlet.

  4. 78 FR 47795 - In the Matter of Entergy Nuclear Generation Company Pilgrim Power Station Independent Spent Fuel...

    Science.gov (United States)

    2013-08-06

    ... Entergy because it has identified near-term plans to store spent fuel in an ISFSI under the general... 20852. FOR FURTHER INFORMATION, CONTACT: L. Raynard Wharton, Office of Nuclear Material Safety and... because it has identified near- term plans to store spent fuel in an ISFSI under the general...

  5. 75 FR 16517 - Dominion Nuclear Connecticut, Inc.; Millstone Power Station, Unit Nos 1, 2, and 3; Exemption

    Science.gov (United States)

    2010-04-01

    ... Background Dominion Nuclear Connecticut, Inc. (DNC or the licensee) is the holder of Facility Operating... orders. It is from two of these new requirements that DNC now seeks an exemption from the March 31, 2010... supplemented by letter dated January 12, 2010 (ADAMS Accession No. ML100131115), DNC requested an exemption...

  6. Thermal Modeling of NUHOMS HSM-15 and HSM-1 Storage Modules at Calvert Cliffs Nuclear Power Station ISFSI

    Energy Technology Data Exchange (ETDEWEB)

    Suffield, Sarah R.; Fort, James A.; Adkins, Harold E.; Cuta, Judith M.; Collins, Brian A.; Siciliano, Edward R.

    2012-10-01

    As part of the Used Fuel Disposition Campaign of the Department of Energy (DOE), visual inspections and temperature measurements were performed on two storage modules in the Calvert Cliffs Nuclear Power Station’s Independent Spent Fuel Storage Installation (ISFSI). Detailed thermal models models were developed to obtain realistic temperature predictions for actual storage systems, in contrast to conservative and bounding design basis calculations.

  7. 核电站事故后监测电离室设计方法%Designing methods for nuclear power station accident condition ionization chamber

    Institute of Scientific and Technical Information of China (English)

    孙光智; 王益元; 李亚坚; 代传波; 粱云; 左亮周

    2011-01-01

    介绍了一种用于核电站事故后γ辐射剂量率监测的电离室设计所需的模拟计算方法;用MCNP程序模拟计算了射线在不同结构、不同工作气体的电离室中灵敏度的能量响应特性,为事故后监测电离室的设计提供了理论依据.%Simulation and calculation methods for designing of ionization chamber used in nuclear power station during accident conditions were introduced in this paper. Using MCNP program,we calculated energy response of this chamber with various structures and sensitive gas,supplied theoretic dependence for designing of ionization chamber used during accident conditions.

  8. Measurements of beta ray spectra inside nuclear generating stations using a silicon detector coincidence telescope: skin dose beta correction factors for TL elements

    Energy Technology Data Exchange (ETDEWEB)

    Horowitz, Y.S.; Weizmann, Y. [Ben Gurion University of the Negev (Israel); Hirning, C.R. [Ontario Hydro, Whitby (Canada). Health Physics

    1996-10-01

    The measurement of beta ray spectra at various work locations inside nuclear generating stations operated by Ontario Hydro is described. The measurements were carried out using an advanced coincidence telescope spectrometer using silicon detectors only. The spectrometer is capable of measuring electron energies over the range 70-2500 keV with close to 100% efficiency. Over 40 beta ray spectra were measured at various work locations in three nuclear generating stations. Photon rejection is carried out by requiring a coincidence between either two or three detectors. Monte Carlo calculations were then used to estimate beta correction factors for the LiF:Mg,Ti elements used in the Ontario Hydro thermoluminescence dosemeters. Averaging over all the measured beta correction factors for the `skin chip (100 mg. cm{sup -2}) results in a value of 2.73 {+-} 0.77 and for the extremity dosemeter (240 mg.cm{sup -2}) an average value of 4.42 {+-} 1.17 is obtained. These values are 57% and 120% greater, respectively, than the current values used by Ontario Hydro. In addition, beta correction factors for nine representative spectra were calculated for 40 mg.cm{sup -2} and 20 mg.cm{sup -2} chips, and the results demonstrate the benefits of decreased dosemeter thickness. The average value of the beta correction factor, as well as the spread in the beta correction factor, decreases dramatically from 4.80 {+-} 2.1 (240 mg.cm{sup -2}) to 1.29 {+-} 0.1 (20mg.cm{sup -2}). (Author).

  9. Screening evaluation of radionuclide groundwater concentrations for the end state basement fill model Zion Nuclear Power Station decommissioning project

    Energy Technology Data Exchange (ETDEWEB)

    Sullivan T.

    2014-06-09

    ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled with clean material. The final selection of fill material has not been made.

  10. Current research and development activities on fission products and hydrogen risk after the accident at Fukushima Daiichi nuclear power station

    Energy Technology Data Exchange (ETDEWEB)

    Nishimura, Takeshi; Hoshi, Harutaka; Hotta, Akitoshi [Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority, Tokyo (Japan)

    2015-02-15

    After the Fukushima Daiichi nuclear power plant (NPP) accident, new regulatory requirements were enforced in July 2013 and a backfit was required for all existing nuclear power plants. It is required to take measures to prevent severe accidents and mitigate their radiological consequences. The Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority (S/NRA/R) has been conducting numerical studies and experimental studies on relevant severe accident phenomena and countermeasures. This article highlights fission product (FP) release and hydrogen risk as two major areas. Relevant activities in the S/NRA/R are briefly introduced, as follows: 1. For FP release: Identifying the source terms and leak mechanisms is a key issue from the viewpoint of understanding the progression of accident phenomena and planning effective countermeasures that take into account vulnerabilities of containment under severe accident conditions. To resolve these issues, the activities focus on wet well venting, pool scrubbing, iodine chemistry (in-vessel and ex-vessel), containment failure mode, and treatment of radioactive liquid effluent. 2. For hydrogen risk: because of three incidents of hydrogen explosion in reactor buildings, a comprehensive reinforcement of the hydrogen risk management has been a high priority topic. Therefore, the activities in evaluation methods focus on hydrogen generation, hydrogen distribution, and hydrogen combustion.

  11. Comparison of the Standards applied to Instrumentation and Control Systems for Nuclear Power Stations in Korea and Russia

    Energy Technology Data Exchange (ETDEWEB)

    Park, Joo Hyun; Hwang, In Koo; Lee, Dong Young

    2005-04-15

    This report describes a comparison result of technical standards applied to instrumentation and control systems for nuclear power plants between in Korea and in Russia. Russia also has a state-run organization authorized to conduct approval, cancellation, and audit in use of nuclear facility or equipment. The Russian standards for nuclear instrumentation and control equipment are analogous with the Korean ones in the aspect of basic concepts and principles. However, there are some differences in document structure, design requirements, qualification test items, depth of contents between two standard systems. The biggest deviation exists in the standard documents for seismic qualification and electromagnetic interference qualification. Korean seismic qualification standard utilizing US approach, defines testing and qualification methods specifically and clearly. Russian standards however provide only conceptual definitions and requirements in the seismic related aspects. Therefore, it is conceived that any equipment or system qualified seismically in accordance with Korean standards should additionally provide technical evidence that it is satisfactory with Russian standards as well. In electromagnetic interference qualification, because Russian standard requires more testing items than the current Korean standard, the additional qualification tests are necessary to meet the Russian requirements. However, these additional test items are based on IEC(International Electrotechnical Commission), therefore it is not a problem to perform those tests in a Korean testing facility.

  12. The uptake of iron-55 by marine sediment, macroalgae, and biota following discharge from a nuclear power station.

    Science.gov (United States)

    Warwick, P E; Cundy, A B; Croudace, I W; Bains, M E; Dale, A A

    2001-06-01

    Significant quantities of 55Fe, an activation product of stable iron, have been released into the environment following the atmospheric testing of nuclear weapons (mainly in the 1950s and 1960s) as well as through authorized discharges of radioactivity from nuclear power and reprocessing sites. Although some studies have been performed on the behavior of weapons' fallout-derived 55Fe in the environment and subsequent impact on humans, little has been published on the behavior of 55Fe released as a point source discharge from nuclear sites. This study presents data on the concentration and temporal variation of 55Fe in fucoid seaweeds, shellfish, crab, and lobster collected from Weymouth Bay and adjacent coastal areas, southern England. These areas have received authorized discharges of radionuclides originating from the operation of a now-decommissioned steam-generating, heavy water-type reactor at AEE Winfrith. The highest activities of 55Fe are found associated with marine sediments collected near the discharge pipeline and a rapid decline occurs away from the pipeline. This is consistent with rapid sorption of 55Fe by the sediment, and the data show there is only limited reworking and remobilization. Activities of 55Fe in biota generally decreased over time, due to a reduction in the amount of 55Fe discharged. The variation of 55Fe activity, revealed from the monthly sampling of seaweed, does not reflect the short-term fluctuations seen in the patterns of discharged 55Fe activity. Although discharges of 55Fe from AEE Winfrith exceeded other radionuclides, the radiological impact on local seafood consumers is considerably less than for other key radionuclides such as 60Co and 65Zn but of comparable magnitude to the global average population dose arising from fallout-derived 55Fe.

  13. Preliminary Thermal Modeling of Hi-Storm 100S-218 Version B Storage Modules at Hope Creek Nuclear Power Station ISFSI

    Energy Technology Data Exchange (ETDEWEB)

    Cuta, Judith M.; Adkins, Harold E.

    2013-08-30

    This report fulfills the M3 milestone M3FT-13PN0810022, “Report on Inspection 1”, under Work Package FT-13PN081002. Thermal analysis is being undertaken at Pacific Northwest National Laboratory (PNNL) in support of inspections of selected storage modules at various locations around the United States, as part of the Used Fuel Disposition Campaign of the U.S. Department of Energy, Office of Nuclear Energy (DOE-NE) Fuel Cycle Research and Development. This report documents pre-inspection predictions of temperatures for four modules at the Hope Creek Nuclear Generating Station ISFSI that have been identified as candidates for inspection in late summer or early fall/winter of 2013. These are HI-STORM 100S-218 Version B modules storing BWR 8x8 fuel in MPC-68 canisters. The temperature predictions reported in this document were obtained with detailed COBRA-SFS models of these four storage systems, with the following boundary conditions and assumptions.

  14. Effect of pH on the release of radionuclides and chelating agents from cement-solidified decontamination ion-exchange resins collected from operating nuclear power stations

    Energy Technology Data Exchange (ETDEWEB)

    McIsaac, C.V.; Akers, D.W.; McConnell, J.W. (EG and G Idaho, Inc., Idaho Falls, ID (USA))

    1991-06-01

    Data are presented on the physical stability and leachability of radionuclides and chelating agents from cement-solidified decontamination ion-exchange resin wastes collected from two operating commercial light water reactors. Small-scale waste--form specimens collected during solidifications performed at the Brunswick Steam Electric Plant Unit 1 and at the James A. FitzPatrick Nuclear Power Station were leach-tested and subjected to compressive strength testing in accordance with the Nuclear Regulatory Commission's Technical Position on Waste Form'' (Revision 1). Samples of untreated resin waste collected from each solidification vessel before the solidification process were analyzed for concentrations of radionuclides, selected transition metals, and chelating agents to determine the quantities of these chemicals in the waste-form specimens. The chelating agents included oxalic, citric, and picolinic acids. In order to determine the effect of leachant chemical composition and pH on the stability and leachability of the waste forms, waste-form specimens were leached in various leachants. Results of this study indicate that differences in pH do not affect releases from cement-solidified decontamination ion-exchange resin waste forms, but that differences in leachant chemistry and the presence of chelating agents may affect the releases of radionuclides and chelating agents. Also, this study indicates that the cumulative releases of radionuclides and chelating agents are similar for waste- form specimens that decomposed and those that retained their general physical form. 36 refs., 60 figs., 28 tabs.

  15. Fuzzy logics acquisition and simulation modules for expert systems to assist operator`s decision for nuclear power stations

    Energy Technology Data Exchange (ETDEWEB)

    Averkin, A.A. [Russian Academy of Sciences, Moscow (Russian Federation). Computer centre

    1994-12-31

    A new type of fuzzy expert system for assisting the operator`s decisions in nuclear power plant system in non-standard situations is proposed. This expert system is based on new approaches to fuzzy logics acquisition and to fuzzy logics testing. Fuzzy logics can be generated by a T-norms axiomatic system to choose the most suitable to operator`s way of thinking. Then the chosen fuzzy logic is tested by simulation of inference process in expert system. The designed logic is the input of inference module of expert system.

  16. 岭澳核电站二期反应堆核测量相关系统设计%Design of Reactor Nuclear Measurement Systems in Ling'ao Nuclear Power Station Phase Ⅱ

    Institute of Scientific and Technical Information of China (English)

    李文平; 杨戴博

    2012-01-01

    分析岭澳核电站二期反应堆核测量各相关系统的主要特点,阐述核仪表系统(RPN)、堆芯中子注量率测量系统(RIC)、冷却剂丧失事故(LOCA)监测系统(LSS)与数字化仪表控制系统(DCS)的功能划分和接口设计方案.岭澳核电站二期设计方案针对RPN、RIC、LSS不同的功能需求和特点,有效地利用数字化仪表控制平台的优势,灵活采用3种与DCS的功能分配和接口划分方案,更好地实现了故障诊断和逻辑功能处理.%This paper analyzes the characteristics of Reactor Nuclear Measurement Systems, including Nuclear Instrumentation System (RPN), In-core Neutron Fluence Rate Measurement system (RIC), LOCA Surveillance System (LSS), and introduces the function distribution and interface design between the Nuclear Measurement Systems and the Digital Instrument Control System (DCS). Based on the advantages of DCS, 3 different function distribution and interface design schemes are taken in Ling'ao Nuclear Power Station Phase II for different function requirements and characteristics of RPN, RIC and LSS. Consequently, these design schemes lead to a good result in fault diagnosis and logic processing.

  17. 滨海核电厂冷却水排水建筑物布置的应用研究%Application Research on Cooling Water Outlet Structure Arrangement of Coastal Nuclear Power Station

    Institute of Scientific and Technical Information of China (English)

    李波; 汤东升

    2012-01-01

    Arrangement design of Cooling Water Outlet Structure is a key problem for Coastal Nuclear Power Station. Cooling Water Outlet structure ensures the normal operation of units, and it protect the equipments of Coastal Nuclear Power Station against storm surge by Cooling Water Outlet Structure. This paper illustrates the design criterions which need to be followed of hydraulic arrangement in Coastal Nuclear Power Station, as well as provides the experience in the Cooling Water Outlet structure arrangement design of Coastal Nuclear Power Station.%冷却水排水建筑物布置是滨海核电厂水工建筑物布置设计中的关键问题,排水建筑物不仅确保核电厂冷却水系统正常运行,同时保护核电厂免受风暴潮危害影响.通过对已建滨海核电厂冷却水排水建筑物布置特点进行分类阐述,为排水建筑物布置设计提供工程应用参考.

  18. Hydrologic, water-quality, and meteorologic data from selected sites in the Upper Catawba River Basin, North Carolina, January 1993 through March 1994

    Science.gov (United States)

    Jaynes, M.L.

    1994-01-01

    Hydrologic, water-quality, and meteorologic data were collected from January 1993 through March 1994 as part of a water-quality investigation of the Upper Catawba River Basin, North Carolina. Specific objectives of the investigation were to characterize the water quality of Rhodhiss Lake, Lake Hickory, and three tributary streams, and to calibrate hydrodynamic water-quality models for the two reservoirs. Sampling locations included 11 sites in Rhodhiss Lake, 14 sites in Lake Hickory, and 3 tributary sites. Tributary sites were located at Lower Creek upstream from Rhodhiss Lake and at Upper Little River and Middle Little River upstream from Lake Hickory. During 21 sampling visits, specific conductance, pH, water temperature, dissolved-oxygen concentration, and water transparency were measured at all sampling locations. Water samples were collected for analysis of biochemical oxygen demand, fecal coliform bacteria, hardness, alkalinity, total and volatile suspended solids, suspended sediment, nutrients, total organic carbon, chlorophyll, iron, calcium, and magnesium from three sites in each reservoir and from the three tributary sites. Chemical and particle-size analyses of bottom material from Rhodhiss Lake and Lake Hickory were performed once during the study. At selected locations, automated instruments recorded water level, streamflow, water temperature, solar radiation, and air temperature at 15-minute intervals throughout the study. Hydrologic data presented in the report include monthly water-level statistics and daily mean values of discharge. Diagrams, tables, and statistical summaries of water-quality data are provided. Meteorologic data in the report include monthly precipitation, and daily mean values of solar radiation and air temperature.

  19. Application of the k{sub 0}-INAA method for analysis of biological samples at the pneumatic station of the IEA-R1 nuclear research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Puerta, Daniel C.; Figueiredo, Ana Maria G.; Semmler, Renato, E-mail: dcpuerta@hotmail.com, E-mail: anamaria@ipen.br, E-mail: rsemmler@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Jacimovic, Radojko, E-mail: radojko.jacimovic@ijs.si [Jozef Stefan Institute (JSI), Ljubljana, LJU (Slovenia). Department of Environmental Sciences

    2013-07-01

    As part of the process of implementation of the k{sub 0}-INAA standardization method at the Neutron Activation Laboratory (LAN-IPEN), Sao Paulo, Brazil, this study presents the results obtained for the analysis of short and medium-lived nuclides in biological samples by k{sub 0}-INAA using the program k{sub 0}-IAEA, provided by the International Atomic Energy Agency (IAEA). The elements Al, Ba, Br, Na, K, Mn, Mg, Sr and V were determined with respect to gold ({sup 197}Au) using the pneumatic station facility of the IEA-R1 4.5 MW swimming pool nuclear research reactor, Sao Paulo. Characterization of the pneumatic station was carried out by using the 'bare triple-monitor' method with {sup 197}Au-{sup 96}Zr-{sup 94}Zr. The Certified Reference Material IRMM-530R Al-0.1%Au alloy and high purity zirconium comparators were used. The efficiency curves of the gamma-ray spectrometer used were determined by measuring calibrated radioactive sources at the usually utilized counting geometries. The method was validated by analyzing the reference materials NIST SRM 1547 Peach Leaves, INCT-MPH-2 Mixed Polish Herbs and NIST SRM 1573a Tomato Leaves. The concentration results obtained agreed with certified, reference and recommended values, showing relative errors (bias, %) less than 30% for most elements. The Coefficients of Variation were below 20%, showing a good reproducibility of the results. The E{sub n}-number showed that all results, except Na in NIST SRM 1547 and NIST SRM 1573a and Al in INCT-MPH-2, were within 95% confidence interval. (author)

  20. Effect of Coolant Inventories and Parallel Loop Interconnections on the Natural Circulation in Various Heat Transport Systems of a Nuclear Power Plant during Station Blackout

    Directory of Open Access Journals (Sweden)

    Avinash J. Gaikwad

    2008-01-01

    Full Text Available Provision of passive means to reactor core decay heat removal enhances the nuclear power plant (NPP safety and availability. In the earlier Indian pressurised heavy water reactors (IPHWRs, like the 220 MWe and the 540 MWe, crash cooldown from the steam generators (SGs is resorted to mitigate consequences of station blackout (SBO. In the 700 MWe PHWR currently being designed an additional passive decay heat removal (PDHR system is also incorporated to condense the steam generated in the boilers during a SBO. The sustainability of natural circulation in the various heat transport systems (i.e., primary heat transport (PHT, SGs, and PDHRs under station blackout depends on the corresponding system's coolant inventories and the coolant circuit configurations (i.e., parallel paths and interconnections. On the primary side, the interconnection between the two primary loops plays an important role to sustain the natural circulation heat removal. On the secondary side, the steam lines interconnections and the initial inventory in the SGs prior to cooldown, that is, hooking up of the PDHRs are very important. This paper attempts to open up discussions on the concept and the core issues associated with passive systems which can provide continued heat sink during such accident scenarios. The discussions would include the criteria for design, and performance of such concepts already implemented and proposes schemes to be implemented in the proposed 700 MWe IPHWR. The designer feedbacks generated, and critical examination of performance analysis results for the added passive system to the existing generation II & III reactors will help ascertaining that these safety systems/inventories in fact perform in sustaining decay heat removal and augmenting safety.

  1. 30 years in the Veracruz state coast landscape: Laguna Verde nuclear power station. 1. ed.; 30 anos de paisaje costero veracruzano: Central Nucleoelectrica Laguan Verde

    Energy Technology Data Exchange (ETDEWEB)

    Guevara, S; Moreno Casasola, P; Castillo Campos, G; Dorantes, C; Gonzalez Garcia, F; Halffter, G; Isunza, E; Lot H, A; Mendoza, R; Paradowska, K; Priego, A; Sanchez Vigil, C; Vazquez, G [Comision Federal de Electricidad and Instituto Nacional de Ecologia A.C. (Mexico)

    2008-07-01

    36 years ago one of the most important power projects of Mexico was born; the design and construction of the Nuclear power station Laguna Verde. This project became reality thanks to the commitment of a group of Mexican professionals that gave the best of them for its accomplishment. At that time, there was not in Mexico a legislation that contemplated the environmental protection; nevertheless, the Mexican Constitution anticipates that when in the country there is not legislation for the development of a project, this must adopt the legislation of the country that is selling it. In the specific case of Laguna Verde, the legislation of the United States of America was adopted and in the environmental part it had to issue the first Manifest of Environmental impact, that was called Informe Ambiental para la Contruccion de Laguna Verde en el Estado de Veracruz. This study was performed by several national as well as foreign institutions. Among the most outstanding are the Universidad Nacional Autonoma de Mexico, the Intituto Politecnico Nacional, the Universidad Veracruzana, the Intituto National para la Investigacion de Recursos Biologicos, the Instituto de Ecologia, A.C. With this report, the engineers undertook the task of designing and constructing, the biologists and ecologists to realize the studies to mitigate the effects caused to the environment during the construction and later, during the operation of the Nuclear power station. After 18 years of commercial operation of the power station the present book is completed, in which the results obtained in 1972, when the studies of the environmental report began are compared against the ones obtained throughout this period. It is important to see in the results of the different studies and indicators presented/displayed in this book, that the important changes on the environment are due, to the change of the ground use and the over-exploitation of the natural resources as it happens in almost all the country. The

  2. Nuclear Safety Review for Qualification of Class 1E Motor inside Containment for Nuclear Power Stations%1E级安全壳内用电动机鉴定的核安全审查

    Institute of Scientific and Technical Information of China (English)

    李世欣; 毋琦; 张云波; 吴彩霞

    2013-01-01

    In nuclear power plants with pressurized water reactors,the review for class 1E motor inside containment qualification process and documents is an important aspect of nuclear safety equipment review,and the reviewers should make evaluations for the qualification test results in terms of the compliance with standard and regulation,and the consistency with inside containment environment.Firstly,this paper introduces the qualification test of class 1E motor inside containment for nuclear power generating stations,such as aging test and design-basis-event test.Second,there is a discussion about typical problems of review.At last,comparison of IEEE334 with RCC-E is conducted and explored.%对压水堆核电厂1E级安全壳内电动机的鉴定过程和鉴定文件进行审查,要求对鉴定试验结果与标准法规的符合性以及与安全壳内环境要求的一致性做出评价.首先介绍1E级安全壳内用电动机的老化试验、设计基准事故试验等主要鉴定试验,对随后审查过程中遇到的典型问题进行分析,并将IEEE 334与RCC-E两套标准进行对比探讨.

  3. An Independent Assessment of Evacuation Time Estimates for A Peak Population Scenario in the Emergency Planning Zone of the Seabrook Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Moeller, M. P.; Urbanik, II, T.; Mclean, M. A.; Desrosiers, A. E.

    1982-11-01

    This study comprises two major tasks. First, it includes an independent assessment of the methods and assumptions used in calculating evacuation time estimates (ETEs) applicable to the general population for a peak population scenario in the emergency planning zone {EPZ) of the Seabrook Nuclear Power Station. This consists of a review and analysis of previous work by Public Service of New Hampshire {PSNH) and the Federal Emergency Management Agency (FEMA), as well as an independent calculation of evacuation times using the CLEAR model for the demographic data reported by PSNH. Secondly, this study includes independent estimations of evacuation time for the peak population scenario developed using demographic data prepared by the U.S. Nuclear Regulatory Commission {NRC). These evacuation time estimates are approximately 60% and 84% greater, respectively, than the estimate provided by PSNH for a simulataneous evacuation of the entire EPZ under peak conditions. The CLEAR model, which was developed by Pacific Northwest Laboratory {PNL) under the sponsorship of the. NRC, was also used for these latter calculations. The results of this study reveal the importance of the assumptions used for calculating evacuation times. Because traffic routings and management plans have not been prepared for the area, the CLEAR calculations utilized indepdently prepared traffic routings and assumptions. A detailed analysis of the results suggests that the ETEs submitted by PSNH are consistent with the methods and assumptions which provide the bases for PSNH•s evacuation time estimates. Differences among evacuation time estimates stem largely from differences jn the assumed size of the evacuating population and the estimated effectiveness of traffic controls.

  4. 我国核电站运行对周围居民健康影响研究进展%Health effects of residents living around nuclear power station on in China: a review of reccent studies

    Institute of Scientific and Technical Information of China (English)

    张继勉

    2012-01-01

    With the development of China's nuclear power industry in recent years, more and more attention has been paid to the problem on the health effects of residents living around nuclear power station. The health conditions (including residents' recognition on nuclear power, nuclear anxiety situation, the residents' life expectancy, cause of death analysis, the incidence and death of malignant tumors, children's health status and birth defects, etc.) of the residents living around Zhejiang Qinshan Nuclear Power Station, Guangdong Daya Bay Nuclear Power Station and Jiangsu Tianwan Nuclear Power Station before and after the running of nuclear power station has been summarized in this paper. It was found that the running nuclear power stations in China hadn't brought adverse effect to the health of the surrounding residents, and there were no uncommon prevalence and variations of diseases. Meanwhile it has been proposed that with the rapid development of China's nuclear power, it is a significant step in the medical preparation for nuclear accidents to establish and improve the health monitoring network and obtain the fundamental national information about the health conditions of the surrounding residents from the site selection to the retirement of the nuclear station.%近年来随着我国核电事业的发展,核电站的运行对其周围居民健康状况的影响越来越受到关注.该文对我国在运行的浙江泰山、广东大亚湾和江苏田湾核电站周围居民在核电站运行前后的健康状况(包括居民核电认知、核焦虑状况、居民期望寿命、死因分析、恶性肿瘤发病及死亡情况、儿童健康状况和新生儿出生缺陷等)进行综述.结果认为目前我国各核电站的正常运行没有对周围人群的健康带来不利影响,未发现异常的疾病流行及变动.同时提出在我国核电事业迅猛发展的形势下,建立健全健康监测网络,获得核电站从选址至退役多个时期周围人

  5. Concentrations of Radiocesium in Local Foods Collected in Kawauchi Village after the Accident at the Fukushima Dai-ichi Nuclear Power Station

    Science.gov (United States)

    Orita, Makiko; Nakashima, Kanami; Hayashida, Naomi; Endo, Yuuko; Yamashita, Shunichi; Takamura, Noboru

    2016-06-01

    We evaluated the current concentrations of radiocesium in local foods collected in Kawauchi Village, which is located less than 30 km from Fukushima Daiichi Nuclear Power Station, to minimize public anxiety regarding internal radiation exposure through the consumption of locally produced foods after the 2011 Fukushima accident. The number of samples exceeding the regulatory radiocesium limit (100 Bq/kg for general foods) was five out of 4,080 vegetables (0.1%), 652 of 1,986 (32.8%) among edible wild plants and fungi, and eight of 647 (1.2%) in fruits. Our study confirmed that the internal radiation doses of ingesting these foods are acceptably low compared to the public dose limit, ranging from 24.4 to 42.7 μSv for males and from 21.7 to 43.4 μSv for females, although the potential for radiation exposure still exists. Long-term comprehensive follow-up should take place to clarify trends in radiocesium concentrations in local foods and the committed effective doses found in Fukushima-area residents. By constructing a system that allows residents to access information on radiocesium concentration in foods, a risk communication model between specialists and residents could be developed in the recovery phase after the Fukushima accident.

  6. Development of a new aerosol monitoring system and its application in Fukushima nuclear accident related aerosol radioactivity measurement at the CTBT radionuclide station in Sidney of Canada

    Energy Technology Data Exchange (ETDEWEB)

    Zhang Weihua, E-mail: weihua.zhang@hc-sc.gc.ca [Radiation Protection Bureau, Health Canada, 775 Brookfield Road, Ottawa, Ontario, K1A 1C1 (Canada); Bean, Marc; Benotto, Mike; Cheung, Jeff; Ungar, Kurt; Ahier, Brian [Radiation Protection Bureau, Health Canada, 775 Brookfield Road, Ottawa, Ontario, K1A 1C1 (Canada)

    2011-12-15

    A high volume aerosol sampler ('Grey Owl') has been designed and developed at the Radiation Protection Bureau, Health Canada. Its design guidance is based on the need for a low operational cost and reliable sampler to provide daily aerosol monitoring samples that can be used as reference samples for radiological studies. It has been developed to provide a constant air flow rate at low pressure drops ({approx}3 kPa for a day sampling) with variations of less than {+-}1% of the full scale flow rate. Its energy consumption is only about 1.5 kW for a filter sampling over 22,000 standard cubic meter of air. It has been demonstrated in this Fukushima nuclear accident related aerosol radioactivity monitoring study at Sidney station, B.C. that the sampler is robust and reliable. The results provided by the new monitoring system have been used to support decision-making in Canada during an emergency response. - Highlights: > A new high volume aerosol sampler ('Grey Owl') has been developed in this study. > It operates at low pressure drops with low energy consumption. > The variation of air flow rate is less than {+-}1% of the full scale. > Fukushima accident nuclide monitoring at Sidney shows that it is robust and reliable.

  7. INTERNAL DOSES OF THREE PERSONS STAYING 110 KM SOUTH OF THE FUKUSHIMA DAIICHI NUCLEAR POWER STATION DURING THE ARRIVAL OF RADIOACTIVE PLUMES BASED ON DIRECT MEASUREMENTS.

    Science.gov (United States)

    Kurihara, Osamu; Nakagawa, Takahiro; Takada, Chie; Tani, Kotaro; Kim, Eunjoo; Momose, Takumaro

    2016-09-01

    The authors describe the results of direct measurements made on three persons who stayed in Tokai-mura, a village located ∼110 km south of the Fukushima Daiichi Nuclear Power Station (FDNPS), during the arrival of significant radioactive plumes released from the FDNPS as a consequence of the Tohoku earthquake/tsunami/FDNPS accident in March 2011. These measurements were made using a NaI(Tl) spectrometer and a whole-body counter shortly after the accident. Their thyroid equivalent doses ((131)I) were estimated to be 0.9-1.4 mSv under the assumption of acute intake via inhalation on 15 March, when the first significant release event was observed. Although greatly depending on the physicochemical form of iodine, the intake amount ratios of (131)I to (137)Cs for the three subjects were calculated as 2.7-3.7, which were much smaller than the radioactivity ratio (7.8) found in air sampling at the same site.

  8. Development of a new aerosol monitoring system and its application in Fukushima nuclear accident related aerosol radioactivity measurement at the CTBT radionuclide station in Sidney of Canada.

    Science.gov (United States)

    Zhang, Weihua; Bean, Marc; Benotto, Mike; Cheung, Jeff; Ungar, Kurt; Ahier, Brian

    2011-12-01

    A high volume aerosol sampler ("Grey Owl") has been designed and developed at the Radiation Protection Bureau, Health Canada. Its design guidance is based on the need for a low operational cost and reliable sampler to provide daily aerosol monitoring samples that can be used as reference samples for radiological studies. It has been developed to provide a constant air flow rate at low pressure drops (∼3 kPa for a day sampling) with variations of less than ±1% of the full scale flow rate. Its energy consumption is only about 1.5 kW for a filter sampling over 22,000 standard cubic meter of air. It has been demonstrated in this Fukushima nuclear accident related aerosol radioactivity monitoring study at Sidney station, B.C. that the sampler is robust and reliable. The results provided by the new monitoring system have been used to support decision-making in Canada during an emergency response.

  9. Trajectories of radioactive materials after the nuclear leakage in Fukushima Nuclear Power Station in Japan%日本福岛第一核电站核泄漏后放射性物质运动轨迹

    Institute of Scientific and Technical Information of China (English)

    岑况; 陈媛; 刘舒波; 于扬

    2012-01-01

    Magnitude 9.0 earthquake occurred in Coastal waters of northern Japan on March 11,2011,triggered a succession of disasters and led to nuclear leakage in Fukushima Nuclear Power Station.The level of this nuclear accident raised from 5 to 7(the highest level of nuclear accidents).The spread and migration of radioactive materials after the nuclear leakage is the focus and a hot spot in nuclear accidents.HYSPLIT model is used to simulate radioactive materials' trajectories after the nuclear leakage.The results show that atmospheric particulates with radioactive materials mainly move to the east and northeast over the Pacific,and even enter the United States.Sometimes they represent southward and turn to southwest trajectories or movement tendencies making them to move into China.Radioactive materials' trajectories in the next four months,May to August,are speculated by historical meteorological information,and air dispersion from Fukushima is mainly northward,northeast and west directions.Due to factors such as atmospheric turbulence,wind direction,rainfall,ocean current and so on,radioactive materials will still have influence in China.Atmospheric particulates with radioactive material into China mostly come from high altitude.%日本北部近海于2011年3月11日发生里氏9.0级地震,导致福岛第一核电站发生一连串事故并引发了核泄漏。日前此次核事故级别由事发后定的5级提至7级(核事故最高级别),核泄漏后放射性物质的扩散与迁移是目前关于核事故研究的热点之一。利用HYSPLIT模型模拟核爆炸后空气中放射性物质的运动轨迹发现核大气颗粒物主要运移方向为东和东北方向,进入太平洋上空,甚至美国境内,亦有朝南转西南运移的轨迹与趋势,使得放射性物质进入中国上空。根据历史气象资料对接下来的5—8月份大气颗粒物的运动轨迹进行预测,分析结果显示放射性物质随后可能往

  10. The activity of radiocaesium in sediments around off Fukushima after the accident of TEPCO's Fukushima Dai-ich Nuclear Power Station.

    Science.gov (United States)

    Fukuda, Miho; Aono, Tatsuo; Yoshida, Satoshi; Naganuma, Sho; Kubo, Atsushi; Ito, Yukari; Ishimaru, Takashi; Kanda, Jota

    2014-05-01

    The 2011 off the Pacific coast of Tohoku Earthquake and tsunami on March 11, 2011 have led to the accident of TEPCO's Fukushima Dai-ich Nuclear Power Station (FNPS) and large amount of radioactive material were discharged by the hydrogen explosion and leaked from FNPS to the ocean. About three years have passed after the accident, radiocaesium in seawater off Fukushima except for part of area is gradually decreasing to the level before the accident. However, because the decrease of radiocaesium in marine sediment is more slowly than that in seawater, it is worried to influence on marine biota dwelled around the seabed over the long term. The aim of this study was to elucidate the variation and behavior of radiocaesium (134Cs and 137Cs) activities in the marine environment. Sediment and seawater samples were collected from three sites in 5 km-20 km area from FNPS (NP2 site ; 37° 25 N, 141°06 E, water depth 30 m, AN6 site ; 37° 33 N, 141°07 E, water depth 30 m, and M01 site ; 37° 33 N, 141°20 E, water depth 60 m) in May and October 2013 during some cruise of Umitaka-maru and Shinyo-maru (Tokyo University of Marine and Technology) .Vertical changes of 134Cs concentration (Bq/kg-dry) in sediment ranged 17-28, 8.2-53, and 4.2-11 at NP2, AN6 and M01 sites as of May 2013, respectively. At NP2 site, 134Cs inventory (Bq/m2) in seawater in October was about four times higher than that of 134Cs inventory in May. At NP2 and M01 sites in May, 134Cs concentration was higher in the shallow layer (0 cm-1 cm). On the contrary, at AN6 site in May and NP2 site in October, 134Cs concentration was higher in the middle layer (4 cm-5 cm). Trend of organic content at all stations were consistent with that of vertical change of 134Cs concentration. These results suggest that highest radiocaesium layer in the shallow as well as in the middle depth was caused by increase of river input and resedimentation.

  11. 核电站主回路系统主要设备的射线透照工艺%Radiographic Process for Main Equipment of Nuclear Power Station Primary System in Radiographic Testing

    Institute of Scientific and Technical Information of China (English)

    华雄飞; 毛羽飞; 张铁辉; 李金强; 梅义俊; 刘顺

    2012-01-01

    Primary system of nuclear power station is the main examination object of radiographic testing in PSI/ ISI. Starting with radiography process in radiographic testing, radiography process and implementation of main equipment as steam generator ( SG ), reactor pressure vessel ( RPV ) and pressurizer ( PRZ ) were introduced quite systematic in primary system of nuclear power station. Radiographic special tools used in each exposure were presented also. Based on the successful experience of pre-service inspection in Ling'ao No. 3 and 4 nuclear power station, foundation is laid for the PSI/ISI later.%核电站主回路系统是核电站役前/在役检查的主要检测对象,从射线检测透照工艺入手,系统地介绍了核电站主回路系统主要设备蒸汽发生器SG、反应堆压力容器RPV以及稳压器PRZ的透照方式及实施方法,并对各透照中所使用的专用工具架做了介绍。以岭澳核电站3,4号机组役前检查顺利完成的实际经验为依托,为以后役前/在役检查打下基础。

  12. Prediction and modeling of the two-dimensional separation characteristic of a steam generator at a nuclear power station with VVER-1000 reactors

    Science.gov (United States)

    Parchevsky, V. M.; Guryanova, V. V.

    2017-01-01

    A computational and experimental procedure for construction of the two-dimensional separation curve (TDSC) for a horizontal steam generator (SG) at a nuclear power station (NPS) with VVER-reactors. In contrast to the conventional one-dimensional curve describing the wetness of saturated steam generated in SG as a function of the boiler water level at one, usually rated, load, TDSC is a function of two variables, which are the level and the load of SGB that enables TDSC to be used for wetness control in a wide load range. The procedure is based on two types of experimental data obtained during rated load operation: the nonuniformity factor of the steam load at the outlet from the submerged perforated sheet (SPS) and the dependence of the mass water level in the vicinity of the "hot" header on the water level the "cold" end of SG. The TDSC prediction procedure is presented in the form of an algorithm using SG characteristics, such as steam load and water level as the input and giving the calculated steam wetness at the output. The zoneby-zone calculation method is used. The result is presented in an analytical form (as an empirical correlation) suitable for uploading into controllers or other controls. The predicted TDSC can be used during real-time operation for implementation of different wetness control scenarios (for example, if the effectiveness is a priority, then the minimum water level, minimum wetness, and maximum turbine efficiency should be maintained; if safety is a priority, then the maximum level at the allowable wetness and the maximum water inventory should be kept), for operation of NPS in controlling the frequency and power in a power system, at the design phase (as a part of the simulation complex for verification of design solutions), during construction and erection (in developing software for personnel training simulators), during commissioning tests (to reduce the duration and labor-intensity of experimental activities), and for training.

  13. Evaluation of a main steam line break with induced, multiple tube ruptures: A comparison of NUREG 1477 (Draft) and transient methodologies Palo Verde Nuclear Generating Station

    Energy Technology Data Exchange (ETDEWEB)

    Parrish, K.R.

    1995-09-01

    This paper presents the approach taken to analyze the radiological consequences of a postulated main steam line break event, with one or more tube ruptures, for the Palo Verde Nuclear Generating Station. The analysis was required to support the restart of PVNGS Unit 2 following the steam generator tube rupture event on March 14, 1993 and to justify continued operation of Units 1 and 3. During the post-event evaluation, the NRC expressed concern that Unit 2 could have been operating with degraded tubes and that similar conditions could exist in Units 1 and 3. The NRC therefore directed that a safety assessment be performed to evaluate a worst case scenario in which a non-isolable main steam line break occurs inducing one or more tube failures in the faulted steam generator. This assessment was to use the generic approach described in NUREG 1477, Voltage-Based Interim Plugging Criteria for Steam Generator Tubes - Task Group Report. An analysis based on the NUREG approach was performed but produced unacceptable results for off-site and control room thyroid doses. The NUREG methodology, however, does not account for plant thermal-hydraulic transient effects, system performance, or operator actions which could be credited to mitigate dose consequences. To deal with these issues, a more detailed analysis methodology was developed using a modified version of the Combustion Engineering Plant Analysis Code, which examines the dose consequences for a main steam line break transient with induced tube failures for a spectrum equivalent to 1 to 4 double ended guillotine U-tube breaks. By incorporating transient plant system responses and operator actions, the analysis demonstrates that the off-site and control room does consequences for a MSLBGTR can be reduced to acceptable limits. This analysis, in combination with other corrective and recovery actions, provided sufficient justification for continued operation of PVNGS Units 1 and 3, and for the subsequent restart of Unit 2.

  14. Control rod cluster drop time anomaly Guandong nuclear power station (Daya bay) and Electricite de France nuclear power stations (1450 MWe N4 Series); Anomalie de temps de chute des grappes de controle centrale de guang dong (daya bay) et centrales d`electricite de France (Palier N4-1450 MWE)

    Energy Technology Data Exchange (ETDEWEB)

    Olivera, J.J.; Naury, S.; Tricot, N.; Tran Dai, P.; Gama, J.M.

    1996-12-31

    The anomaly of control rod cluster drop time revealed at Guandong Nuclear Power Station in Daya Bay and in the Chooz B1 pilot unit for the N4 series, led to the replacement of the M1 type control rod cluster guide tubes with 1300 MWe PWR type guide tubes, adapted to the geometry of the Guandong reactors and the 1450 MWe reactors of the N4 series. The comparison of the drop times obtained with the 1300 MWe type control rod cluster guide 1300 MWe type control rod cluster guide tubes gave satisfactory results. These met the safety criterion for N4 series control rod cluster drop times (2.15 under hot shutdown conditions). The drop time tests which will be carried out in middle of and at the end of cycle 1 of Chooz B1 should make it possible to finally validate the solution already successfully implemented at Guandong. However, this anomaly has revealed the limits of representativeness of the experimental test loops with regard to the real reactor configuration. In view of this, it has been deemed necessary to ask Electricite de France to pursue its analysis both on the understanding of the phenomena which led to this anomaly and on the limits of the representativeness of the experimental test loops. (authors).

  15. 虚拟现实技术在核电站在役检查管理系统中的应用%Application of virtual reality to in-service inspection management system for a nuclear power station

    Institute of Scientific and Technical Information of China (English)

    周国正; 张学粮; 颜安和

    2013-01-01

      In order to explore the application of virtual reality technology in in-service inspection management system for a nuclear power station, by using the software EON Studio7.0 as the carrier, the emphasis is laid on the solutions to 3D model file conversion, interactive control technology and model optimization, etc., achieving the display of nuclear power station equipment, information feedback and link of drawings, etc. The application of virtual reality technology plays an active role in assuring equipment security and personnel security of a nuclear power plant.%  为了探究虚拟现实技术在核电站在役检查管理系统中的功能应用,以 EON Studio7.0软件为载体,重点研究三维模型文件转换、交互控制技术与模型优化等关键问题的解决方案,实现了核电站设备展示,信息反馈与图纸链接等功能.虚拟现实技术的应用将在保障核电站设备安全,人员安全方面起到积极作用.

  16. Nuclear power generation incorporating modern power system practice

    CERN Document Server

    Myerscough, PB

    1992-01-01

    Nuclear power generation has undergone major expansion and developments in recent years; this third edition contains much revised material in presenting the state-of-the-art of nuclear power station designs currently in operation throughout the world. The volume covers nuclear physics and basic technology, nuclear station design, nuclear station operation, and nuclear safety. Each chapter is independent but with the necessary technical overlap to provide a complete work on the safe and economic design and operation of nuclear power stations.

  17. Distributions of Pu isotopes in seawater and bottom sediments in the coast of the Japanese archipelago before and soon after the Fukushima Dai-ichi Nuclear Power Station accident.

    Science.gov (United States)

    Oikawa, Shinji; Watabe, Teruhisa; Takata, Hyoe

    2015-04-01

    A radioactivity measurement survey was carried out from 24 April 2008 to 3 June 2011 to determine the levels of plutonium isotopes and (240)Pu/(239)Pu atom ratios in the marine environments off the sites of commercial nuclear power stations around the Japanese islands; the sampling period extended to two months after the Fukushima Dai-ichi Nuclear Power Station accident. In our previous study (Oikawa et al., 2015), data on Pu isotopes and (241)Am in sediments have already been reported. In this study, we report those on Pu isotopes in seawater as well as sediments, and the characteristics of sediments in addition (e.g., ignition loss and biogenic opals). Concentrations of (239+240)Pu in seawater and bottom sediments remained nearly constant at all sampling locations during the survey period. In addition, no regional differences were observed in the (239+240)Pu concentrations in surface waters. Higher (239+240)Pu concentrations were found in bottom waters at deeper sampling locations, but the (240)Pu/(239)Pu atom ratios were nearly constant regardless of the water depth. Higher (239+240)Pu concentrations were also found in bottom sediments at deeper sampling locations, but vice versa for (240)Pu/(239)Pu atom ratios as reported in the previous report. The sediments samples from deeper locations showed the higher percentage of ignition loss as well as the higher content of biogenic opal. There was likely to be some driving force participating in the transfer of Pu isotopes associated with biogenic substances to the deeper seabed. The present survey showed that the accident at the Fukushima Dai-ichi Nuclear Power Station did not contribute much to the inventory of Pu isotopes in the adjacent sea area.

  18. 核电厂远程停堆站事故准则的标准研究%Study on the Standard for Accident Criteria of Remote Shutdown Station of Nuclear Power Plant

    Institute of Scientific and Technical Information of China (English)

    程波; 梅世柏; 周毅超; 张建波; 邹杰

    2015-01-01

    In the event that the safety functions determined by safety analysis cannot be conducted in main control room of nuclear power plant, the operators have to withdraw to the remote shutdown station for limited controlling and monitoring of the plant. Aimed at such situation, the accident situation of the nuclear power plant must to be considered. Related standards and regulations at home and abroad are analyzed and researched comprehensively, and the design criteria of the accidents to be handled in remote shutdown station are determined. The suggestions and comments for revising the standards and regulations of our country are proposed. The researching achievements provide guidance for designing remote shutdown station of subsequent nuclear power plants.%当核电厂主控制室失去完成由安全分析所确定的安全功能时,运行人员撤离到远程停堆站对核电厂进行有限控制和监测.针对主控制室不可用、需要转移到远程停堆站时需要考虑的核电厂事故情况,对国内外相关法规标准进行了全面分析研究,确定了核电厂远程停堆站的事故设计原则,并提出了国内相关标准的升版建议和意见. 研究成果为后续核电厂远程停堆站设计提供了指导.

  19. Space Station

    Science.gov (United States)

    Anderton, D. A.

    1985-01-01

    The official start of a bold new space program, essential to maintain the United States' leadership in space was signaled by a Presidential directive to move aggressively again into space by proceeding with the development of a space station. Development concepts for a permanently manned space station are discussed. Reasons for establishing an inhabited space station are given. Cost estimates and timetables are also cited.

  20. Psychological distress of residents in Kawauchi village, Fukushima Prefecture after the accident at Fukushima Daiichi Nuclear Power Station: the Fukushima Health Management Survey

    Directory of Open Access Journals (Sweden)

    Koji Yoshida

    2016-08-01

    Full Text Available Background To shed light on the mental health of evacuees after the accident at Fukushima Daiichi Nuclear Power Station (FDNPS, we evaluate the results of the Fukushima Health Management Survey (FHMS of the residents at Kawauchi village in Fukushima, which is located less than 30 km from the FDNPS. Methods We conducted the cross-sectional study within the framework of the FHMS. Exposure values were “anorexia,” “subjective feelings about health,” “feelings about sleep satisfaction,” and “bereavement caused by the disaster,” confounding variables were “age” and “sex,” and outcome variables were “K6 points.” We collected data from the FHMS, and employed the Kessler Psychological Distress Scale (K6 and the posttraumatic stress disorder (PTSD Checklist Stressor-Specific Version (PCL-S to carry out the research. A total of 13 or greater was the cut-off for identifying serious mental illness using the K6 scale. The study subjects included residents (n = 542 of over 30 years of age from Kawauchi village, and data were used from the period of January 1, 2012 to October 31, 2012. Results A total of 474 residents (87.5% scored less than 13 points in the K6 and 68 (12.6% scored 13 points or more. The proportion of elderly residents (over 65 years old among people with K6 score above the cut-off was higher than that among people with K6 score below the cut-off (44.1 vs 31.0%, p < 0.05. In addition, the proportion of residents with anorexia and mental illness among people with K6 score above the cut-off was higher than among people with K6 score below the cut-off (p < 0.001 and p < 0.05, respectively. The amount of residents who scored 44 points or more in the PCL-S among people with K6 score above the cut-off was also considerably higher than among people with K6 score below the cut-off (79.4 vs 12.9%, p < 0.001. Interestingly, the proportion of residents who scored more than among people with K6 score above the cut-off and the

  1. 从日本福岛事件看核电站危机应对机制的建构%The study about construction of the nuclear power station crisis response mechanism from the Fisland crisis

    Institute of Scientific and Technical Information of China (English)

    石先钰; 白森文

    2012-01-01

    2011年3月11日,日本东北部宫城县以东太平洋海域发生里氏9.0级地震,引发巨大海啸,福岛核电站1、2、3、4号机组接连发生事故,如果说地震和海啸引起了人们关注的眼光,那么更加让全世界震惊的则是福岛核电站的爆炸。本应在自然环境中“雷打不动”的核电站,为何会出现可怕的核泄漏?福岛事件给日本民众乃至全世界带来了怎样的灾难,对整个核电产业的发展又带来了怎样的影响?在出现核电站危机时,人们该怎样去应对?本文重点分析核电站危机应对机制的基本原则以及相应的制度安排。%On March 11,2011 ,a magnitude 9.0 degree earthquake occurred in the Pacific waters of northeastern of Japan GongCheng County which also led to huge tsunami,and therefore there were continuous accidents in the Fukushima Nuclear Power Plant 1,2,3 and 4 Units. If the earthquake and tsunami caused people' s attention,what made the whole world more shocked was the explosions of the Fukushima nuclear power station. Why did Nuclear leakage happened at Nuclear power stations which should have not been altered un- der any circumstances? What disasters did fukushima island event bring to the Japanese public and the whole world,and even to the de- velopmentof the nuclear power industry,9 In the crisis of nuclear power plants,what should people deal with9 This paper focuses on the analysis of basic principle and the corresponding system arrangement of the nuclear crisis response mechanism.

  2. Station Capacity

    DEFF Research Database (Denmark)

    Landex, Alex

    2011-01-01

    Stations are often limiting the capacity of railway networks. This is due to extra need of tracks when trains stand still, trains turning around, and conflicting train routes. Although stations are often the capacity bottlenecks, most capacity analysis methods focus on open line capacity. Therefore......, this paper presents methods to analyze station capacity. Four methods to analyze station capacity are developed. The first method is an adapted UIC 406 capacity method that can be used to analyze switch zones and platform tracks at stations that are not too complex. The second method examines the need...... for platform tracks and the probability that arriving trains will not get a platform track immediately at arrival. The third method is a scalable method that analyzes the conflicts in the switch zone(s). In its simplest stage, the method just analyzes the track layout while the more advanced stages also take...

  3. Dynamic analysis of the condensate and of the feed water in the Laguna Verde nuclear power station; Analisis dinamico del sistema de condensado y agua de alimentacion de la nucleoelectrica de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Macedo Muth, Javier; Sandoval Pena, Ramon [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1988-12-31

    This article shows a non-lineal mathematical model for the condensate, and feed water systems and for feed water heater drains at the Laguna Verde Nuclear Power Station for its simulation in real time. The model allows the calculation of flows and pressures in all the piping system and equipment that integrate the systems. It was obtained by using the force unbalance in the fluid concept and is capable of reproducing its dynamic behavior through variations induced by the different operation modes and more common failures. The final model objective is to form part of the Laguna Verde simulator that will be used for operator training of this Nuclear Power Plant. [Espanol] En este articulo se muestra un modelo matematico no lineal de los sistemas de condensado, agua de alimentacion y drenes de calentadores de la central nuclear de Laguna Verde para su simulacion en tiempo real. El modelo permite calcular los flujos y las presiones en toda la red de tuberias y equipos que integran los sistemas. Se obtuvo utilizando el concepto de desbalance de fuerzas en el fluido, y es capaz de reproducir su comportamiento dinamico ante variaciones inducidas por los diversos modos de operacion y fallas mas comunes. El objetivo final del modelo es formar parte del simulador de Laguna Verde que se empleara para el adiestramiento de los operadores de dicha central nuclear.

  4. 52 years of Kahl pilot nuclear power station. A special chapter in German technology history come to an end; 52 Jahre Versuchsatomkraftwerk Kahl. Ein besonderes Kapitel deutscher Technikgeschichte ist zu Ende

    Energy Technology Data Exchange (ETDEWEB)

    Hackel, Walter [VAK GmbH, Karlstein am Main (Germany)

    2011-06-15

    Since October 2010, the site of the former Kahl Experimental Nuclear Power Station (VAK) has been returned to the desired green-field condition. A special chapter in the German history of the use of nuclear power, which has played a major role in the technical and economic development of this energy resource, has come to an end after 52 years. When nuclear power pioneer Heinrich Mandel ordered VAK from AEG in 1958, the mood associated with using this source of energy was different from what it is now. Politicians of all parties were euphoric about the use of nuclear power, while power plant operators were more reluctant. Finally, also RWE was convinced and planned the construction of VAK as a joint venture with the Bayernwerk AG (now E.ON) utility in Grosswelzheim, Bavaria. The objective was clear: 'The order was placed so that the atomic power plant to be built could be used to accumulate experience in planning, operation, in capital cost and operating cost.' After a construction period of only 29 months, VAK was commissioned on November 13, 1960 as the first German nuclear power plant. The US-designed boiling water reactor had been designed for a power of 16,000 kilowatt. After synchronization with the power grid, the first electricity produced from nuclear power in Germany was fed into the interconnected grid system on June 17, 1961. In its 25 years of operation, VAK proved to be a valuable experimental facility. The plant was decommissioned on November 25, 1985 as planned. In order to maintain its experimental character also beyond the operating phase, the operators had agreed from the beginning to demolish VAK completely to green-field conditions immediately after the end of operations. This became official on May 17, 2010, when the plant was released from the scope of the Atomic Energy Act and was granted a permit for demolition under conventional building law. (orig.)

  5. Design of the System of Maintenance Operations Occupational Safety and Health Database Application of Nuclear Power Station%核电站维修作业职业安全健康数据库应用系统设计

    Institute of Scientific and Technical Information of China (English)

    王学洪; 李向阳; 叶勇军

    2011-01-01

    Based on the KKS code of building equipment in nuclear power station,this paper introduces the method of establishing the system of maintenance operation occupational safety and health database application. Through the application system of maintenance occupational safety and health database, it can summarize systematically all kinds of maintenance operation dangerous factor of nuclear power station,and make a convenience for staff to learn the maintenance operation dangerous factors and the prevention measures,so that it can achieve the management concept of "precaution crucial,continuous improvement"that advocated by OSHMS.%以核电站厂房设备KKS编码等为基础,建立维修作业职业安全健康数据库应用系统.通过维修作业职业安全数据库应用系统,可以系统地归纳核电站各类维修作业危险危害因素,方便员工在作业前查询学习维修作业危险危害因素及防范措施;达到OSHMS所倡导的“预防为主、持续改进”的管理理念.

  6. Optimized design of chilled water system of transit changing room in nuclear power station%核电厂更衣室冷冻水系统优化设计

    Institute of Scientific and Technical Information of China (English)

    苏兵; 张凤阁; 刘占盛; 韩玮

    2011-01-01

    针对在建核电厂的更衣室冷冻水系统,通过计算分析,并结合工程实践经验,对原有设计进行了优化和改进.总结出适用于核电厂冷冻水系统设计的有用结论,包括:系统供回水温度的适当调整、气源热泵技术的有效利用以及模块化冷水机组的合理引入.这些结论目前均已有效地应用于在建核电项目的施工设计中,同时,对于国内其他行业内的冷冻水系统设计也提供了借鉴和参考.%Based on the basis of analysis, calculation and engineering experience, we optimized the chilled water system of transit changing room in nuclear power station. Furthermore, we could get certain useful conclusions including modification of temperature of in - and - out water, usage of air source heat pump technique, modularization of water chiller. The conclusions were all applied in the construction design of the latest nuclear power stations. This article can provide some references to chilled water system design in other areas in China.

  7. 岭澳核电站CFI系统雷达液位计的原理和操作%Ling ao nuclear power station CFI system the principle of radar level gauge and operations

    Institute of Scientific and Technical Information of China (English)

    陈罡

    2015-01-01

    岭澳核电站CFI系统原使用超声波水位测量仪,总是因潮湿、天气及泡沫等因素的影响导致故障闪发,状态不是很稳定,所以将其改造为雷达式液位计。本文就岭澳核电站CFI系统的雷达式液位计的原理、特点和操作方法进行简要论述。%The CFI system of Ling Ao nuclear power station the original use of ultrasonic level measurement instrument is always affected by wet weather and other factors,the bubble causes the failure of flash,the state is not very stable,so its transformation for the radar level gauge.The principle, characteristic and operation method of this paper is the radar type level of Ling Ao Nuclear Power Station CFI system tester are briefly discussed.

  8. Generation Mechanism of Human Errors and Preventive Countermeasures in Nuclear Power Stations%核电站人因失误的产生机理及其预防措施

    Institute of Scientific and Technical Information of China (English)

    张言滨

    2011-01-01

    在核电站的人-机系统中,核电站特有的运行控制特征使得人因失误事件的发生概率很大,如何预防与减少人因失误,提高人的可靠性已成为保证核电安全生产的主要因素.研究了人因失误的特点,通过总结核电站人因失误事件的产生机理,给出了预防核电站人因失误的有效措施.%In the person -machine system of a nuclear power station, the unique operating control characteristics of the station increase probability of human failure events. How to prevent from and reduce human errors have become the primary factor in nuclear power safety producUon. This paper studied the characteristics of human errors, and through summarizing of generation mechanism of human failure events, and proposed some effective prevention measures.

  9. 百万级压水堆核电站空冷汽轮机选型研究%Calculation and Selecting of Air-cooled Turbine in 1 000 MW PWR Nuclear Power Station

    Institute of Scientific and Technical Information of China (English)

    杨建军; 孙传军; 赵迪

    2015-01-01

    针对国内某核电厂址的初步气象条件,进行了百万等级核电机组空冷汽轮机选型计算分析。分析结果表明,该厂址参数下若选用半转速核电汽轮机,目前已有的末级叶片不能满足要求,需要开发全新的空冷末级叶片;而利用大型火电空冷汽轮机已有运行业绩的末级叶片,开发全转速百万级核电空冷汽轮机,将花费较少的时间和经费,是比较适宜的方案。某厂址气象条件在我国北方具有代表性,上述工作为我国北方缺水地区核电站汽轮机选型提供了参考。建议国内汽轮机厂利用已有核电、火电汽轮机技术积累,尽快启动全转速百万级核电空冷汽轮机研发工作,形成具有完全自主知识产权的百万级核电空冷汽轮机技术,抢占技术制高点。%By analyzing the weather characters of one potential 1000MW nuclear power station site ,this paper calculated the air-cooled steam turbine exhausting area .It is concluded that the present last long blade used in half-speed turbine is not suitable,new last long blade shall be developed if we want to use half-speed turbine in 1 000MW air-cooled nuclear power station.However,the full-speed turbines and their last long blades used in coal burning power station are appropriate for this site,excepting plus one low pressure turbine and some measures to remove moisture steam in the last stage .The latter is better,for it will cost less money and time .The site mentioned in this paper is representive in China north area ,and this paper is useful for turbine selecting of nuclear power station in this area .Domestic turbine manufacturers have accumulated many experiences and technologies by manufacturing and developing half -speed nuclear turbine and air-cooled full-speed turbines in coal burning power station .It is suggested the domestic turbine manufacturers should setup the research work as soon as possible .

  10. Análisis de la respuesta estructural del edificio de contención de un reactor nuclear PWR frente a una secuencia de Station Blackout

    OpenAIRE

    2013-01-01

    Después del Accidente que sucedió el 11 de marzo de 2011 en la central nuclear de Daichii-Fukushima, han sido muchos los debates reabiertos acerca de la seguridad que ofrecen los reactores nucleares en operación. Debido a las incertidumbres que este accidente ha suscitado, surge ésta tesina, en la que se pretende conocer y comprender técnicamente que sucedería si un accidente similar al de Fukushima ocurriese en uno de los reactores de nuestro país. Con el principal objetivo de encontrar res...

  11. Nuclear questions

    Energy Technology Data Exchange (ETDEWEB)

    Durrani, M. [Physics World (United Kingdom)

    2006-01-01

    The future of nuclear power has returned to centre stage. Freezing weather on both sides of the Atlantic and last month's climate-change talks in Montreal have helped to put energy and the future of nuclear power right back on the political agenda. The issue is particularly pressing for those countries where existing nuclear stations are reaching the end of their lives. In the UK, prime minister Tony Blair has commissioned a review of energy, with a view to deciding later this year whether to build new nuclear power plants. The review comes just four years after the Labour government published a White Paper on energy that said the country should keep the nuclear option open but did not follow this up with any concrete action. In Germany, new chancellor and former physicist Angela Merkel is a fan of nuclear energy and had said she would extend the lifetime of its nuclear plants beyond 2020, when they are due to close. However, that commitment has had to be abandoned, at least for the time being, following negotiations with her left-wing coalition partners. The arguments in favour of nuclear power will be familiar to all physicists - it emits almost no carbon dioxide and can play a vital role in maintaining a diverse energy supply. To over-rely on imported supplies of oil and gas can leave a nation hostage to fortune. The arguments against are equally easy to list - the public is scared of nuclear power, it generates dangerous waste with potentially huge clean-up costs, and it is not necessarily cheap. Nuclear plants could also be a target for terrorist attacks. Given political will, many of these problems can be resolved, or at least tackled. China certainly sees the benefits of nuclear power, as does Finland, which is building a new 1600 MW station - the world's most powerful - that is set to open in 2009. Physicists, of course, are essential to such developments. They play a vital role in ensuring the safety of such plants and developing new types of

  12. The problem of optimizing the water chemistry used in the primary coolant circuit of a nuclear power station equipped with VVER reactors under the conditions of longer fuel cycle campaigns and increased capacity of power units

    Science.gov (United States)

    Sharafutdinov, R. B.; Kharitonova, N. L.

    2011-05-01

    It is shown that the optimal water chemistry of the primary coolant circuit must be substantiated while introducing measures aimed at increasing the power output in operating power units and for the project called AES-2006/AES TOI (a typical optimized project of a nuclear power station with enhanced information support). The experience gained from operation of PWR reactors with an elongated fuel cycle at an increased level of power is analyzed. Conditions under which boron compounds are locally concentrated on the fuel rod surfaces (the hideout phenomenon) and axial offset anomaly occurs are enlisted, and the influence of lithium on the hideout in the pores of deposits on the surfaces of fuel assemblies is shown.

  13. On a Special Fixation of a Fire Alarming System in a Nuclear Station%谈核电站火灾自动报警系统的特殊配置

    Institute of Scientific and Technical Information of China (English)

    邹田荣

    2012-01-01

    结合核电站火灾危险的特殊性,阐述了核电站常规岛中网控楼、蓄电池室、汽轮机厂房、电缆隧道、输变电变压器等建筑的火灾自动报警系统设备的特殊配置及选用特点,以发挥火灾自动报警系统的监控作用。%This paper explains the unique characteristics of a fire risk in a nuclear station in terms of its normal centre control building,a battery room turbulent plant and wire tunnels and power transformers to make the better use of fire automatic alarm system.

  14. The nuclear techniques in function of improving the efficiency of the flocculators and floats in the industrial waste treatment station of PETROBRAS; Las tecnicas nucleares en funcion de mejorar la eficiencia de los floculadores y los flotadores de la estacion de tratamiento de desechos industriales en PETROBRAS

    Energy Technology Data Exchange (ETDEWEB)

    Damera Martinez, Arnaldo; Ramos Espinosa, Kenia A. [Centro de Atencion a la Actividad Nuclear, Camaguey (Cuba)]. E-mail: damera@caonao.cmw.inf.cu; Pinto, Amenonia Ferreira; Barbalho, Andrea de Magalhaes [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Belo Horizonte, MG (Brazil); Derivet Zarzabal, Milagros [Instituto Cubano de Investigaciones Azucareras, La Habana (Cuba)

    2001-07-01

    This work was carried out in the Station of Treatment of Industrial Waste (STIW) in PETROBRAS (Brazil). The STIW has the function of receiving, to treat and storage liquid wastes coming from diverse points of the refinery, avoiding the environment contamination. This study consists on the determination of the time of residence inside the flocculators and floats, by means of nuclear technique of radioactive tracer, using Tc-99m. This technique has a great economic and environmental importance because the time of residence obtained experimentally in the flocculators and the floats, can be compared with those obtained theoretically, which allow to influence on the system, optimizing its operation.

  15. Analysis of internal events for the Unit 1 of the Laguna Verde nuclear power station; Analisis de eventos internos para la Unidad 1 de la Central Nucleolelectrica de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Huerta B, A.; Aguilar T, O.; Nunez C, A.; Lopez M, R. [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

    1993-07-01

    This volume presents the results of the starter event analysis and the event tree analysis for the Unit 1 of the Laguna Verde nuclear power station. The starter event analysis includes the identification of all those internal events which cause a disturbance to the normal operation of the power station and require mitigation. Those called external events stay beyond the reach of this study. For the analysis of the Laguna Verde power station eight transient categories were identified, three categories of loss of coolant accidents (LOCA) inside the container, a LOCA out of the primary container, as well as the vessel break. The event trees analysis involves the development of the possible accident sequences for each category of starter events. Events trees by systems for the different types of LOCA and for all the transients were constructed. It was constructed the event tree for the total loss of alternating current, which represents an extension of the event tree for the loss of external power transient. Also the event tree by systems for the anticipated transients without scram was developed (ATWS). The events trees for the accident sequences includes the sequences evaluation with vulnerable nucleus, that is to say those sequences in which it is had an adequate cooling of nucleus but the remoting systems of residual heat had failed. In order to model adequately the previous, headings were added to the event tree for developing the sequences until the point where be solved the nucleus state. This process includes: the determination of the failure pressure of the primary container, the evaluation of the environment generated in the reactor building as result of the container failure or cracked of itself, the determination of the localization of the components in the reactor building and the construction of boolean expressions to estimate the failure of the subordinated components to an severe environment. (Author)

  16. Polarographic determination of Iodide and Iodate, in Solutions Coming from Aerosols in Fission Products Containment Studies in Nuclear Power Stations; Determinacion Polarografica de Especies de Iodo (Ioduro y Iodato) en Soluciones Procedentes de Aerosoles, para Estudios de Contencion de Productos de Fision en Centrales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, M.; Ballesteros, O.; Fernandez, M.; Clavero, M.; Gonzalez, A. M. [Ciemat, Madrid (Spain)

    2000-07-01

    A polarographic method is described for the iodine species determination, iodide and iodate in water solutions. the iodate can be determined by differential pulse polarography. Calibration curves and the detection and determination limits have been obtained. Iodides is oxidized to iodate with sodium hypochlorite and the excess of oxidizing agent is destroyed with sodium sulphide. The concentration of iodide is calculated as the difference between the concentration of iodate in the sample before and after the oxidation. As an application, species of iodine in samples coming from the experimental plants GIRS (Gaseous Iodine Removal by Sprays) of Nuclear Fission Department of the CIEMAT, dedicated to fission products containment studies in nuclear power station, were determined. (Author) 10 refs.

  17. Imaging of high-Z material for nuclear contraband detection with a minimal prototype of a Muon Tomography station based on GEM detectors

    CERN Document Server

    Gnanvo, Kondo; Hohlmann, Marcus; Locke, Judson B; Quintero, Amilkar S; Mitra, Debasis

    2010-01-01

    Muon Tomography based on the measurement of multiple scattering of atmospheric cosmic ray muons in matter is a promising technique for detecting heavily shielded high-Z radioactive materials (U, Pu) in cargo or vehicles. The technique uses the deflection of cosmic ray muons in matter to perform tomographic imaging of high-Z material inside a probed volume. A Muon Tomography Station (MTS) requires position-sensitive detectors with high spatial resolution for optimal tracking of incoming and outgoing cosmic ray muons. Micro Pattern Gaseous Detector (MPGD) technologies such as Gas Electron Multiplier (GEM) detectors are excellent candidates for this application. We have built and operated a minimal MTS prototype based on 30cm \\times 30cm GEM detectors for probing targets with various Z values inside the MTS volume. We report the first successful detection and imaging of medium-Z and high-Z targets of small volumes (~0.03 liters) using GEM-based Muon Tomography.

  18. Population dose estimation from a hypothetical release of 2. 4 x 10/sup 6/ curies of noble gases and 1 x 10/sup 4/ curies of /sup 131/I at the Three Mile Island Nuclear Station, Unit 2

    Energy Technology Data Exchange (ETDEWEB)

    Berger, C.D.; Lane, B.H.; Cotter, S.J.; Miller, C.W.; Glandon, S.R.

    1981-09-01

    Beginning on March 28, 1979, a sequence of events occurred at the Three Mile Island Nuclear Station Unit 2 (TMINS-2) nuclear power reactor which resulted in the accidental release of approximately 2.4 x 10/sup 6/ Ci of noble gases and 13 to 15 Ci /sup 131/I. A comprehensive study of this incident has been reported by the President's Commission on the Accident at Three Mile Island. As part of this study, the Technical Assessment Task Group for the Commission addressed a series of alternative event scenarios, including the potential for a higher release of /sup 131/I. As a continuation of this task, this report presents the estimated collective dose to the population within 50 miles of TMINS-2 from a hypothetical release of 2.4 x 10/sup 6/ Ci of noble gases and 1 x 10/sup 4/ Ci /sup 131/I by the methodology of atmospheric dispersion modeling and population dose estimation through the inhalation, ingestion and immersion exposure pathways.

  19. 核电站机器人技术应用现状和发展%Application Status and Development of Robotics in Nuclear Power Station

    Institute of Scientific and Technical Information of China (English)

    周小倩

    2015-01-01

    With the development of economy, science and technology continuous update, remote control and automation technology in today's society is becoming more and more common, is widely used in people's production and life. The use of robots in the use, maintenance and inspection of nuclear power plants in some countries are working to improve the work efficiency and reduce the burden on the staff of the nuclear powerstation.%随着经济的发展,科学技术的不断更新,遥控以及自动化技术在当今社会越来越普遍,被广泛地应用于人们的生产生活中. 部分国家在核电站的使用、维修、检测中利用机器人来为其工作,在一定程度上提高了工作效率,减轻了核电站工作人员的工作负担.

  20. Installation and Commissioning of RCP Cartridge for Nuclear Power Stations%核电厂主泵密封系统的安装与调试

    Institute of Scientific and Technical Information of China (English)

    霍亚邦; 王玉旭

    2011-01-01

    The installation process and method for the cooling pump sealing system of CPR1000 nuclear power plant reactor is studied, and various cases occurred during the installation and commisioning of RCP sealing systems are analyzed. The scheme for flushing of the nuclear loop in the various cases is developed to provide a reference for the installation and commissioning of RCP sealing system in the coming CPR1000 project.%研究CPR1000堆型核电厂反应堆冷却剂泵(RCP)密封安装工艺流程及方法,对RCP密封系统安装和调试过程中的各种情况进行分析,制定各种情况下核回路冲洗采取的特殊处理方案,为后续CPR1000项目RCP密封系统安装调试提供参考.

  1. Independent technical support for the frozen soil barrier installation and operation at the Fukushima Daiichi Nuclear Power Station (F1 Site)

    Energy Technology Data Exchange (ETDEWEB)

    Looney, Brian B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Jackson, Dennis G. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Truex, Michael J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Johnson, Christian D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-02-23

    TEPCO is implementing a number of water countermeasures to limit the releases and impacts of contaminated water to the surrounding environment. The diverse countermeasures work together in an integrated manner to provide different types, and several levels, of protection. In general, the strategy represents a comprehensive example of a “defense in depth” concept that is used for nuclear facilities around the world. One of the key countermeasures is a frozen soil barrier encircling the damaged reactor facilities. The frozen barrier is intended to limit the flow of water into the area and provide TEPCO the ability to reduce the amount of contaminated water that requires treatment and storage. The National Laboratory team supports the selection of artificial ground freezing and the incorporation of the frozen soil barrier in the contaminated water countermeasures -- the technical characteristics of a frozen barrier are relatively well suited to the Fukushima-specific conditions and the need for inflow reduction. Further, our independent review generally supports the TEPCO/Kajima design, installation strategy and operation plan.

  2. Assessment of RELAP5/MOD2 against a pressurizer spray valve inadverted fully opening transient and recovery by natural circulation in Jose Cabrera Nuclear Station

    Energy Technology Data Exchange (ETDEWEB)

    Arroyo, R.; Rebollo, L. [Union Electrica, SA, Madrid (Spain)

    1993-06-01

    This document presents the comparison between the simulation results and the plant measurements of a real event that took place in JOSE CABRERA nuclear power plant in August 30th, 1984. The event was originated by the total, continuous and inadverted opening of the pressurizer spray valve PCV-400A. JOSE CABRERA power plant is a single loop Westinghouse PWR belonging to UNION ELECTRICA FENOSA, S.A. (UNION FENOSA), an Spanish utility which participates in the International Code Assessment and Applications Program (ICAP) as a member of UNIDAD ELECTRICA, S.A. (UNESA). This is the second of its two contributions to the Program: the first one was an application case and this is an assessment one. The simulation has been performed using the RELAP5/MOD2 cycle 36.04 code, running on a CDC CYBER 180/830 computer under NOS 2.5 operating system. The main phenomena have been calculated correctly and some conclusions about the 3D characteristics of the condensation due to the spray and its simulation with a 1D tool have been got.

  3. INSTALLATION OF A POST-ACCIDENT CONFINEMENT HIGH-LEVEL RADIATION MONITORING SYSTEM IN THE KOLA NUCLEAR POWER STATION (UNIT 2) IN RUSSIA

    Energy Technology Data Exchange (ETDEWEB)

    GREENE,G.A.; GUPPY,J.G.

    1998-09-01

    This is the final report on the INSP project entitled, ``Post-Accident Confinement High-Level Radiation Monitoring System'' conducted by BNL under the authorization of Project Work Plan WBS 1.2.2.6 (Attachment 1). This project was initiated in February 1993 to assist the Russians in reducing risks associated with the continued operation of older Soviet-designed nuclear power plants, specifically the Kola VVER-440/230 Unit 2, through improved accident detection capability, specifically by the installation of a dual train high-level radiation detection system in the confinement of Unit 2 of the Kola NPP. The major technical objective of this project was to provide, install and make operational the necessary hardware inside the confinement of the Kola NPP Unit 2 to provide early and reliable warning of the release of radionuclides from the reactor into the confinement air space as an indication of the occurrence of a severe accident at the plant. In addition, it was intended to provide hands-on experience and training to the Russian plant workers in the installation, operation, calibration and maintenance of the equipment in order that they may use the equipment without continued US assistance as an effective measure to improve reactor safety at the plant.

  4. Compression and immersion tests and leaching of radionuclides, stable metals, and chelating agents from cement-solidified decontamination waste collected from nuclear power stations

    Energy Technology Data Exchange (ETDEWEB)

    Akers, D.W.; Kraft, N.C.; Mandler, J.W. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

    1994-06-01

    A study was performed for the Nuclear Regulatory Commission (NRC) to evaluate structural stability and leachability of radionuclides, stable metals, and chelating agents from cement-solidified decontamination ion-exchange resin wastes collected from seven commercial boiling water reactors and one pressurized water reactor. The decontamination methods used at the reactors were the Can-Decon, AP/Citrox, Dow NS-1, and LOMI processes. Samples of untreated resin waste and solidified waste forms were subjected to immersion and compressive strength testing. Some waste-form samples were leach-tested using simulated groundwaters and simulated seawater for comparison with the deionized water tests that are normally performed to assess waste-form leachability. This report presents the results of these tests and assesses the effects of the various decontamination methods, waste form formulations, leachant chemical compositions, and pH of the leachant on the structural stability and leachability of the waste forms. Results indicate that releases from intact and degraded waste forms are similar and that the behavior of some radionuclides such as {sup 55}Fe, {sup 60}Co, and {sup 99}Tc were similar. In addition, the leachability indexes are greater than 6.0, which meets the requirement in the NRC`s ``Technical Position on Waste Form,`` Revision 1.

  5. Calculation of the pipes failure probability of the Rcic system of a nuclear power station by means of software WinPRAISE 07; Calculo de la probabilidad de falla de tuberias del sistema RCIC de una central nuclear mediante el software WinPRAISE 07

    Energy Technology Data Exchange (ETDEWEB)

    Jasso G, J.; Diaz S, A.; Mendoza G, G.; Sainz M, E. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Garcia de la C, F. M., E-mail: angeles.diaz@inin.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Km 44.5 Carretera Cardel-Nautla, 91476 Laguna Verde, Alto Lucero, Veracruz (Mexico)

    2014-10-15

    The growth and the cracks propagation by fatigue are a typical degradation mechanism that is presented in the nuclear industry as in the conventional industry; the unstable propagation of a crack can cause the catastrophic failure of a metallic component even with high ductility; for this reason, activities of programmed maintenance have been established in the industry using inspection and visual techniques and/or ultrasound with an established periodicity allowing to follow up to these growths, controlling the undesirable effects; however, these activities increase the operation costs; and in the peculiar case of the nuclear industry, they increase the radiation exposure to the participant personnel. The use of mathematical processes that integrate concepts of uncertainty, material properties and the probability associated to the inspection results, has been constituted as a powerful tool of evaluation of the component reliability, reducing costs and exposure levels. In this work the evaluation of the failure probability by cracks growth preexisting by fatigue is presented, in pipes of a Reactor Core Isolation Cooling system (Rcic) in a nuclear power station. The software WinPRAISE 07 (Piping Reliability Analysis Including Seismic Events) was used supported in the probabilistic fracture mechanics principles. The obtained values of failure probability evidenced a good behavior of the analyzed pipes with a maximum order of 1.0 E-6, therefore is concluded that the performance of the lines of these pipes is reliable even extrapolating the calculations at 10, 20, 30 and 40 years of service. (Author)

  6. Hourly atmospheric concentrations of Cs-134 and Cs-137 at monitoring stations for suspended particulate matter in and south of Fukushima after the Fukushima Daiichi Nuclear Power Plant accident

    Science.gov (United States)

    Tsuruta, Haruo; Oura, Yasuji; Ebihara, Mitsuru; Ohara, Toshimasa; Nakajima, Teruyuki

    2013-04-01

    No data has been found of continuous monitoring of radioactive materials in the atmosphere in Fukushima area after the Fukushima Daiichi Nuclear Power Plant (FD1NPP) accident on March 11, 2011, although it greatly contributes to accurate evaluation of the internal exposure dose, to reconstruction of emission time series of released radionuclides, and to validation of numerical simulations by atmospheric transport models. Then, we have challenged to retrieve the radioactivity in atmospheric aerosols collected every hour on a filter tape of Suspended Particulate Matter (SPM) monitoring system with beta ray attenuation method used at air pollution monitoring stations in east Japan. A test measurement for hourly atmospheric concentrations of Cs-134 and Cs-137 was successfully performed with a Ge detector for the used filter tapes during March 15-23, 2011, at three stations in Fukushima City 60 km northwest of the FD1NPP and four stations in southwest Ibaraki prefecture more than 150 km southwest of the FD1NPP. The data in Fukushima City revealed high Cs-137 concentrations of 10-30 Bq m-3 from the evening of March 15 to the early morning of March 16, when a large amount of radioactive materials was simultaneously deposited on the land surface by precipitation according to the measurement of radiation dose rate. Higher Cs-137 concentrations of 10-50 Bq m-3 were also found from the afternoon of March 20 to the morning of March 21, and which could not be detected by the radiation dose rate due to no precipitation. In contrast, much higher concentrations with the maximum of 320 Bq m-3 in southwest Ibaraki than in Fukushima City were found on the morning of March 15 and 21 under strong temperature inversion near the surface. The polluted air masses with high radioactive materials were passed away within a few hours as a plume in southwest Ibaraki, while the high Cs-137 concentrations lasted for 10-16 hours in Fukushima City where the polluted air masses after their transport

  7. Study and Realization of Fault Diagnosis for CRDM in PWR Nuclear Power Station%压水堆核电站CRDM故障诊断研究与实践

    Institute of Scientific and Technical Information of China (English)

    昌正科; 董治国; 常乐莉

    2013-01-01

    The fault diagnosis method for control rod drive mechanism (CRDM) in pressurized water reactor nuclear power station is studied.By using virtual instrument technology,the coil current waveform of CRDM is monitored on line,then the characteristics of the waveform and movement point are analyzed and recognized,thus the operating status of the drive mechanism and its current regulating output loop are judged.The analysis results are saved in real time database for long term performance trending analysis.The system is significant to enhance the operation reliability of CRDM,and has been applied in Qinshan Phase Ⅱ Nuclear Power Plant,it possesses better promotion value.%对压水堆核电站控制棒驱动机构故障诊断方法进行了研究.通过采用虚拟仪器技术,在线监测控制棒驱动机构线圈电流波形、分析波形特征、辨识驱动机构动作特征点,从而判断驱动机构及其电流调节输出回路的运行情况.分析结果实时保存到数据库,可用于驱动机构性能变化趋势的长期分析.系统对提高控制棒驱动机构运行可靠性具有重要意义,已成功应用于秦山第二核电厂,具有一定的推广价值.

  8. Nuclear Security for Floating Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Skiba, James M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Scherer, Carolynn P. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-10-13

    Recently there has been a lot of interest in small modular reactors. A specific type of these small modular reactors (SMR,) are marine based power plants called floating nuclear power plants (FNPP). These FNPPs are typically built by countries with extensive knowledge of nuclear energy, such as Russia, France, China and the US. These FNPPs are built in one country and then sent to countries in need of power and/or seawater desalination. Fifteen countries have expressed interest in acquiring such power stations. Some designs for such power stations are briefly summarized. Several different avenues for cooperation in FNPP technology are proposed, including IAEA nuclear security (i.e. safeguards), multilateral or bilateral agreements, and working with Russian design that incorporates nuclear safeguards for IAEA inspections in non-nuclear weapons states

  9. Internal Mainland Nuclear Power Liquid Waste Treatment Technology

    Institute of Scientific and Technical Information of China (English)

    YOU; Xin-feng; ZHANG; Zhen-tao; ZHENG; Wen-jun; WANG; Lei; YANG; Lin-yue; HUA; Xiao-hui; ZHENG; Yu; YANG; Yong-gang; WU; Yan

    2013-01-01

    Taohuajiang power station is the first internal mainland nuclear power station,and it adopts AP1000nuclear technology belongs to the Westinghouse Electric Corporation.To ensure the safety of the environment around the station and satisfy the radio liquid waste discharge standards,our team has researched the liquid waste treatment technology for the internal mainland nuclear power plant.According

  10. Optimization for Main Steam Super Pipe Hot Extrusion Mouthpiece of Nuclear Power Station%核电站主蒸汽超级管道热挤压管嘴设计优化

    Institute of Scientific and Technical Information of China (English)

    李强; 王磊; 马国顺; 刘翠波

    2015-01-01

    By the finite element method based on commercial software,ANASY,it show that inner pressure plays a major role in the mouthpiece stress of main steam super pipe in nuclear power station.In addition, through studying the effect of mouthpiece radius and longitudinal inner arc radius on mouthpiece stress, The range of longitudinal inner arc radius to optimize the peak stress and local thin film stress were pro-posed.Specifically,it is emphasized that the optimized longitudinal inner arc radius of No.1 mouthpiece is 30 mm.%对核电站主蒸汽超级管道热挤压管嘴进行有限元分析,结果表明内压是影响管嘴应力的主要因素。通过研究管嘴纵向内角半径对管嘴应力的影响,得出在给定载荷的情况下峰值应力和局部薄膜应力存在一个最优的纵向内角半径范围。根据分析结果,推荐了1号管嘴纵向内角半径尺寸为 R =30 mm。

  11. 900MW压水堆核电站主要控制系统的设计%Design Of Main Control System Of Nuclear Power Station With Pressurized Water Reactor Of 900MW

    Institute of Scientific and Technical Information of China (English)

    李宏巍

    2012-01-01

    本论文介绍了900MW压水堆核电站概况;分析了压水堆核电站主要控制系统的设备和控制原理;介绍了关于反应堆功率(中子通量密度水平)控制、平均温度调节控制、一回路压力控制、稳压器液位控制、蒸汽发生器液位控制和蒸汽排放控制等具体控制原理。%This paper introduces the general status of nuclear power station with pressurized water reactor of 900MW,analyzes control principle,introduces specific control principles of reactor capability control,average temperature adjustment control,circuit pressure control,voltage stabilizer liquid level control,steam generator liquid level control and steam emission control.

  12. Manufacture Process of Steel Box Girder for RP Gantry in Some Nuclear Power Station%某核电站RP龙门架箱形钢结构梁制作工艺

    Institute of Scientific and Technical Information of China (English)

    展之芳

    2014-01-01

    In steel structure project, fabrication process of steel box girder is complex, so it is difficult to control welding deformation. This paper introduced the fabrication process of steel box girder for RP gantry in nuclear power station from the material, assembly, welding and correction. The fabrication process ensures the overall geometry of box girder, and guarantees the effective control of welding deformation and welding quality, achieves a certain economic benefits.%钢结构工程中,箱形钢梁制作工艺复杂,焊接变形控制困难。通过从下料、组装、焊接、矫正等方面详细介绍了核电站RP龙门架箱形钢结构梁的制作工艺过程,该过程保证了箱形钢梁的整体几何尺寸,同时又保证了焊接质量并有效控制了焊接变形,取得了一定经济效益。

  13. Radiation Effects of Fukushima Dai-ichi Nuclear Power Station Accident on Fishies in Offshore Area%福岛第一核电站事故对近岸海域鱼类的辐射影响

    Institute of Scientific and Technical Information of China (English)

    李冰; 杨端节; 陈晓秋; 余少青

    2012-01-01

    利用福岛第一核电站事故后不同沿岸和离岸距离处的海水中放射性核素137Cs的监测数据。以鱼类为参考水生生物,通过核素137Cs的累积动力学模式对鱼体内核素的动态浓集进行了评估,给出了福岛第一核电站事故后液态放射性释放所致近岸海域水生动物体内核素水平的变化规律。%The dynamic modeling of 137Cs accumulation by the fish, as reference aquatic biota species, was developed for evaluating dynamic concentration process, based on monitoring data of 137Cs coneentra tions in the sea water offshore and longshore after the accident at Fukushima Dai-iehi Nuclear Power Station. The dependence of 137Cs dynamic concentration by the fish was provided on 137Cs concentration in the water and fish age.

  14. Cycle for fuel elements. Uranium production, programs for nuclear power stations and capital expenditure involved; Cycles de combustibles. Production d'uranium, programme de centrales electriques et effort financier correspondant

    Energy Technology Data Exchange (ETDEWEB)

    Andriot, J.; Gaussens, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    A number of different possible programs for nuclear power stations of various types are presented in this survey. These programs are established in relation to the use of uranium and thorium in amounts similar to those that shall probably be produced in France during the next fifteen years. As it is possible to draw plans for nuclear power stations in which several processes exist simultaneously, an unlimited number of variations being thinkable, this survey is limited to successive analysis of the results obtained by use of only one of each of the following three systems: - system natural uranium-graphite, - system natural uranium-heavy water, -system enriched uranium-pressurised light water. All schemes are considered as assemblages of these three simple systems. The effects of plutonium recycling are also considered for each system. The electric power installed and the capacity of stations situated up-stream and down-stream have been calculated by this method and an attempt has been made to establish the sum to be invested during the fifteen years necessary for the launching of the programs scheduled. A table of timing for the investments groups the results obtained. Considering the fact that French availabilities in capital shall not be unlimited during the coming years, this way of presenting the results seems to be interesting. (author)Fren. [French] L'etude presentee comporte l'examen d'un certain nombre d'hypotheses de programmes de centrales nucleaires de types differents. Ces programmes correspondent a l'utilisation de tonnages d'uranium et de thorium de l'ordre de grandeur de ceux qui seront probablement produits par la France dans les quinze prochaines annees. Comme il est possible de batir un programme de centrales nucleaires, comportant a la fois plusieurs filieres suivant des variantes en nombre infini, on s'est contente d'examiner successivement les resultats ous si on utilisait exclusivement l

  15. Analysis of the operator's connaissance competence for SGTR accidents in a digital nuclear power station%数字化核电站SGTR事故操纵员认知分析

    Institute of Scientific and Technical Information of China (English)

    袁科; 张力; 戴立操

    2012-01-01

    This paper intends to make a review and summarize the technological features of the control room digitalized, including the digital codes, alarming system, the operation team information sharing, the interface management tasks, all of which involve its operator ' s cognitive power and sense of responsibility. To be exact, the responsibility of an operator involve the safety and security of millions' life and the social well-being. Just from the urgent need, this paper intends to introduce an IDA cognition model for such station operator. The model is divided the reconnaissance competence of an operator into 3 phases: Information-receiving, Diagnosis/Decision and Action-taking. The third part of this paper is dedicated to the application of cognitive model with IDA for analyzing SGTR cognitive accidents in the above said power station. This section can be divided into two parts: the first part is to deal with the introduction of the background of the SGTR experiments (including the reactor core, the experimental initiator events, the initial power, control room environment and SGTR experimental physics process, etc.), whereas the second part is to analyze the cognitive process (including control room of the instrument and control system interface, and overall layout control room from the point of view of an operator ( SOP operating procedure of six state parameter) . Part 4 is on the basis of the operators, including the cognitive performances and the interview reports by which he can analyze and judge the failures in his operating process. And, if anything wrong has happened, the operator is expected to detect and distinguish what is wrong with any of the whole working, including the information at hand, diagnosis/decision to be made and the necessary actions to be taken). Thus, the article has made a summary of SGTR accidents in the digital nuclear power plant on the basis of analyzing and judging the causes of likely errors in operating process o as to provide

  16. 核电站工业水池的地震反应分析%Seismic Response Analysis of Industry Pool Building on a Nuclear Power Station

    Institute of Scientific and Technical Information of China (English)

    薛志成; 裴强; 赵杰

    2013-01-01

    目的 探索核电站工业水池作为抗震物项进行动力计算时的内力分布规律及其危险工况,为工业水池合理截面设计及配筋方案提供技术支持.方法 基于大型有限元商业软件开发了工业水池构筑物进行地震反应分析的编码程序,该程序考虑了土-结构动力相互作用,并以黏弹性边界模拟无限地基的影响.结果 依据材料力学平截面假定实现了ANSYS三维实体单元应力到内力转化,得到了各种荷载工况作用下工业水池后墙弯矩最大值为101.8 kN·m,相对于反应位移法的计算结果小17%,并通过统计最大内力包络确定了工业水池的危险工况为空水状态与SL2地震波共同作用.结论 笔者确定出危险工况下最不利内力的方法比较准确且简单明了,易于工程设计应用.%As a seismic item,internal force distribution and risk case of industry pool in the nuclear power plant is explored while calculating the earthquake responses.The results can provide technical support for the design plan of sectional dimensions and reinforcement.The finite element program of seismic response analysis for industrial pool structures is developed based on commercial software.And soil-structure interaction is simulated by means of adding a viscoelastic boundary in the sides of the model.Based on the plane section assumes of materials mechanics,the transformation between the stress and internal force of three-dimensional solid elements is accomplished.Internal forces distribution and envelope of industrial pools are obtained from the simulation results,the value of the maximum bending moment is 101.8 that is 17% smaller than the calculation results of response displacement method,and then it is determined that the most dangerous case is the combined effects of SL2 seismic waves and empty pool.Based on the calculation results,it can be concluded that the method of determining the worst intemal force in the most dangerous case is

  17. Nuclear Propulsion for Space (Rev.)

    Energy Technology Data Exchange (ETDEWEB)

    Corliss, William R; Schwenk, Francis C

    1971-01-01

    The operation of nuclear rockets and a description of the development of nuclear rockets in the U.S. is given. Early developments and Project Rover, Project Pluto, and the NERVA (Nuclear Engine for Rocket Vehicle Application) Program are detailed. The Nuclear Rocket Development Station facilities in Nevada are described. The possibilities and advantages of using nuclear rockets for missions beginning from an earth orbit and moving outward toward higher earth orbits, the moon, and the planets are discussed.

  18. Ecosystem monitoring on dispersion and export dynamics of ¹³⁷Cs deposited on the forested area in Fukushima after the nuclear power stations accident in March 2011

    Energy Technology Data Exchange (ETDEWEB)

    Ohte, Nobuhito; Endo, Izuki; Iseda, Kohei; Tanoi, Keitaro [University of Tokyo, Bunkyo-ku, Tokyo, 113-8657 (Japan); Murakami, Masashi [Chiba University, Inage-ku, Chiba, 263-8522 (Japan); Ishii, Nobuyoshi [National Institute of Radiological Sciences, Inage-ku, Chiba, 263-8555 (Japan)

    2014-07-01

    The accident of the Fukushima Daiichi Nuclear Power Stations in March 2011 emitted 1.5x10¹⁷ Bq of ¹³¹I, 1.2x10¹⁶ Bq of ¹³⁷Cs into the surrounding environment. Those radioactive substances including ¹³⁷Cs deposited onto the forest areas of the northeastern region of the Honshu Island, Japan. Forests of these regions are especially important for the people not only for their forest production industry, but also for the source areas of drinking water. The first phase of the governmental survey and investigations showed that major portion of deposited ¹³⁷Cs is trapped on the canopies and litter layers of soil surface. As ¹³⁷Cs is easily adsorbed onto clay minerals in soil, major portion of those can be transported by eroded soils and particulate organic matters through the hydrological pathways. Dissolved ¹³⁷Cs which is relatively free from soil adsorption can be taken up by microbes, algae and plants in soil and aquatic systems. Then, those ¹³⁷Cs are eventually introduced into soil insects, worms, aquatic insects, fishes and birds through the food web. To clarify the mechanisms of dispersion and export of ¹³⁷Cs within and from a forested ecosystem, we started intensive field observations and samplings in a small catchment including forests and farmlands in the area ~50 km distant from the Nuclear Power Station. The study is conducted at the Kami-Oguni River catchment in the northern part of Fukushima Prefecture. Major land uses of the catchment are forests and paddy fields. Expected two major pathways of ¹³⁷Cs diffusion and export are investigated; 1) transportation by water movement with dissolved and particulate or colloidal forms through the hydrological processes, 2) dispersion through the food web including both detritus food chains based upon plant litters and grazing food chains based upon living plant leaves in the forest-stream ecological continuum. The ¹³⁷Cs concentrations of stream waters at several sampling

  19. Dome module lifting pre-design and analysis of nuclear power station%某核电站穹顶模块吊装预案设计分析

    Institute of Scientific and Technical Information of China (English)

    于喜年; 杨全军; 王建国; 崔亮; 陈娜

    2015-01-01

    为降低核电站穹顶吊装施工风险,保证核岛建造质量,结合第三代核电站工程实际,针对穹顶薄壁、整体模块质量大、对接精度高、吊装要求严格、构件重心与形心偏离等特点,设计钢箱梁吊具及焊接H型钢桁架吊具两套预吊装系统,采用多吊点垂直起吊方案。基于Ansys有限元分析软件,对吊装方案进行分析评价。结果表明:钢箱梁吊装方案吊具结构难以满足大型穹顶吊装要求,焊接H型钢桁架吊装方案吊具结构质量轻、造价低,强度刚度好。桁架吊装系统整体最大等效应力273.761 MPa,小于材料许用应力值;最大位移21.9 mm,符合起重机设计规范要求的挠度值,满足刚度要求;三阶屈曲系数均大于2,吊装系统稳定性良好。分析数据验证吊装系统参数设计基本合理,吊具结构设计可行。%This paper is targeted at reducing project risks associated with nuclear power station dome lifting and ensuring the construction quality of nuclear island. This research involves addressing dome-lift-ing challenges, such as a thinner wall, a heavier weight, a higher docking precision and a stringent lift-ing requirement, and deviation between center of gravity and centroid, as in case of the dome lifting of third-generation nuclear power plant. The solution does so by designing two sets of lifting systems: steel box girder and H-beam welding truss, and adopting mulit-points&vertical lifting scheme. The scheme is validated by the analysis and evaluation based on FEA software like Ansys. The results show that, in con-trast to steel box girder lifting program thwarted by the spreader inadequate to meet large dome lifting re-quirements, H-beam welding truss program boasts such advantages as a lighter weight, a lower cost and a better strength & stiffness. H-beam welding truss has the maximum overall stress of 273. 761 MPa, less than the material allowable stress value;the max displacement of 21. 9

  20. Nuclear safety in perspective

    Directory of Open Access Journals (Sweden)

    J. K. Basson

    1983-03-01

    Full Text Available The impending operation of South Africa’s first nuclear power station, Koeberg, necessitates a thorough analysis of nuclear safety under local conditions. More is known, worldwide, about radiation effects than about any other health hazard, and international norms have already been accepted since 1928. The widespread use of X-rays and radio-isotopes, the extraction and processing of uranium, visits by nuclear-powered ships and, especially, the nuclear-reactor operation in South Africa. Consequently, the pre-operational investigations of Koeberg could be completed thoroughly, with full confidence in its safe commissioning.

  1. Nuclear Regulatory Commission issuances

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    This report includes the issuances received during the April 1996 reporting period from the Commission, the Atomic Safety and Licensing Boards, the Administrative Law Judges, the Directors` Decisions, and the Decisions on Petitions for Rulemaking. Included are issuances pertaining to: (1) Yankee Nuclear Power Station, (2) Georgia Tech Research Reactor, (3) River Bend Station, (4) Millstone Unit 1, (5) Thermo-Lag fire barrier material, and (6) Louisiana Energy Services.

  2. Detailed source term estimation of the atmospheric release for the Fukushima Daiichi Nuclear Power Station accident by coupling simulations of an atmospheric dispersion model with an improved deposition scheme and oceanic dispersion model

    Science.gov (United States)

    Katata, G.; Chino, M.; Kobayashi, T.; Terada, H.; Ota, M.; Nagai, H.; Kajino, M.; Draxler, R.; Hort, M. C.; Malo, A.; Torii, T.; Sanada, Y.

    2015-01-01

    Temporal variations in the amount of radionuclides released into the atmosphere during the Fukushima Daiichi Nuclear Power Station (FNPS1) accident and their atmospheric and marine dispersion are essential to evaluate the environmental impacts and resultant radiological doses to the public. In this paper, we estimate the detailed atmospheric releases during the accident using a reverse estimation method which calculates the release rates of radionuclides by comparing measurements of air concentration of a radionuclide or its dose rate in the environment with the ones calculated by atmospheric and oceanic transport, dispersion and deposition models. The atmospheric and oceanic models used are WSPEEDI-II (Worldwide version of System for Prediction of Environmental Emergency Dose Information) and SEA-GEARN-FDM (Finite difference oceanic dispersion model), both developed by the authors. A sophisticated deposition scheme, which deals with dry and fog-water depositions, cloud condensation nuclei (CCN) activation, and subsequent wet scavenging due to mixed-phase cloud microphysics (in-cloud scavenging) for radioactive iodine gas (I2 and CH3I) and other particles (CsI, Cs, and Te), was incorporated into WSPEEDI-II to improve the surface deposition calculations. The results revealed that the major releases of radionuclides due to the FNPS1 accident occurred in the following periods during March 2011: the afternoon of 12 March due to the wet venting and hydrogen explosion at Unit 1, midnight of 14 March when the SRV (safety relief valve) was opened three times at Unit 2, the morning and night of 15 March, and the morning of 16 March. According to the simulation results, the highest radioactive contamination areas around FNPS1 were created from 15 to 16 March by complicated interactions among rainfall, plume movements, and the temporal variation of release rates. The simulation by WSPEEDI-II using the new source term reproduced the local and regional patterns of cumulative

  3. Estimating the Duration of Public Concern After the Fukushima Dai-ichi Nuclear Power Station Accident From the Occurrence of Radiation Exposure-Related Terms on Twitter: A Retrospective Data Analysis

    Science.gov (United States)

    2016-01-01

    Background After the Fukushima Dai-ichi Nuclear Power Station accident in Japan on March 11, 2011, a large number of comments, both positive and negative, were posted on social media. Objective The objective of this study was to clarify the characteristics of the trend in the number of tweets posted on Twitter, and to estimate how long public concern regarding the accident continued. We surveyed the attenuation period of the first term occurrence related to radiation exposure as a surrogate endpoint for the duration of concern. Methods We retrieved 18,891,284 tweets from Twitter data between March 11, 2011 and March 10, 2012, containing 143 variables in Japanese. We selected radiation, radioactive, Sievert (Sv), Becquerel (Bq), and gray (Gy) as keywords to estimate the attenuation period of public concern regarding radiation exposure. These data, formatted as comma-separated values, were transferred into a Statistical Analysis System (SAS) dataset for analysis, and survival analysis methodology was followed using the SAS LIFETEST procedure. This study was approved by the institutional review board of Hokkaido University and informed consent was waived. Results A Kaplan-Meier curve was used to show the rate of Twitter users posting a message after the accident that included one or more of the keywords. The term Sv occurred in tweets up to one year after the first tweet. Among the Twitter users studied, 75.32% (880,108/1,168,542) tweeted the word radioactive and 9.20% (107,522/1,168,542) tweeted the term Sv. The first reduction was observed within the first 7 days after March 11, 2011. The means and standard errors (SEs) of the duration from the first tweet on March 11, 2011 were 31.9 days (SE 0.096) for radioactive and 300.6 days (SE 0.181) for Sv. These keywords were still being used at the end of the study period. The mean attenuation period for radioactive was one month, and approximately one year for radiation and radiation units. The difference in mean duration

  4. 76 FR 15001 - Entergy Nuclear Operations, Inc,. Entergy Nuclear Vermont Yankee, LLC, Vermont Yankee Nuclear...

    Science.gov (United States)

    2011-03-18

    ... dated January 12, 2010, from Mr. Michael Mulligan, February 8, 2010, from Mr. Raymond Shadis, and... (NRC) take action with regard to the Vermont Yankee Nuclear Power Station (VY). Mr. Mulligan...

  5. Joint scientific publication by the INSERM and IRSN concerning child leukaemia about French nuclear power stations on the Internet site of the 'International Journal of Cancer' the 4 January 2012; Publication scientifique conjointe Inserm et IRSN concernant les leucemies chez l'enfant autour des centrales nucleaires francaises sur le site internet de la revue 'International Journal of Cancer' le 4 Janvier 2012

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-01-12

    This document describes the cooperation between the INSERM and IRSN in the field of child leukaemia about nuclear power stations, and presents the published study: context and objectives, methodology (epidemiological data, geographical data), and obtained results (risks and comparison with a German study)

  6. Hammond Bay Biological Station

    Data.gov (United States)

    Federal Laboratory Consortium — Hammond Bay Biological Station (HBBS), located near Millersburg, Michigan, is a field station of the USGS Great Lakes Science Center (GLSC). HBBS was established by...

  7. Big Game Reporting Stations

    Data.gov (United States)

    Vermont Center for Geographic Information — Point locations of big game reporting stations. Big game reporting stations are places where hunters can legally report harvested deer, bear, or turkey. These are...

  8. Reference Climatological Stations

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The Reference Climatological Stations (RCS) network represents the first effort by NOAA to create and maintain a nationwide network of stations located only in areas...

  9. Fire Stations - 2009

    Data.gov (United States)

    Kansas Data Access and Support Center — Fire Stations in Kansas Any location where fire fighters are stationed or based out of, or where equipment that such personnel use in carrying out their jobs is...

  10. Fire Stations - 2007

    Data.gov (United States)

    Kansas Data Access and Support Center — Fire Station Locations in Kansas Any location where fire fighters are stationed at or based out of, or where equipment that such personnel use in carrying out their...

  11. Water Level Station History

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Images contain station history information for 175 stations in the National Water Level Observation Network (NWLON). The NWLON is a network of long-term,...

  12. Weather Radar Stations

    Data.gov (United States)

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

  13. Newport Research Station

    Data.gov (United States)

    Federal Laboratory Consortium — The Newport Research Station is the Center's only ocean-port research facility. This station is located at Oregon State University's Hatfield Marine Science Center,...

  14. Catawba Science Center solar activities. Final report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1983-01-01

    Two demonstration solar water heaters were built. One was to be used at the Science Center and the other with traveling programs. This was completed and both units are being used for these programs which continue. We were able to build a library of 99 solar energy books and booklets that are available to the public for reference. We also conducted programs for 683 students of all ages. The culminating activity was the planned Energy Awareness Festival. This was held on September 26, 1981 and attracted 450 area citizens. We offered free exhibit space and hosted 17 exhibitors.

  15. Station Climatic Summaries, Asia

    Science.gov (United States)

    1989-07-01

    OCDS) ................................................... 077 BIRJAND 408090 8612 (OCDS) ............................................. ( 381 BUSHEHR...ALL HOURS # 2 1 0 1 0 # 0 # 1 # 1 1 CACECR-IB 080 OPERATIONAL CLIMATIC DATA SUMM ARY STATION: BIRJAND , IRAN STATION #: 408090 ICAO ID...082. L@ OPERATIONAL CLIMATIC DATA SIJ44ARY STATION: BIRJAND , IRAN STATION #: 408090 ICAO ID: OIMB LOCATION: 32054’N, 59016’E ELEVATION (FEET): 4823 LST

  16. Simulation of the steady state of the Laguna Verde Nuclear power station at full power (1931 MWt and 2027 Mwt) with the SCDAPSIM code; Simulacion del estado estacionario de la Central Nucleoelectrica de Laguna Verde a plena potencia (1931 MWt y 2027 MWt) con el codigo SCDAPSIM

    Energy Technology Data Exchange (ETDEWEB)

    Amador G, R.; Nunez C, A.; Mateos, E. del A. [Comision Nacional de Seguridad Nuclear y Salvaguardias, Mexico D.F. (Mexico)

    2001-07-01

    This document describes two models developed for the Laguna Verde Nuclear Power Station (LVNPP) using SCDAPSIM computer code. These models represent the LVNPP in normal operation with a nominal power of 1931 MWt and power uprate conditions of 2027 MWt. The steady states obtained by means of these models comply with the criteria established by the ANSI/ANS-3.5-1985 for nuclear power plant simulators. This criteria has been applied to the models of the LVNPP developed by CNSNS in want of some international accepted criteria for ''Best Estimation'' computer codes. These models will be the bases to carry out studies of validation of the own models as well as the analysis of diverse scenarios that evolve to a severe accident. (Author)

  17. Operate a Nuclear Power Plant.

    Science.gov (United States)

    Frimpter, Bonnie J.; And Others

    1983-01-01

    Describes classroom use of a computer program originally published in Creative Computing magazine. "The Nuclear Power Plant" (runs on Apple II with 48K memory) simulates the operating of a nuclear generating station, requiring students to make decisions as they assume the task of managing the plant. (JN)

  18. 镀锌钢在红沿河大气环境中的腐蚀行为%Atmospheric Corrosion Behavior of Galvanized Steel at Hongyanhe Nuclear Power Station

    Institute of Scientific and Technical Information of China (English)

    刘雨薇; 曹公望; 王振尧; 曹岩; 蒋双优; 王磊

    2016-01-01

    目的:研究镀锌钢在红沿河地区SO2和Cl-含量较高的大气环境中的腐蚀行为与机理。方法根据GB/T 6464—1997将制备好的试样在红沿河核电厂进行现场暴晒试验,分别暴晒4、12、18、24个月后取回试样。利用失重分析、X 射线衍射( XRD)和扫描电镜( SEM)等技术,观察与分析试样暴晒后的腐蚀产物。结果镀锌钢腐蚀失重随暴晒时间的延长而线性增加;随着暴晒时间的延长,锌镀层表面形成的腐蚀产物成分变化不大,以Zn12(SO4)3Cl3(OH)15·5H2O和6Zn(OH)2·ZnSO4·4H2O为主;腐蚀产物随暴晒时间的延长逐渐增加,产物形貌略有变化,以球状和针状为主。暴晒18个月后,腐蚀产物分为双两层,内层致密,外层疏松;暴晒24个月后,腐蚀产物厚度稍有增加,疏松层向致密层转变。结论 SO2与Cl-是镀锌钢在红沿河地区的大气腐蚀过程的主要影响因子。镀锌钢表面形成的腐蚀产物对锌镀层的保护作用较差。%ABSTRACT:Objective To study the atmospheric corrosion behavior and mechanism of galvanized steel at Hongyanhe nuclear power station with high SO2 and Cl-concentrations. Methods The galvanized steel was exposed in the Hongyanhe atmospheric envi-ronment for 4, 12,18 and 24 months, according to GB/T 6464—1997. The corrosion products of galvanized steel after explosion were observed and analyzed by corrosion mass loss test, scanning electron microscopy ( SEM ) and X-ray diffraction ( XRD ) . Results The results of corrosion kinetics analysis showed that the galvanized steel corrosion weight loss increased linearly with the increase of the exposure time. XRD analysis results showed that with the extension of exposure time, there was no big change in the composition of corrosion products formed on the surface of the zinc coating, which were mainly Zn12(SO4)3Cl3(OH)15·5H2O and 6Zn(OH)2·ZnSO4·4H2O. SEM results showed that the corrosion products increased

  19. Detailed source term estimation of the atmospheric release for the Fukushima Daiichi Nuclear Power Station accident by coupling simulations of atmospheric dispersion model with improved deposition scheme and oceanic dispersion model

    Directory of Open Access Journals (Sweden)

    G. Katata

    2014-06-01

    Full Text Available Temporal variations in the amount of radionuclides released into the atmosphere during the Fukushima Dai-ichi Nuclear Power Station (FNPS1 accident and their atmospheric and marine dispersion are essential to evaluate the environmental impacts and resultant radiological doses to the public. In this paper, we estimate a detailed time trend of atmospheric releases during the accident by combining environmental monitoring data with atmospheric model simulations from WSPEEDI-II (Worldwide version of System for Prediction of Environmental Emergency Dose Information, and simulations from the oceanic dispersion model SEA-GEARN-FDM, both developed by the authors. A sophisticated deposition scheme, which deals with dry and fogwater depositions, cloud condensation nuclei (CCN activation and subsequent wet scavenging due to mixed-phase cloud microphysics (in-cloud scavenging for radioactive iodine gas (I2 and CH3I and other particles (CsI, Cs, and Te, was incorporated into WSPEEDI-II to improve the surface deposition calculations. The fallout to the ocean surface calculated by WSPEEDI-II was used as input data for the SEA-GEARN-FDM calculations. Reverse and inverse source-term estimation methods based on coupling the simulations from both models was adopted using air dose rates and concentrations, and sea surface concentrations. The results revealed that the major releases of radionuclides due to FNPS1 accident occurred in the following periods during March 2011: the afternoon of 12 March due to the wet venting and hydrogen explosion at Unit 1, the morning of 13 March after the venting event at Unit 3, midnight of 14 March when the SRV (Safely Relief Valve at Unit 2 was opened three times, the morning and night of 15 March, and the morning of 16 March. According to the simulation results, the highest radioactive contamination areas around FNPS1 were created from 15 to 16 March by complicated interactions among rainfall, plume movements, and the temporal

  20. Detailed source term estimation of the atmospheric release for the Fukushima Daiichi Nuclear Power Station accident by coupling simulations of atmospheric dispersion model with improved deposition scheme and oceanic dispersion model

    Science.gov (United States)

    Katata, G.; Chino, M.; Kobayashi, T.; Terada, H.; Ota, M.; Nagai, H.; Kajino, M.; Draxler, R.; Hort, M. C.; Malo, A.; Torii, T.; Sanada, Y.

    2014-06-01

    Temporal variations in the amount of radionuclides released into the atmosphere during the Fukushima Dai-ichi Nuclear Power Station (FNPS1) accident and their atmospheric and marine dispersion are essential to evaluate the environmental impacts and resultant radiological doses to the public. In this paper, we estimate a detailed time trend of atmospheric releases during the accident by combining environmental monitoring data with atmospheric model simulations from WSPEEDI-II (Worldwide version of System for Prediction of Environmental Emergency Dose Information), and simulations from the oceanic dispersion model SEA-GEARN-FDM, both developed by the authors. A sophisticated deposition scheme, which deals with dry and fogwater depositions, cloud condensation nuclei (CCN) activation and subsequent wet scavenging due to mixed-phase cloud microphysics (in-cloud scavenging) for radioactive iodine gas (I2 and CH3I) and other particles (CsI, Cs, and Te), was incorporated into WSPEEDI-II to improve the surface deposition calculations. The fallout to the ocean surface calculated by WSPEEDI-II was used as input data for the SEA-GEARN-FDM calculations. Reverse and inverse source-term estimation methods based on coupling the simulations from both models was adopted using air dose rates and concentrations, and sea surface concentrations. The results revealed that the major releases of radionuclides due to FNPS1 accident occurred in the following periods during March 2011: the afternoon of 12 March due to the wet venting and hydrogen explosion at Unit 1, the morning of 13 March after the venting event at Unit 3, midnight of 14 March when the SRV (Safely Relief Valve) at Unit 2 was opened three times, the morning and night of 15 March, and the morning of 16 March. According to the simulation results, the highest radioactive contamination areas around FNPS1 were created from 15 to 16 March by complicated interactions among rainfall, plume movements, and the temporal variation of

  1. Non-Coop Station History

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Station history documentation for stations outside the US Cooperative Observer network. Primarily National Weather Service stations assigned WBAN station IDs. Other...

  2. Space station, 1959 to . .

    Science.gov (United States)

    Butler, G. V.

    1981-04-01

    Early space station designs are considered, taking into account Herman Oberth's first space station, the London Daily Mail Study, the first major space station design developed during the moon mission, and the Manned Orbiting Laboratory Program of DOD. Attention is given to Skylab, new space station studies, the Shuttle and Spacelab, communication satellites, solar power satellites, a 30 meter diameter radiometer for geological measurements and agricultural assessments, the mining of the moons, and questions of international cooperation. It is thought to be very probable that there will be very large space stations at some time in the future. However, for the more immediate future a step-by-step development that will start with Spacelab stations of 3-4 men is envisaged.

  3. Amtrak Rail Stations (National)

    Data.gov (United States)

    Department of Transportation — Updated database of the Federal Railroad Administration's (FRA) Amtrak Station database. This database is a geographic data set containing Amtrak intercity railroad...

  4. Cooperative Station History Forms

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Various forms, photographs and correspondence documenting the history of Cooperative station instrumentation, location changes, inspections, and...

  5. Reevaluation of air surveillance station siting

    Energy Technology Data Exchange (ETDEWEB)

    Abbott, K. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Jannik, T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2016-07-06

    DOE Technical Standard HDBK-1216-2015 (DOE 2015) recommends evaluating air-monitoring station placement using the analytical method developed by Waite (Waite, 1973). The technique utilizes wind rose and population distribution data in order to determine a weighting factor for each directional sector surrounding a nuclear facility. Based on the available resources (number of stations) and a scaling factor, this weighting factor is used to determine the number of stations recommended to be placed in each sector considered. An assessment utilizing this method was performed in 2003 to evaluate the effectiveness of the existing SRS air-monitoring program. The resulting recommended distribution of air-monitoring stations was then compared to that of the existing site perimeter surveillance program (Fledderman 2003). The assessment demonstrated that the distribution of air-monitoring stations at the time generally agreed with the results obtained using the Waite method; however at the time new stations were established in Barnwell and in Williston in order to meet requirements of DOE guidance document EH-0173T.

  6. Reevaluation of air surveillance station siting

    Energy Technology Data Exchange (ETDEWEB)

    Abbott, K. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Jannik, T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2016-07-06

    DOE Technical Standard HDBK-1216-2015 (DOE 2015) recommends evaluating air-monitoring station placement using the analytical method developed by Waite. The technique utilizes wind rose and population distribution data in order to determine a weighting factor for each directional sector surrounding a nuclear facility. Based on the available resources (number of stations) and a scaling factor, this weighting factor is used to determine the number of stations recommended to be placed in each sector considered. An assessment utilizing this method was performed in 2003 to evaluate the effectiveness of the existing SRS air-monitoring program. The resulting recommended distribution of air-monitoring stations was then compared to that of the existing site perimeter surveillance program. The assessment demonstrated that the distribution of air-monitoring stations at the time generally agreed with the results obtained using the Waite method; however, at the time new stations were established in Barnwell and in Williston in order to meet requirements of DOE guidance document EH-0173T.

  7. Experience and lessons learned from emergency disposal of Fukushima nuclear power station accident%日本福岛核电站核事故应急处置的经验和教训

    Institute of Scientific and Technical Information of China (English)

    徐卸古; 甄蓓; 杨晓明; 陈肖华

    2012-01-01

    After Fukushima nuclear accident , we visited the related medical aid agencies for nuclear accidents and con -ducted investigations in disaster-affected areas in Japan. This article summarizes the problems with emergency disposal of Fukushima nuclear accident while disclosing problems that should be solved during the emergency force construction for nu -clear accidents.%日本福岛核事故后,应日本同行的邀请,我们访问了日本核医学应急的相关单位,并到相关地区进行了考察.本文探讨了日本福岛核事故应急处置过程中存在的问题,提出了我国核应急力量建设过程中应注意的问题及相关对策.

  8. Meyrin Petrol Station

    CERN Multimedia

    2006-01-01

    Please note that the Meyrin petrol station will be closed for maintenance work on Tuesday 19 and Wednesday 20 December 2006. If you require petrol during this period we invite you to use the Prévessin petrol station, which will remain open. TS-IC-LO Section Tel.: 77039 - 73793

  9. SPS rectifier stations

    CERN Multimedia

    1974-01-01

    The first of the twelves SPS rectifier stations for the bending magnets arrived at CERN at the end of the year. The photograph shows a station with the rectifiers on the left and in the other three cubicles the chokes, capacitors and resistor of the passive filter.

  10. "Inventive" Learning Stations

    Science.gov (United States)

    Jarrett, Olga

    2010-01-01

    Learning stations can be used for myriad purposes--to teach concepts, integrate subject matter, build interest, and allow for inquiry--the possibilities are limited only by the imagination of the teacher and the supplies available. In this article, the author shares suggestions and a checklist for setting up successful learning stations. In…

  11. Secure base stations

    NARCIS (Netherlands)

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

    2009-01-01

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

  12. Capacity at Railway Stations

    DEFF Research Database (Denmark)

    Landex, Alex

    2011-01-01

    special focus when conducting UIC 406 capacity analyses.This paper describes how the UIC 406 capacity method can be expounded for stations. Commonly for the analyses of the stations it is recommended to include the entire station including the switch zone(s) and all station tracks. By including the switch...... zone(s) the possible conflicts with other trains (also in the opposite direction) are taken into account leading to more trustworthy results. Although the UIC 406 methodology proposes that the railway network should be divided into line sections when trains turn around and when the train order...... is changed, this paper recommends that the railway lines are not always be divided. In case trains turn around on open (single track) line, the capacity consumption may be too low if a railway line is divided. The same can be the case if only few trains are overtaken at an overtaking station. For dead end...

  13. Central Station Design Options

    DEFF Research Database (Denmark)

    2011-01-01

    The purpose of EDISON Work Package 4.1 is the evaluation of possible Central (charging) Stations design options for making possible the public charging of Electric Vehicles (EVs). A number of scenarios for EVs are assessed, with special emphasis on the options of Fast Charging and Battery Swapping....... The work identifies the architecture, sizing and siting of prospective Central Stations in Denmark, which can be located at shopping centers, large car parking lots or gas stations. Central Stations are planned to be integrated in the Danish distribution grid. The Danish island of Bornholm, where a high.......g. due to vandalism, the charge supply circuit is disconnected. More electrical vehicles on the market are capable today of quick charging up to 50 kW power level. The feasibility of Central Stations with fast charging/swapping option, their capacity, design, costs and grid impact, as well as battery...

  14. 2005-2010年大亚湾核电站附近海域海水中总β放射性水平%The radioactivity level of gross beta in sea water near Daya Bay Nuclear Power Stations from 2005 to 2010

    Institute of Scientific and Technical Information of China (English)

    赵力; 周鹏; 张红标; 李冬梅; 黄楚光; 方宏达; 蔡伟叙; 陈嘉辉

    2013-01-01

    分析大亚湾核电附近海域2005-2010年海水总β放射性的空间分布特征和年际变化趋势。结果表明2005-2010年该海域海水总β放射性水平范围为0.029-0.073Bq·L−1,平均值为0.051Bq·L−1。2005年以来该海域海水中总β放射性总体上呈缓慢升高趋势且在本底范围内波动,但与其他海域相比仍然处于较低水平,核电站排水口附近海域海水总β放射性水平最高且变化梯度显著,这与排水口排放的低放射性污染物随潮流逐渐扩散有密切的关系。研究为今后科学、合理地评价核电站运行对海洋环境的影响提供了历史资料。%This paper introduces the spatial and temporal distribution of gross beta radioactivity in sea water around Daya Bay Nuclear Power Stations from 2005 to 2010. The gross beta radioactivity in the sea water ranged from 0.029 to 0.073 Bq·L−1 with a mean of 0.051 Bq·L−1. The gross beta radioactivity increased year after year during 2005−2010, but was still in the normal range in 2010 in terms of the background level standard;in fact, it was in a lower level compared with those at other China sea areas which has nuclear power stations. The gross beta radioactivity in the cooling water ejected area was higher than in other areas nearby due to diffuse. This research offers important data for evaluating radioactivity around the coastal nuclear power station of Daya Bay, and also has some significance for preventing radioactivity pollution and protecting the environment of the sea.

  15. White Paper on Nuclear Astrophysics

    OpenAIRE

    Arcones, Almudena; Bardayan, Dan W.; Beers, Timothy C.; Berstein, Lee A.; Blackmon, Jeffrey C.; Messer, Bronson; Brown, B. Alex; Brown, Edward F; Brune, Carl R.; Champagne, Art E.; Chieffi, Alessandro; Couture, Aaron J.; Danielewicz, Pawel; Diehl, Roland; El-Eid, Mounib

    2016-01-01

    This white paper informs the nuclear astrophysics community and funding agencies about the scientific directions and priorities of the field and provides input from this community for the 2015 Nuclear Science Long Range Plan. It summarizes the outcome of the nuclear astrophysics town meeting that was held on August 21-23, 2014 in College Station at the campus of Texas A&M University in preparation of the NSAC Nuclear Science Long Range Plan. It also reflects the outcome of an earlier town mee...

  16. Nuclear Energy in Space Exploration

    Energy Technology Data Exchange (ETDEWEB)

    Seaborg, Glenn T.

    1968-01-01

    Nuclear space programs under development by the Atomic Energy Commission are reviewed including the Rover Program, systems for nuclear rocket propulsion and, the SNAP Program, systems for generating electric power in space. The letters S-N-A-P stands for Systems for Nuclear Auxiliary Power. Some of the projected uses of nuclear systems in space are briefly discussed including lunar orbit, lunar transportation from lunar orbit to lunar surface and base stations; planetary exploration, and longer space missions. The limitations of other sources of energy such as solar, fuel cells, and electric batteries are discussed. The excitement and visionary possibilities of the Age of Space are discussed.

  17. Nuclear Confidence

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    The Fukushima nuclear accident provides valuable lessons for China national nuclear Corp.as it continues to expand its operations AS Japan’s Fukushima nuclear crisis sparks a global debate over nuclear safety,China National Nuclear Corp. (CNNC),the country’s largest nuclear plant operator, comes under the spotlight.

  18. Space station operations management

    Science.gov (United States)

    Cannon, Kathleen V.

    1989-01-01

    Space Station Freedom operations management concepts must be responsive to the unique challenges presented by the permanently manned international laboratory. Space Station Freedom will be assembled over a three year period where the operational environment will change as significant capability plateaus are reached. First Element Launch, Man-Tended Capability, and Permanent Manned Capability, represent milestones in operational capability that is increasing toward mature operations capability. Operations management concepts are being developed to accomodate the varying operational capabilities during assembly, as well as the mature operational environment. This paper describes operations management concepts designed to accomodate the uniqueness of Space Station Freedoom, utilizing tools and processes that seek to control operations costs.

  19. Enhanced Master Station History Report

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The Enhanced Master Station History Report (EMSHR) is a compiled list of basic, historical information for every station in the station history database, beginning...

  20. Analysis of internal events for the Unit 1 of the Laguna Verde Nuclear Power Station. Appendixes; Analisis de eventos internos para la Unidad 1 de la Central Nucleoelectrica de Laguna Verde. Apendices

    Energy Technology Data Exchange (ETDEWEB)

    Huerta B, A.; Lopez M, R. [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

    1995-07-01

    This volume contains the appendices for the accident sequences analysis for those internally initiated events for Laguna Verde Unit 1, Nuclear Power Plant. The appendix A presents the comments raised by the Sandia National Laboratories technical staff as a result of the review of the Internal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant. This review was performed during a joint Sandia/CNSNS multi-day meeting by the end 1992. Also included is a brief evaluation on the applicability of these comments to the present study. The appendix B presents the fault tree models printed for each of the systems included and.analyzed in the Internal Event Analysis for LVNPP. The appendice C presents the outputs of the TEMAC code, used for the cuantification of the dominant accident sequences as well as for the final core damage evaluation. (Author)

  1. Analysis of internal events for the Unit 1 of the Laguna Verde Nuclear Power Station. Appendixes; Analisis de eventos internos para la Unidad 1 de la Central Nucleoelectrica de Laguna Verde. Apendices

    Energy Technology Data Exchange (ETDEWEB)

    Huerta B, A.; Lopez M, R. [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

    1995-07-01

    This volume contains the appendices for the accident sequences analysis for those internally initiated events for Laguna Verde Unit 1, Nuclear Power Plant. The appendix A presents the comments raised by the Sandia National Laboratories technical staff as a result of the review of the Internal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant. This review was performed during a joint Sandia/CNSNS multi-day meeting by the end 1992. Also included is a brief evaluation on the applicability of these comments to the present study. The appendix B presents the fault tree models printed for each of the systems included and analyzed in the Internal Event Analysis for LVNPP. The appendice C presents the outputs of the TEMAC code, used for the cuantification of the dominant accident sequences as well as for the final core damage evaluation. (Author)

  2. White Paper on Nuclear Astrophysics and Low Energy Nuclear Physics - Part 1. Nuclear Astrophysics

    Energy Technology Data Exchange (ETDEWEB)

    Arcones, Almudena [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Escher, Jutta E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Others, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-04-04

    This white paper informs the nuclear astrophysics community and funding agencies about the scientific directions and priorities of the field and provides input from this community for the 2015 Nuclear Science Long Range Plan. It summarizes the outcome of the nuclear astrophysics town meeting that was held on August 21 - 23, 2014 in College Station at the campus of Texas A&M University in preparation of the NSAC Nuclear Science Long Range Plan. It also reflects the outcome of an earlier town meeting of the nuclear astrophysics community organized by the Joint Institute for Nuclear Astrophysics (JINA) on October 9 - 10, 2012 Detroit, Michigan, with the purpose of developing a vision for nuclear astrophysics in light of the recent NRC decadal surveys in nuclear physics (NP2010) and astronomy (ASTRO2010). The white paper is furthermore informed by the town meeting of the Association of Research at University Nuclear Accelerators (ARUNA) that took place at the University of Notre Dame on June 12 - 13, 2014. In summary we find that nuclear astrophysics is a modern and vibrant field addressing fundamental science questions at the intersection of nuclear physics and astrophysics. These questions relate to the origin of the elements, the nuclear engines that drive life and death of stars, and the properties of dense matter. A broad range of nuclear accelerator facilities, astronomical observatories, theory efforts, and computational capabilities are needed. With the developments outlined in this white paper, answers to long-standing key questions are well within reach in the coming decade.

  3. Current research and development activities on fission products and hydrogen risk after the accident at Fukushima Daiichi Nuclear Power Station

    Directory of Open Access Journals (Sweden)

    Takeshi Nishimura

    2015-02-01

    Full Text Available After the Fukushima Daiichi nuclear power plant (NPP accident, new regulatory requirements were enforced in July 2013 and a backfit was required for all existing nuclear power plants. It is required to take measures to prevent severe accidents and mitigate their radiological consequences. The Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority (S/NRA/R has been conducting numerical studies and experimental studies on relevant severe accident phenomena and countermeasures. This article highlights fission product (FP release and hydrogen risk as two major areas. Relevant activities in the S/NRA/R are briefly introduced, as follows: 1. For FP release: Identifying the source terms and leak mechanisms is a key issue from the viewpoint of understanding the progression of accident phenomena and planning effective countermeasures that take into account vulnerabilities of containment under severe accident conditions. To resolve these issues, the activities focus on wet well venting, pool scrubbing, iodine chemistry (in-vessel and ex-vessel, containment failure mode, and treatment of radioactive liquid effluent. 2. For hydrogen risk: because of three incidents of hydrogen explosion in reactor buildings, a comprehensive reinforcement of the hydrogen risk management has been a high priority topic. Therefore, the activities in evaluation methods focus on hydrogen generation, hydrogen distribution, and hydrogen combustion.

  4. Signal Station Inspection Reports

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Handwritten reports resulting from detailed inspections of US Army Signal Service Stations, 1871-1889. Features reported included instrument exposure and condition,...

  5. ASOS Station Photos

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The images contained in this library are of stations in the Automated Surface Observing System (ASOS) network. These images were taken between 1998-2001 for the ASOS...

  6. Active Marine Station Metadata

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The Active Marine Station Metadata is a daily metadata report for active marine bouy and C-MAN (Coastal Marine Automated Network) platforms from the National Data...

  7. Mukilteo Research Station

    Data.gov (United States)

    Federal Laboratory Consortium — Research at the Mukilteo Research Station focuses on understanding the life cycle of marine species and the impacts of ecosystem stressors on anadromous and marine...

  8. Electrostatic pickup station

    CERN Multimedia

    1982-01-01

    Electrostatic pickup station, with 4 interleaved electrodes, to measure beam position in the horizontal and vertical plane. This type is used in the transfer lines leaving the PS (TT2, TT70, TTL2). See also 7904075.

  9. USRCRN Station Information

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Documentation of United States Regional Climate Reference Network (USRCRN) installations in 2009. Installations documented are for USRCRN pilot project stations in...

  10. TV Analog Station Transmitters

    Data.gov (United States)

    Department of Homeland Security — This file is an extract from the Consolidated Database System (CDBS) licensed by the Media Bureau. It consists of Analog Television Stations (see Rule Part47 CFR...

  11. Natural Weathering Exposure Station

    Data.gov (United States)

    Federal Laboratory Consortium — The Corps of Engineers' Treat Island Natural Weathering Exposure Station is a long-term natural weathering facility used to study concrete durability. Located on the...

  12. Maine Field Station

    Data.gov (United States)

    Federal Laboratory Consortium — In 2000 NOAA's National Marine Fisheries Service established the Maine Field Station in Orono, ME to have more direct involvement in the conservation of the living...

  13. Materials Test Station

    Data.gov (United States)

    Federal Laboratory Consortium — When completed, the Materials Test Station at the Los Alamos Neutron Science Center will meet mission need. MTS will provide the only fast-reactor-like irradiation...

  14. Realtime USGS Streamflow Stations

    Data.gov (United States)

    U.S. Geological Survey, Department of the Interior — Approximately 5,000 of the 6,900 U.S. Geological Survey sampling stations are equipped with telemetry to transmit data on streamflow, temperature, and other...

  15. FEMA DFIRM Station Start

    Data.gov (United States)

    Minnesota Department of Natural Resources — This table contains information about station starting locations. These locations indicate the reference point that was used as the origin for distance measurements...

  16. Station Management Plan

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — The following plan is the result of a recent initiative in Region 5 to produce general management guidance based on stated objectives for individual field stations....

  17. Master Station History Report

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The Standard/Legacy MSHR, formally identified as the DSI-9767 dataset, is the legacy dataset/report sorted by NCDC Station ID and period of record. This...

  18. "Central Station" Londonis

    Index Scriptorium Estoniae

    2000-01-01

    Londoni galeriis Milch seitsme läti, leedu ja eesti kunstniku projekt "Central Station". Kuraatorid Lisa Panting, Sally Tallant. Eestist osalevad Hanno Soans (Catarina Campinoga koostöös valminud video), Kiwa, Kai Kaljo

  19. LAERTIS, a multidisciplinary station

    Science.gov (United States)

    Aggouras, G.; Anassontzis, E. G.; Ball, A. E.; Chinowsky, W.; Fahrun, E.; Grammatikakis, G.; Green, C.; Grieder, P.; Katrivanos, P.; Koske, P.; Markopoulos, E.; Minkowsky, P.; Nygren, D.; Papageorgiou, K.; Przybylski, G.; Resvanis, L. K.; Siotis, I.; Sopher, J.; Tsagli, V.; Zhukov, V. A.

    2006-11-01

    LAERTIS, designed to collect environmental data from the deep-sea, is operated since 1999 and has been deployed several time at 4000 m depth at the NESTOR site. Power and data were transferred through a 30-km electro-optical cable to the Shore Station. In this report, we describe briefly the LAERTIS instrumentation and present typical data that were collected successfully during those deployment demonstrating the importance of a deep-sea station permanently connected to shore.

  20. Leadership at Antarctic Stations.

    Science.gov (United States)

    1987-03-01

    Claseification 6. No. Pegees LEADERSHIP AT ANTARTIC STATIONS hxIs i4 5, C =r~eta(C), 17 Rfs~W (R, Udusiied U)J 7. No Refs 8. Author(s) Edocumesnt I...whether there is a "best" approach to leadership at an Antartic Station and what leadership style may have the most to offer. 3~~ __ ___ Tipesis to be

  1. Thermoelectrical power stations in 1967

    Energy Technology Data Exchange (ETDEWEB)

    Medici, M. (University of Padova, Italy)

    1968-01-01

    In Italy in 1967, geothermal electric power production was 2.66% of the national energy production. The implementation of traditional and nuclear power plants is described. The trend in conventional thermoelectric power plants is characterized by ever-increasing block capacities (100-160 MW at present), they are expected to increase to 600 MW in Europe and to 1200 MW in the USA 10 years from now. Nuclear power plants with pressurized-water reactors, boiling-water reactors, and graphite-gas reactors have been built recently in Italy. Studies are being conducted in the area of high-speed reactors and breeder reactors. A description is presented of a power station using geothermal energy. At the end of 1967, geothermal power plants with an electrical capacity of 340 MW were in operation. Generally, U.S. thermoelectrical engine blocks with high productivity were used. The thermodynamic characteristics of these blocks are described in detail. The most powerful engine in the field in Italy- a turbocompressore Franco Tosi- was constructed in the ENEL central Castlenuovo Val Cecina in the Larderello region. The compressor is fed by a combined flow of steam, CO/sub 2/ and H/sub 2/S. It is characterized by a load of 22 t/h and an input pressure of 0.0905 atm at the outlet. The absorbed power is 2.28 MW at a velocity of 50 rotations/sec. Thirty figures are presented.

  2. The Princess Elisabeth Station

    Science.gov (United States)

    Berte, Johan

    2012-01-01

    Aware of the increasing impact of human activities on the Earth system, Belgian Science Policy Office (Belspo) launched in 1997 a research programme in support of a sustainable development policy. This umbrella programme included the Belgian Scientific Programme on Antarctic Research. The International Polar Foundation, an organization led by the civil engineer and explorer Alain Hubert, was commissioned by the Belgian Federal government in 2004 to design, construct and operate a new Belgian Antarctic Research Station as an element under this umbrella programme. The station was to be designed as a central location for investigating the characteristic sequence of Antarctic geographical regions (polynia, coast, ice shelf, ice sheet, marginal mountain area and dry valleys, inland plateau) within a radius of 200 kilometers (approx.124 miles) of a selected site. The station was also to be designed as "state of the art" with respect to sustainable development, energy consumption, and waste disposal, with a minimum lifetime of 25 years. The goal of the project was to build a station and enable science. So first we needed some basic requirements, which I have listed here; plus we had to finance the station ourselves. Our most important requirement was that we decided to make it a zero emissions station. This was both a philosophical choice as we thought it more consistent with Antarctic Treaty obligations and it was also a logistical advantage. If you are using renewable energy sources, you do not have to bring in all the fuel.

  3. Nuclear moments

    CERN Document Server

    Kopferman, H; Massey, H S W

    1958-01-01

    Nuclear Moments focuses on the processes, methodologies, reactions, and transformations of molecules and atoms, including magnetic resonance and nuclear moments. The book first offers information on nuclear moments in free atoms and molecules, including theoretical foundations of hyperfine structure, isotope shift, spectra of diatomic molecules, and vector model of molecules. The manuscript then takes a look at nuclear moments in liquids and crystals. Discussions focus on nuclear paramagnetic and magnetic resonance and nuclear quadrupole resonance. The text discusses nuclear moments and nucl

  4. Nuclear safeguards; Salvaguardias nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Zurron, O.

    2015-07-01

    Safeguards control at the Juzbado Plant is implemented through the joint IAEA/EURATOM partnership approach in force within the European Union for all nuclear facilities. this verification agreement is designed to minimize burden on the operators whilst ensuring that both inspectorate achieve the objectives related to their respective safeguards regimes. This paper outlines the safeguards approaches followed by the inspectorate and the particularities of the Juzbado Plants nuclear material accountancy and control system. (Authors)

  5. Lunar Base Thermoelectric Power Station Study

    Science.gov (United States)

    Determan, William; Frye, Patrick; Mondt, Jack; Fleurial, Jean-Pierre; Johnson, Ken; Stapfer, Gerhard; Brooks, Michael; Heshmatpour, Ben

    2006-01-01

    Under NASA's Project Prometheus, the Nuclear Space Power Systems Program, the Jet Propulsion Laboratory, Pratt & Whitney Rocketdyne, and Teledyne Energy Systems have teamed with a number of universities, under the Segmented Thermoelectric Multicouple Converter (STMC) Task, to develop the next generation of advanced thermoelectric converters for space reactor power systems. Work on the STMC converter assembly has progressed to the point where the lower temperature stage of the segmented multicouple converter assembly is ready for laboratory testing, and promising candidates for the upper stage materials have been identified and their properties are being characterized. One aspect of the program involves mission application studies to help define the potential benefits from the use of these STMC technologies for designated NASA missions such as a lunar base power station where kilowatts of power would be required to maintain a permanent manned presence on the surface of the moon. A modular 50 kWe thermoelectric power station concept was developed to address a specific set of requirements developed for this particular mission concept. Previous lunar lander concepts had proposed the use of lunar regolith as in-situ radiation shielding material for a reactor power station with a one kilometer exclusion zone radius to minimize astronaut radiation dose rate levels. In the present concept, we will examine the benefits and requirements for a hermetically-sealed reactor thermoelectric power station module suspended within a man-made lunar surface cavity. The concept appears to maximize the shielding capabilities of the lunar regolith while minimizing its handling requirements. Both thermal and nuclear radiation levels from operation of the station, at its 100-m exclusion zone radius, were evaluated and found to be acceptable. Site preparation activities are reviewed as well as transport issues for this concept. The goal of the study was to review the entire life cycle of the

  6. Batteries'Usability Study in Station Blackout (SBO) for QinShan Nuclear Power Phase II Extension Project%秦山二期扩建核电厂全厂断电(SBO)事故下蓄电池可用性研究

    Institute of Scientific and Technical Information of China (English)

    游洲; 韩勇; 刘文静; 李朋

    2015-01-01

    Station Blackout (SBO) indicates the all AC power supply lost on the emergency and non-emergency bus in the nuclear power plant. In SBO period, batteries' usability is vital for the nuclear power plant to deal with this fault. This paper introduces the way to use batteries, the calculation and analysis of the power supply time in SBO accident. Some suggestions are given for how to deal with SBO.%全厂断电(SBO)是指核电厂完全丧失应急以及非应急母线上的交流电源。全厂断电后,核电厂蓄电池组的可用性成为整个核电厂应对该事故的关键。对秦山二期扩建工程的蓄电池组在SBO事故下的投用方式进行了介绍,对其带载时间进行了计算和分析,就应对SBO事故提出了建议。

  7. ABB Combustion Engineering nuclear technology

    Energy Technology Data Exchange (ETDEWEB)

    Matzie, R.A.

    1994-12-31

    The activities of ABB Combustion Engineering in the design and construction of nuclear systems and components are briefly reviewed. ABB Construction Engineering continues to improve the design and design process for nuclear generating stations. Potential improvements are evaluated to meet new requirements both of the public and the regulator, so that the designs meet the highest standards worldwide. Advancements necessary to meet market needs and to ensure the highest level of performance in the future will be made.

  8. UMTS Network Stations

    Science.gov (United States)

    Hernandez, C.

    2010-09-01

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

  9. The Space Station

    Science.gov (United States)

    Sharples, R.; Hieatt, J.

    1984-11-01

    The configuration of the Space Station under design studies by NASA is limited only by the capabilities of the Shuttle and the purposes to which it is applied. Once the standard interlocks, launch vibration modes, and pallet designs are fixed, all other assembly of modular components, testing, and trim will be performed in space. The Station will serve for long-term experiments, as a base for planetary missions asembly, launch, and retrieval, and for loading and launching multiple satellites on an orbital transfer vehicle. Materials processing research will be carried out in the Station, as will various scientific and commercial remote sensing activities. The first operational version (1990) will require four Shuttle launches to reach an assembled mass of 70,000 kg drawing 30 kWe from solar panels and housing a crew of five. By the year 2000 the station will support 10-12 crew members in five habitat modules, will be 31 m long, will have cost $18-20 billion, and will be returning $2 billion per year. The station will be periodically reboosted to higher orbits that decay suficiently for orbiter rendezvous for supplies and assignments.

  10. Nuclear ventriculography

    Science.gov (United States)

    ... ventriculography (RNV); Multiple gate acquisition scan (MUGA); Nuclear cardiology; Cardiomyopathy - nuclear ventriculography ... 56. Udelson JE, Dilsizian V, Bonow RO. Nuclear cardiology. In: Bonow RO, Mann DL, Zipes DP, Libby ...

  11. Nuclear Medicine.

    Science.gov (United States)

    Badawi, Ramsey D.

    2001-01-01

    Describes the use of nuclear medicine techniques in diagnosis and therapy. Describes instrumentation in diagnostic nuclear medicine and predicts future trends in nuclear medicine imaging technology. (Author/MM)

  12. Waste Transfer Stations

    DEFF Research Database (Denmark)

    Christensen, Thomas Højlund

    2011-01-01

    tion and transport is usually the most costly part of any waste management system; and when waste is transported over a considerable distance or for a long time, transferring the waste from the collection vehicles to more efficient transportation may be economically beneficial. This involves...... a transfer station where the transfer takes place. These stations may also be accessible by private people, offering flexibility to the waste system, including facilities for bulky waste, household hazardous waste and recyclables. Waste transfer may also take place on the collection route from small...... satellite collection vehicles to large compacting vehicles that cannot effectively travel small streets and alleys within the inner city or in residential communities with narrow roads. However, mobile transfer is not dealt with in this chapter, which focuses on stationary transfer stations. This chapter...

  13. Hydrogen vehicle fueling station

    Energy Technology Data Exchange (ETDEWEB)

    Daney, D.E.; Edeskuty, F.J.; Daugherty, M.A. [Los Alamos National Lab., NM (United States)] [and others

    1995-09-01

    Hydrogen fueling stations are an essential element in the practical application of hydrogen as a vehicle fuel, and a number of issues such as safety, efficiency, design, and operating procedures can only be accurately addressed by a practical demonstration. Regardless of whether the vehicle is powered by an internal combustion engine or fuel cell, or whether the vehicle has a liquid or gaseous fuel tank, the fueling station is a critical technology which is the link between the local storage facility and the vehicle. Because most merchant hydrogen delivered in the US today (and in the near future) is in liquid form due to the overall economics of production and delivery, we believe a practical refueling station should be designed to receive liquid. Systems studies confirm this assumption for stations fueling up to about 300 vehicles. Our fueling station, aimed at refueling fleet vehicles, will receive hydrogen as a liquid and dispense it as either liquid, high pressure gas, or low pressure gas. Thus, it can refuel any of the three types of tanks proposed for hydrogen-powered vehicles -- liquid, gaseous, or hydride. The paper discusses the fueling station design. Results of a numerical model of liquid hydrogen vehicle tank filling, with emphasis on no vent filling, are presented to illustrate the usefulness of the model as a design tool. Results of our vehicle performance model illustrate our thesis that it is too early to judge what the preferred method of on-board vehicle fuel storage will be in practice -- thus our decision to accommodate all three methods.

  14. Nuclear Power Plants (Rev.)

    Energy Technology Data Exchange (ETDEWEB)

    Lyerly, Ray L.; Mitchell III, Walter [Southern Nuclear Engineering, Inc.

    1973-01-01

    Projected energy requirements for the future suggest that we must employ atomic energy to generate electric power or face depletion of our fossil-fuel resources—coal, oil, and gas. In short, both conservation and economic considerations will require us to use nuclear energy to generate the electricity that supports our civilization. Until we reach the time when nuclear power plants are as common as fossil-fueled or hydroelectric plants, many people will wonder how the nuclear plants work, how much they cost, where they are located, and what kinds of reactors they use. The purpose of this booklet is to answer these questions. In doing so, it will consider only central station plants, which are those that provide electric power for established utility systems.

  15. Nuclear Theory - Nuclear Power

    Science.gov (United States)

    Svenne, J. P.; Canton, L.; Kozier, K. S.

    2008-01-01

    The results from modern nuclear theory are accurate and reliable enough to be used for practical applications, in particular for scattering that involves few-nucleon systems of importance to nuclear power. Using well-established nucleon-nucleon (NN) interactions that fit well the NN scattering data, and the AGS form of the three-body theory, we have performed precise calculations of low-energy neutron-deuteron (n+d) scattering. We show that three-nucleon force effects that have impact on the low-energy vector analyzing powers have no practical effects on the angular distribution of the n+d cross-section. There appear to be problems for this scattering in the evaluated nuclear data file (ENDF) libraries, at the incident neutron energies less than 3.2 MeV. Supporting experimental data in this energy region are rather old (>25 years), sparse and often inconsistent. Our three-body results at low energies, 50 keV to 10.0 MeV, are compared to the ENDF/B-VII.0 and JENDL (Japanese Evaluated Nuclear Data Library) -3.3 evaluated angular distributions. The impact of these results on the calculated reactivity for various critical systems involving heavy water is shown.

  16. Galileo Station Keeping Strategy

    Science.gov (United States)

    Perez-Cambriles, Antonio; Bejar-Romero, Juan Antonio; Aguilar-Taboada, Daniel; Perez-Lopez, Fernando; Navarro, Daniel

    2007-01-01

    This paper presents analyses done for the design and implementation of the Maneuver Planning software of the Galileo Flight Dynamics Facility. The station keeping requirements of the constellation have been analyzed in order to identify the key parameters to be taken into account in the design and implementation of the software.

  17. Summit Station Skiway Review

    Science.gov (United States)

    2013-03-01

    operating procedures (SOPs) for future construction and maintenance efforts. DISCLAIMER: The contents of this report are not to be used for...Runway Construction .......................................................... 22 Appendix B: Rammsonde Instructions...13. Snow accumulation at Summit Station in the Bamboo Forest. .......................................... 13 Figure 14. Strength of Summit skiway

  18. Designing a Weather Station

    Science.gov (United States)

    Roman, Harry T.

    2012-01-01

    The collection and analysis of weather data is crucial to the location of alternate energy systems like solar and wind. This article presents a design challenge that gives students a chance to design a weather station to collect data in advance of a large wind turbine installation. Data analysis is a crucial part of any science or engineering…

  19. Electrostatic pickup station

    CERN Multimedia

    1979-01-01

    Electrostatic pickup station, with 4 electrodes, to measure beam position in the horizontal and vertical plane. This type is used in the transfer lines leaving the PS (TT2, TTL2, TT70). See also 8206063, where the electrode shapes are clearly visible.

  20. INTERACT Station Catalogue - 2015

    DEFF Research Database (Denmark)

    INTERACT stations are located in all major environmental envelopes of the Arctic providing an ideal platform for studying climate change and its impact on the environment and local communities. Since alpine environments face similar changes and challenges as the Arctic, the INTERACT network also ...

  1. Kiowa Creek Switching Station

    Energy Technology Data Exchange (ETDEWEB)

    1990-03-01

    The Western Area Power Administration (Western) proposes to construct, operate, and maintain a new Kiowa Creek Switching Station near Orchard in Morgan County, Colorado. Kiowa Creek Switching Station would consist of a fenced area of approximately 300 by 300 feet and contain various electrical equipment typical for a switching station. As part of this new construction, approximately one mile of an existing 115-kilovolt (kV) transmission line will be removed and replaced with a double circuit overhead line. The project will also include a short (one-third mile) realignment of an existing line to permit connection with the new switching station. In accordance with the Council on Environmental Quality (CEQ) regulations for implementing the procedural provisions of the National Environmental Policy Act of 1969 (NEPA), 40 CFR Parts 1500--1508, the Department of Energy (DOE) has determined that an environmental impact statement (EIS) is not required for the proposed project. This determination is based on the information contained in this environmental assessment (EA) prepared by Western. The EA identifies and evaluates the environmental and socioeconomic effects of the proposed action, and concludes that the advance impacts on the human environment resulting from the proposed project would not be significant. 8 refs., 3 figs., 1 tab.

  2. Cause and countermeasure of protective coating failure for AP1000 nuclear power station during construction%AP1000核电站施工期间防护涂层失效的原因及对策

    Institute of Scientific and Technical Information of China (English)

    李炳颖; 林金平; 朱瑞峰

    2015-01-01

    基于山东海阳核电项目,对AP1000核电站独特的模块化建造施工工艺带来的防护涂层破坏问题进行了分析:“开顶法”施工使涂层遭受光照和雨水侵蚀,潮湿的环境有利于霉菌生长并加速对涂层的浸蚀,运输、组装、吊装、焊接等施工过程造成涂层损伤,涂层体系选择不当,等等。提出了相应的解决措施:合理安排施工进度,加盖临时覆盖物,加强排水通风,将用于混凝土墙面的内墙涂料Dry Fall改为耐辐射、防潮防污、耐老化性能好的Macropoxy646涂料,采用“无机富锌+环氧面漆”复合涂层体系代替环氧单层漆用于结构模块和钢结构件等。%Based on the Shandong Haiyang Nuclear Power Plant project, the problem of protection coating failure during the special modularization construction of AP1000 nuclear power plant was analyzed as follows:open-top construction leads to coating suffering of sun light irradiation and rain water erosion;wet environment benefits the mildew growth and accelerates coating erosion;coating is easily damaged during transportation, assembly, lifting, setting, soldering, and other construction procedures;and improper coating system is selected. Some countermeasures were presented:reasonably arrange construction schedule;add temporary covering;enhance water discharge and airing;replace the Dry Fall interior wall coating for concrete wall by Macropoxy646 coating which has good resistance to irradiation, moisture, fouling, and aging; and use a composite coating system composed of inorganic zinc-rich primer plus epoxy topcoat in place of the monolayer epoxy paint for structural modules and steel structure parts.

  3. 地磁扰动对岭澳核电站变压器GIC影响分析%Minimum Geomagnetic Disturbance Leading to Ling'ao Nuclear Power Station 500 kV Transformer DC Bias

    Institute of Scientific and Technical Information of China (English)

    吴伟丽

    2013-01-01

    通过对2004年11月-2006年12月期间的岭澳核电站监测到的地磁感应电流和广州地磁台站观测的地磁数据对比分析,发现缓始磁暴产生的地磁感应电流(GIC)与地磁场分量的变化的相关系数可以大于与其时间一阶导数之间的相关系数.GIC与地磁分量的呈负相关,且相关性均比较大.对8次磁暴产生的GIC的最大幅值与其对应的地磁水平分量的变化率进行最小二乘拟合,推导出二者之间的关系式,可为预测核电站变压器GIC提供依据,并为磁暴灾害对核电站影响程度提供理论参考.%The relationship between geomagentically induced currents(GIC) flowing through 500kV transformer neutral point in Ling' ao power grid and the geomagnetic data observed at Guangzhou geomagnetic observatory during 2004/11-2006/12 is analysised.It is found that correlation coefficient between GIC and magnetic field component variation may be greater than that of time derivative of the geomagnetic field,which are all less than-0.5.By fitting maximum amplitude of GIC and the horizontal component of the geomagnetic field variation rate during 8 storms can be deduced the relation between them.According to the relation,minimum geomagnetic disturbance leading to 500kV transformer DC bias.can be calculated,which can provide a basis for predicting GIC of the nuclear power plant transformer,and provide a theoretical reference for the impact of geomagnetic disasters(GMD) on nuclear power plants.

  4. An under-operation diagnostic apparatus for motor-operated valve. Technical trends on motor-operated valve conservation for nuclear power stations and condition based maintenance using the new diagnostic apparatus

    Energy Technology Data Exchange (ETDEWEB)

    Itou, Haruo [Japan Atomic Power Co., Tokyo (Japan)

    2002-08-01

    A new motor-operated valve diagnostic analysis system (MOVDAS) can be, in short time, simply and with high precision, carried out diagnosis on deterioration and accident of motor-operated valves with many numbers used for separated and feeding valves important for safety of a nuclear reactor, not only at cease but also under operation of a power plant, and is technology capable of upgrading reliability on a motor-operated valve for a condition based maintenance tool and reducing conservation cost. MOVDAS is composed of a built-in torque sensor directly measurable transit torque behaviors with high precision by upgrading a torque sensing technology using strain gauges and a diagnostic apparatus to analyze their signals, which can be used even under operation of the valves. And, this technology can be adapted for under-operation integrity recognition of the valve recommended by NRC in U.S.A. and for operation and maintenance indication, JEAG-4803 in Japan. Here were introduced its contents and also a motor-operated valve remote diagnostic system recently developed in parallel. (G.K.)

  5. SEISMIC PERFORMANCE ANALYSIS OF WATER INTAKE BUILDING IN A NUCLEAR POWER STATION%核电站取水口建筑物的抗震性能分析

    Institute of Scientific and Technical Information of China (English)

    薛志成; 王振清; 裴强; 吴爽

    2012-01-01

    Based on dynamic time-history response analysis, seismic performance analysis of water intake building in the million-kilowatt nuclear power plant was carried out. Considering rock properties and structural characteristics of water intake building, many combinations with different design water levels, operation and maintenance conditions, wave pressure, ice loadings, static and dynamic water pressure, earth pressure and seismic action were considered. The internal force of each section of the structure was obtained by secondary development of ANSYS and the results could provide theoretic evidences for the structural design of water intake building.%针对某百万千瓦级核电厂,运用动力时程反应分析法对取水口建筑物进行抗震分析。结合取水口建筑物场地岩性和结构特点,分别考虑运行和检修情况、波浪、冰块冲击、水压、土压和地震等作用的组合工况,对结构进行抗震性能分析,得到结构构件各个截面内力包络图,对取水LI建筑物设计提供理论依据。

  6. Advances in nuclear science and technology

    CERN Document Server

    Henley, Ernest J

    1962-01-01

    Advances in Nuclear Science and Technology, Volume 1 provides an authoritative, complete, coherent, and critical review of the nuclear industry. This book covers a variety of topics, including nuclear power stations, graft polymerization, diffusion in uranium alloys, and conventional power plants.Organized into seven chapters, this volume begins with an overview of the three stages of the operation of a power plant, either nuclear or conventionally fueled. This text then examines the major problems that face the successful development of commercial nuclear power plants. Other chapters consider

  7. Hydrogen Filling Station

    Energy Technology Data Exchange (ETDEWEB)

    Boehm, Robert F; Sabacky, Bruce; Anderson II, Everett B; Haberman, David; Al-Hassin, Mowafak; He, Xiaoming; Morriseau, Brian

    2010-02-24

    Hydrogen is an environmentally attractive transportation fuel that has the potential to displace fossil fuels. The Freedom CAR and Freedom FUEL initiatives emphasize the importance of hydrogen as a future transportation fuel. Presently, Las Vegas has one hydrogen fueling station powered by natural gas. However, the use of traditional sources of energy to produce hydrogen does not maximize the benefit. The hydrogen fueling station developed under this grant used electrolysis units and solar energy to produce hydrogen fuel. Water and electricity are furnished to the unit and the output is hydrogen and oxygen. Three vehicles were converted to utilize the hydrogen produced at the station. The vehicles were all equipped with different types of technologies. The vehicles were used in the day-to-day operation of the Las Vegas Valley Water District and monitoring was performed on efficiency, reliability and maintenance requirements. The research and demonstration utilized for the reconfiguration of these vehicles could lead to new technologies in vehicle development that could make hydrogen-fueled vehicles more cost effective, economical, efficient and more widely used. In order to advance the development of a hydrogen future in Southern Nevada, project partners recognized a need to bring various entities involved in hydrogen development and deployment together as a means of sharing knowledge and eliminating duplication of efforts. A road-mapping session was held in Las Vegas in June 2006. The Nevada State Energy Office, representatives from DOE, DOE contractors and LANL, NETL, NREL were present. Leadership from the National hydrogen Association Board of Directors also attended. As a result of this session, a roadmap for hydrogen development was created. This roadmap has the ability to become a tool for use by other road-mapping efforts in the hydrogen community. It could also become a standard template for other states or even countries to approach planning for a hydrogen

  8. Hydrogen Filling Station

    Energy Technology Data Exchange (ETDEWEB)

    Boehm, Robert F; Sabacky, Bruce; Anderson II, Everett B; Haberman, David; Al-Hassin, Mowafak; He, Xiaoming; Morriseau, Brian

    2010-02-24

    Hydrogen is an environmentally attractive transportation fuel that has the potential to displace fossil fuels. The Freedom CAR and Freedom FUEL initiatives emphasize the importance of hydrogen as a future transportation fuel. Presently, Las Vegas has one hydrogen fueling station powered by natural gas. However, the use of traditional sources of energy to produce hydrogen does not maximize the benefit. The hydrogen fueling station developed under this grant used electrolysis units and solar energy to produce hydrogen fuel. Water and electricity are furnished to the unit and the output is hydrogen and oxygen. Three vehicles were converted to utilize the hydrogen produced at the station. The vehicles were all equipped with different types of technologies. The vehicles were used in the day-to-day operation of the Las Vegas Valley Water District and monitoring was performed on efficiency, reliability and maintenance requirements. The research and demonstration utilized for the reconfiguration of these vehicles could lead to new technologies in vehicle development that could make hydrogen-fueled vehicles more cost effective, economical, efficient and more widely used. In order to advance the development of a hydrogen future in Southern Nevada, project partners recognized a need to bring various entities involved in hydrogen development and deployment together as a means of sharing knowledge and eliminating duplication of efforts. A road-mapping session was held in Las Vegas in June 2006. The Nevada State Energy Office, representatives from DOE, DOE contractors and LANL, NETL, NREL were present. Leadership from the National hydrogen Association Board of Directors also attended. As a result of this session, a roadmap for hydrogen development was created. This roadmap has the ability to become a tool for use by other road-mapping efforts in the hydrogen community. It could also become a standard template for other states or even countries to approach planning for a hydrogen

  9. Nuclear control

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Wan Kee [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-02-01

    International cooperation in nuclear industries requires nuclear control as prerequisites. The concept of nuclear control is based on the Treaty on the Non-proliferation of Nuclear Weapon (NPT). The International Atomic Energy Agency (IAEA) plays central role in implementing nuclear control. Nuclear control consists of nuclear safeguards, physical protection, and export/import control. Each member state of NPT is subject to the IAEA`s safeguards by concluding safeguards agreements with the IAEA. IAEA recommends member states to implement physical protection on nuclear materials by `The Physical Protection of Nuclear Material` and `The Convention on the Physical Protection of Nuclear Material` of IAEA. Export/Import Control is to deter development of nuclear weapons by controlling international trade on nuclear materials, nuclear equipments and technology. Current status of domestic and foreign nuclear control implementation including recent induction of national inspection system in Korea is described and functions of recently set-up Technology Center for Nuclear Control (TCNC) under the Korea Atomic Energy Research Institute (KAERI) are also explained. 6 tabs., 11 refs. (Author).

  10. 某核电站循环水泵房结构的地震反应分析%Earthquake response analysis of circulation water pump house in nuclear power station

    Institute of Scientific and Technical Information of China (English)

    裴强; 薛志成

    2011-01-01

    文中运用动力时程反应分析方法,针对某百万千瓦级核电厂,利用Ansys对循环水泵房结构进行了抗震分析.针对循环水泵房结构场地岩性、结构特点,分别考虑不同设计水位、运行和检修情况、波浪压力、静动水压力和土压力以及地震荷载的组合工况,对结构进行了抗震性能计算分析,得到结构构件各个截面上内力包络,该成果对循环水泵房结构设计具有参考价值和指导意义.%Using dynamic time-history response analysis method, seismic analysis of circulation water pump house in the million-kilowatt nuclear power plant is carried out in this paper. Based on rock properties and structural characteristics of circulating water pump house, all kinds of combination with different design water levels, operation and maintenance conditions, wave pressure, static and dynamic water pressure and soil pressure and seismic loadings are considered. The internal force envelope of each section of the structure is obtained and the results can provide reference value and guidance significance for the structural design of circulating water pump house.

  11. Emergency Medical Service (EMS) Stations

    Data.gov (United States)

    Kansas Data Access and Support Center — EMS Locations in Kansas The EMS stations dataset consists of any location where emergency medical services (EMS) personnel are stationed or based out of, or where...

  12. Automatic Traffic Recorder (ATR) Stations

    Data.gov (United States)

    Department of Homeland Security — The data included in the GIS Traffic Stations Version database have been assimilated from station description files provided by FHWA for Weigh-in-Motion (WIM), and...

  13. Mesocarnivore Photo Stations [ds26

    Data.gov (United States)

    California Department of Resources — This database was established to record furbearer and raptor presence through photographs taken at camera stations. The general study area where camera stations were...

  14. Weigh-in-Motion Stations

    Data.gov (United States)

    Department of Homeland Security — The data included in the GIS Traffic Stations Version database have been assimilated from station description files provided by FHWA for Weigh-in-Motion (WIM), and...

  15. 47 CFR 80.519 - Station identification.

    Science.gov (United States)

    2010-10-01

    ... MARITIME SERVICES Private Coast Stations and Marine Utility Stations § 80.519 Station identification. (a) Stations must identify transmissions by announcing in the English language the station's assigned call sign...) Marine utility stations, private coast stations, and associated hand-held radios, when...

  16. 78 FR 66385 - Omaha Public Power District Fort Calhoun Station, Unit 1; Exemption

    Science.gov (United States)

    2013-11-05

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Omaha Public Power District Fort Calhoun Station, Unit 1; Exemption 1.0 Background Omaha Public Power District (OPPD, the licensee) is the holder of Renewed Facility Operating License No. DPR-40, which authorizes operation of Fort Calhoun Station...

  17. 78 FR 37592 - Omaha Public Power District, Fort Calhoun Station, Unit 1; Exemption

    Science.gov (United States)

    2013-06-21

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Omaha Public Power District, Fort Calhoun Station, Unit 1; Exemption 1.0 Background Omaha Public Power District (OPPD, the licensee) is the holder of Facility Operating License, which authorizes operation of Fort Calhoun Station (FCS), Unit 1....

  18. Battery charging stations

    Energy Technology Data Exchange (ETDEWEB)

    Bergey, M.

    1997-12-01

    This paper discusses the concept of battery charging stations (BCSs), designed to service rural owners of battery power sources. Many such power sources now are transported to urban areas for recharging. A BCS provides the opportunity to locate these facilities closer to the user, is often powered by renewable sources, or hybrid systems, takes advantage of economies of scale, and has the potential to provide lower cost of service, better service, and better cost recovery than other rural electrification programs. Typical systems discussed can service 200 to 1200 people, and consist of stations powered by photovoltaics, wind/PV, wind/diesel, or diesel only. Examples of installed systems are presented, followed by cost figures, economic analysis, and typical system design and performance numbers.

  19. The Dynamic Response and Stability Analysis of Water Diversion Dike at a Nuclear Power Station%某核电站取水导流堤动力响应及稳定性分析

    Institute of Scientific and Technical Information of China (English)

    赵杰; 王桂萱; 郑洋

    2013-01-01

    将土体简化为Hardin-Drnevich等效线性模型,运用有效应力动力分析方法,得到SL1和SL2地震动作用下莱核电导流堤的稳定安全系数、液化区分布以及震后残余变形.分别采用整个地震过程中的最小安全系数和最小平均安全系数评价了导流堤的稳定性,对计算结果进行了比对.SL1地震动作用下,导流堤地基砂土液化范围较小,不会影响导流堤结构的正常使用;SL2地震动作用下,导流堤地基土层中的砂土发生了大面积的液化,导流堤发生了较大的变形,但不至于使导流堤整体向渠心滑移,不会影响到核电厂的安全用水.本文成果对类似工程抗震设计具有一定的参考价值和指导意义.%Abstract:This paper uses the Hardin-Drnevich equivalent linear model and dynamic effective stress analysis method to simulate the dynamic behavior of soil,gets the factor of safety,liquefaction zone distribution and seismic residual deformation of a diversion dike under seismic load of SL1 and SL2.The paper also uses the minimum safety factor and average minimum safety factor in the whole process of an earthquake to evaluate the stability of the diversion dike under different seismic action and evaluates the results.The liquefaction range in the diversion dike foundation is smaller under SL2 than under SL1.So it does not affect the normal use of diversion dike structure.Under seismic load of SL2,diversion dike foundation in sandy soil liquefies over a large area,resulting in large deformation.But the diversion dam does not slide down to the ditch in whole,so the use of water in the nuclear power plant is safe.The results of this paper have a certain reference value and guidance to similar engineering.

  20. Space Station fluid management logistics

    Science.gov (United States)

    Dominick, Sam M.

    1990-01-01

    Viewgraphs and discussion on space station fluid management logistics are presented. Topics covered include: fluid management logistics - issues for Space Station Freedom evolution; current fluid logistics approach; evolution of Space Station Freedom fluid resupply; launch vehicle evolution; ELV logistics system approach; logistics carrier configuration; expendable fluid/propellant carrier description; fluid carrier design concept; logistics carrier orbital operations; carrier operations at space station; summary/status of orbital fluid transfer techniques; Soviet progress tanker system; and Soviet propellant resupply system observations.

  1. Air and radiation monitoring stations

    CERN Multimedia

    AUTHOR|(SzGeCERN)582709

    2015-01-01

    CERN has around 100 monitoring stations on and around its sites. New radiation measuring stations, capable of detecting even lower levels of radiation, were installed in 2014. Two members of HE-SEE group (Safety Engineering and Environment group) in front of one of the new monitoring stations.

  2. Thermal management of space stations

    Institute of Scientific and Technical Information of China (English)

    2001-01-01

    Thermal management aims at making full use of energy resources available in the space station to reduce energy consumption, waste heat rejection and the weight of the station. It is an extension of the thermal control. This discussion introduces the concept and development of thermal management, presents the aspects of thermal management and further extends its application to subsystems of the space station.

  3. Build Your Own Space Station

    Science.gov (United States)

    Bolinger, Allison

    2016-01-01

    This presentation will be used to educate elementary students on the purposes and components of the International Space Station and then allow them to build their own space stations with household objects and then present details on their space stations to the rest of the group.

  4. 核电厂控制棒导向筒半方管真空电子束焊接的试验研究%Manufacturing Process of Electric Beam Welding on Control Rod Guide Tube of Million-kilowatt-class Nuclear Power Station

    Institute of Scientific and Technical Information of China (English)

    张斌; 吴义党; 刘鸣宇; 张其先; 陈洪

    2013-01-01

    百万千瓦级核电站控制棒导向筒中半方管采用真空电子束进行焊接.本文制定了合理的试验方案,对真空电子束焊接的热循环曲线与焊缝及附近区域残余应力的分布进行了试验测量,并分析了其热循环与残余应力的特征,为更好的控制焊接质量与制造精度提供依据.%The control rod guide tube of million-kilowatt-class nuclear power station was welded by electric beam welding. A test plan for the measurement on welding thermal circulation and residual stress was provided. The character and relationship of welding thermal circulation and residual stress were analyzed in order to provide a practical basis for improving the welding quality and manufacturing precision.

  5. The Use and Improvement of Mechanical Interlock in the Batteries Test Loops System of A nuclear power station%机械联锁在A核电站蓄电池放电系统中的应用及改进

    Institute of Scientific and Technical Information of China (English)

    张瑞明; 刘盼; 雷亚清

    2013-01-01

    In order to make discharge safely of the Batteries, we take use of mechanical interlock in A nuclear power station. Base on the deep analysis of mechanical interlock and interlock scheme, we shape the improvement plan. The result shows that mechanical interlock can avoid man-made mistake, the improvement solution can reduce the man-made risk, improve the system reliability.%为了保证蓄电池系统安全可靠放电,A核电站引入了机械联锁装置。本文通过对机械联锁装置的研究以及对联锁方案的深入分析,制定了改进方案。分析以及试验结果表明,机械联锁装置可以有效避免人因失误,改进后的机械联锁方案更能降低人因风险,增强系统的安全可靠性。

  6. Centre Exposure Testing Technology of PST Safe-End-Welds of RPV in Nuclear Power Station%核电站反应堆压力容器接管安全端焊缝役前192Ir源中心曝光射线检测技术

    Institute of Scientific and Technical Information of China (English)

    李得彬

    2011-01-01

    介绍了岭澳Ⅱ期核电站4号机组反应堆压力容器(RPV)接管安全端役前(PSI)射线检查技术。依据法国压水堆核电站设计建造标准RCC-M和在役检查标准RSE—M,总结了反应堆压力容器接管安全端射线检测的技术要点;同时还介绍了RCC-M和RSE—M标准中的一些特别规定。%This thesis introduces the PSI RT inspection technology of safe-end-welds of NO. 4 unit's RPV in Ling'ao Nuclear Power Station Period Ⅱ. According to French PWR's standards REEM and RSE-M, it concludes the key technological points in safe-end-welds of RPV's PSI RT inspection. Meanwhile, it also introduces some special stipulations in RCC-M and RSE-M standards.

  7. White Paper on Nuclear Astrophysics

    CERN Document Server

    Arcones, Almudena; Beers, Timothy; Berstein, Lee; Blackmon, Jeff; Bronson, Messer; Brown, Alex; Brown, Edward; Brune, Carl; Champagne, Art; Chieffi, Alessandro; Couture, Aaron; Danielewicz, Pawel; Diehl, Roland; El-Eid, Mounib; Escher, Jutta; Fields, Brian; Frohlich, Carla; Herwig, Falk; Hix, William Raphael; Iliadis, Christian; Lynch, William; McLaughlin, Gail; Meyer, Bradley; Mezzacappa, Anthony; Nunes, Filomena; O'Shea, Brian; Prakash, Madappa; Pritychenko, Boris; Reddy, Sanjay; Rehm, Ernst; Rogachev, Grigory; Rutledge, Robert; Schatz, Hendrik; Smith, Michael; Stairs, Ingrid; Steiner, Andrew; Strohmayer, Tod; Timmes, Frank; Townsley, Dean; Wiescher, Michael; Zegers, Remco; Zingale, Michael

    2016-01-01

    This white paper informs the nuclear astrophysics community and funding agencies about the scientific directions and priorities of the field and provides input from this community for the 2015 Nuclear Science Long Range Plan. It summarizes the outcome of the nuclear astrophysics town meeting that was held on August 21-23, 2014 in College Station at the campus of Texas A&M University in preparation of the NSAC Nuclear Science Long Range Plan. It also reflects the outcome of an earlier town meeting of the nuclear astrophysics community organized by the Joint Institute for Nuclear Astrophysics (JINA) on October 9- 10, 2012 Detroit, Michigan, with the purpose of developing a vision for nuclear astrophysics in light of the recent NRC decadal surveys in nuclear physics (NP2010) and astronomy (ASTRO2010). The white paper is furthermore informed by the town meeting of the Association of Research at University Nuclear Accelerators (ARUNA) that took place at the University of Notre Dame on June 12-13, 2014. In summ...

  8. Study on the Welding Performance of SA738Gr.B Steel for the Safety Shell of Nuclear Power Station%核电站安全壳用SA738Gr.B钢板焊接性能研究

    Institute of Scientific and Technical Information of China (English)

    蒋善玉

    2015-01-01

    以核电站安全壳用42.5 mm厚SA738Gr.B钢板为试验材料,研究了熔化极气体保护焊焊接过程中的热输入以及焊后热处理对试验钢焊接接头组织和性能的影响。结果表明,随着焊接热输入量的增加,焊接接头的低温冲击功有先增大后减小的趋势;抗拉强度相差不大;而焊后热处理对焊接接头的力学性能影响较小。随着线能量的增大,针状铁素体减小且伴随着一定程度的粗化,粗大的先共析铁素体组织明显增多。焊接热输入量在1.2~2.0 kJ/mm范围内焊接时,焊接接头均可获得良好的综合力学性能。焊后消除应力热处理对焊接接头的性能影响不大,当采用较大线能量进行焊接时,建议进行焊后热处理以减小残余拉应力。%The SA738Gr.B steel plate with 42.5 mm thickness for the safety shell of a nuclear power plant is used as the experimental material, the GMAW welding heat input and post weld heat treatment on the microstructure and properties of welded joint were studied. The results show that, with increasing of the welding heat input, low temperature impact toughness of welded joint increased firstly and then decreased;the tensile strength difference is lesser, and the post weld heat treatment has little effect on the mechanical properties of the welding joint. Weld microstructure has fine and homogeneous acicular ferrite, with increasing of input energy lines, acicular ferrite prime number gradually decreased and accompanied by a certain coarsening, massive pro-eutectoid ferrite increased significantly. Welding heat input in the range of 1.2-2 kJ/mm in the range of welding, the better comprehensive mechanical properties can be obtain in welding joint, on this condition post weld stress relief heat treatment has little effect on the properties of welded joints. When using large line energy welding, heat treatment after welding is recommended to reduce the residual tensile stress.

  9. 内陆核电暂停政策对未拆迁村民的影响分析--以皖南地区WH核电站为例%Effect of Inland Nuclear Power Moratorium Policy onthe Impact of No Relocation of Villagers---A Case Study of WH Nuclear Power Station in the South of Anhui

    Institute of Scientific and Technical Information of China (English)

    韩俊丽; 杨方

    2016-01-01

    After the Fukushima nuclear accident,China's inland nuclear power projects were suspended,de-rived from a series of problems.Due to the nuclear policy adjustment,the villagers,not been moved out in WH nuclear planning area,are in the limited development state:the increase of life cost;the slowing of infrastruc-tures;the increase of the travel security risks;the negative welfare of the villagers;have a strong sense of rela-tive deprivation .therefore put the following measures:Improve the traffic conditions,properly add traffic facili-ties;reasonable adjustment of the restriction development policy;increase the transparency of the policy,im-prove the participation of the villagers;Pay attention to the psychological state of the villagers,reduce the sense of being deprived of the villagers.%福岛核事故后,我国内陆核电项目暂停,衍生出一系列问题。WH 核电站受核电政策调整的影响,规划区内尚未拆迁的村民处于发展受限的状态:村民生活成本增加;基础设施发展缓滞;出行安全隐患增加;福利“负面化”;相对剥夺感较为强烈。为此提出以下几点措施:改善交通条件,适当增设交通设施;合理的调整限制开发政策;增加政策透明度,提高村民的参与度;关注村民的心理状况,降低村民的被剥夺感。

  10. Nuclear Chemistry.

    Science.gov (United States)

    Chemical and Engineering News, 1979

    1979-01-01

    Provides a brief review of the latest developments in nuclear chemistry. Nuclear research today is directed toward increased activity in radiopharmaceuticals and formation of new isotopes by high-energy, heavy-ion collisions. (Author/BB)

  11. Nuclear Scans

    Science.gov (United States)

    Nuclear scans use radioactive substances to see structures and functions inside your body. They use a special ... images. Most scans take 20 to 45 minutes. Nuclear scans can help doctors diagnose many conditions, including ...

  12. Nuclear weapons, nuclear effects, nuclear war

    Energy Technology Data Exchange (ETDEWEB)

    Bing, G.F.

    1991-08-20

    This paper provides a brief and mostly non-technical description of the militarily important features of nuclear weapons, of the physical phenomena associated with individual explosions, and of the expected or possible results of the use of many weapons in a nuclear war. Most emphasis is on the effects of so-called ``strategic exchanges.``

  13. Nuclear structure

    CERN Document Server

    Nazarewicz, W

    1999-01-01

    Current developments in nuclear structure are discussed from a theoretical perspective. The studies of the nuclear many-body system provide us with invaluable information about the nature of the nuclear interaction, nucleonic correlations at various energy-distance scales, and the modes of the nucleonic matter.

  14. Nuclear Ambitions

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    China will begin to build the world’s first third-generation nuclear power plant at the Sanmen Nuclear Power Project in Sanmen City, coastal Zhejiang Province, in March 2009, accord-ing to the State Nuclear Power Technology Corp.

  15. Brave nuclear world

    Energy Technology Data Exchange (ETDEWEB)

    Pockley, P

    1999-05-01

    Two announcements have confirmed that the current Australian government intends to realize the unfulfilled dream of the Menzies era for Australia to become a `nuclear nation` by approving a new `research reactor` and a new uranium mine. Meanwhile, the government is working hard to overturn UNESCO`s recommendation to stop the development of the Jabiluka uranium mine. And, an international proposal to store in Australia stockpiles of high level waste from the world`s power stations and decommissioned nuclear weapons has finally come into the open with the revelation that Pangea Resources Australia Pty Ltd has presented a summary proposal to the government. Though rejected, the plan remains active. Central to the rush to capitalise on Australia`s uranium resources is Environment Minister, Senator Robert Hill, whose formal approvals for the reactor and the mine have been legally essential

  16. Designing Space Station

    Science.gov (United States)

    1986-01-01

    An overview of preparations for the construction of Space Station Freedom (SSF) is presented. The video includes footage of astronauts testing materials for erectable structures in space both in the Shuttle bay while in orbit and in a neutral buoyancy tank at McDonald Douglas' Underwater Test Facility. Also shown are footage of robot systems that will assist the astronauts in building SSF, a computer simulation of an Orbiting Maneuvering Vehicle, solar dynamic mirrors that will power SSF, and mockups of the living quarters of the SSF.

  17. Compressor station layout considerations

    Energy Technology Data Exchange (ETDEWEB)

    Kurz, Rainer; Ohanian, Sebouh; Lubomirsky, Matt [Solar Turbines Incorporated, San Diego, CA (United States)

    2003-07-01

    This paper discusses issues that influence the decision on the arrangement of compressors and the type of equipment in gas pipeline compressor stations. Different concepts such as multiple small units versus single large units are considered, both regarding their impact on the individual station and the overall pipeline. The necessity of standby units is discussed. Various concepts for drivers (gas turbine, gas motor and electric motor) and compressors (centrifugal and reciprocating) are analyzed. The importance of considering all possible operating conditions is stressed. With the wide range of possible operating conditions for the pipeline in mind, the discussion is brought into the general context of operational flexibility, availability, reliability, installation issues, remote control, and operability of gas turbine driven centrifugal compressors compared to other solutions such as electric motor driven compressors or gas engine driven reciprocating compressors. The impact of different concepts on emissions and fuel cost is discussed. Among the assumptions in this paper are the performance characteristics of the compressor. This paper outlines how these performance characteristics influence the conclusions. (author)

  18. The UAE. Lessons learned from a new nuclear regulator

    Energy Technology Data Exchange (ETDEWEB)

    Kraev, Kamen [NucNet, Brussels (Belgium)

    2015-12-15

    The United Arab Emirates (UAE) is building four South Korean APR-1400 reactors at the Barakah nuclear site. The first is scheduled to enter into commercial operation in 2017. Christer Viktorsson, Director General of the United Arabic Emirate's(UAE) Federal Office for Nuclear Regulation, talks to NucNet about the challenges of establishing a nuclear regulatory body from scratch in a country where nuclear stations have never been built before.

  19. Reactor coolant pump shaft seal stability during station blackout

    Energy Technology Data Exchange (ETDEWEB)

    Rhodes, D B; Hill, R C; Wensel, R G

    1987-05-01

    Results are presented from an investigation into the behavior of Reactor Coolant Pump shaft seals during a potential station blackout (loss of all ac power) at a nuclear power plant. The investigation assumes loss of cooling to the seals and focuses on the effect of high temperature on polymer seals located in the shaft seal assemblies, and the identification of parameters having the most influence on overall hydraulic seal performance. Predicted seal failure thresholds are presented for a range of station blackout conditions and shaft seal geometries.

  20. A simple decay-spectroscopy station at CRIS-ISOLDE

    Science.gov (United States)

    Lynch, K. M.; Cocolios, T. E.; Althubiti, N.; Farooq-Smith, G. J.; Gins, W.; Smith, A. J.

    2017-02-01

    A new decay-spectroscopy station (DSS2.0) has been designed by the CRIS collaboration for use at the radioactive ion beam facility, ISOLDE. With the design optimised for both charged-particle and γ-ray detection, the DDS2.0 allows high-efficiency decay spectroscopy to be performed. The DSS2.0 complements the existing decay-spectroscopy system at the CRIS experiment, and together provide the ability to perform laser-assisted nuclear decay spectroscopy on both ground state and long-lived isomeric species. This paper describes the new decay-spectroscopy station and presents the characterisation studies that have recently been performed.

  1. China's First Salvaging Robot for Nuclear Power Plants

    Institute of Scientific and Technical Information of China (English)

    2006-01-01

    @@ Researchers from the CAS Institute of Optics and Electronics in Chengdu,capital of southwest China's Sichuan Province, have been successful in building China's first robot for searching and retrieving underwater foreign objects in nuclear power stations.

  2. Hydrogen Fuelling Stations

    DEFF Research Database (Denmark)

    Rothuizen, Erasmus Damgaard

    . A system consisting of one high pressure storage tank is used to investigate the thermodynamics of fuelling a hydrogen vehicle. The results show that the decisive parameter for how the fuelling proceeds is the pressure loss in the vehicle. The single tank fuelling system is compared to a cascade fuelling...... of the fuelling. Models of cascade systems consisting of between 1 and 8 tanks have been used to analyse the effect of the number of tanks at the station with respect to energy consumption. An optimisation using a parameter variation of the tanks volumes and pressures is performed, to reduce the energy...... in accordance with the fuelling protocol. The analysis showed that it is possible to eliminate all the high pressure storage tanks from the cascade system, using one of the other fuelling systems. The energy consumption of the direct compression system was 18 % lower than for the two other systems. The exergy...

  3. Application for the Tape Station

    CERN Document Server

    Solero, A

    2003-01-01

    The Tape Station is used as an Isolde facility to observe the variations of intensity and the lifespan of certain isotopes. A Siemens Simatic FM-352-5 module controls the Tape Station in a PLC system then a DSC controls the PLC, which will be controlled the Tape station program. During the Isolde consolidation project, the Tape Station has been rebuilt, and the control system has been fully integrated in the PS control. Finally, a new application has been written in JAVA Development kit 1.4 and the PS Java environment. The main purpose of this note is to explain how to use this program.

  4. Laser ranging ground station development

    Science.gov (United States)

    Faller, J. E.

    1973-01-01

    The employment of ground to conduct radar range measurements of the lunar distance is discussed. The advantages of additional ground stations for this purpose are analyzed. The goals which are desirable for any new type of ranging station are: (1) full time availability of the station for laser ranging, (2) optimization for signal strength, (3) automation to the greatest extent possible, (4) the capability for blind pointing, (5) reasonable initial and modest operational costs, and (6) transportability to enhance the value of the station for geophysical purposes.

  5. The Calern atmospheric turbulence station

    Science.gov (United States)

    Chabé, Julien; Ziad, Aziz; Fantéï-Caujolle, Yan; Aristidi, Éric; Renaud, Catherine; Blary, Flavien; Marjani, Mohammed

    2016-07-01

    From its long expertise in Atmospheric Optics, the Observatoire de la Côte d'Azur and the J.L. Lagrange Laboratory have equipped the Calern Observatory with a station of atmospheric turbulence measurement (CATS: Calern Atmospheric Turbulence Station). The CATS station is equipped with a set of complementary instruments for monitoring atmospheric turbulence parameters. These new-generation instruments are autonomous within original techniques for measuring optical turbulence since the first meters above the ground to the borders of the atmosphere. The CATS station is also a support for our training activities as part of our Masters MAUCA and OPTICS, through the organization of on-sky practical works.

  6. Photochemical Assessment Monitoring Stations (PAMS)

    Data.gov (United States)

    U.S. Environmental Protection Agency — Photochemical Assessment Monitoring Stations (PAMS). This file provides information on the numbers and distribution (latitude/longitude) of air monitoring sites...

  7. Study on Design and Performance of Anti-cavitation Erosion Coatings of LCQ Valve Splitter at Tianwan Nuclear Power Station%田湾核电站LCQ阀门分流片抗空蚀涂层设计及其性能研究

    Institute of Scientific and Technical Information of China (English)

    刘永生; 黄磊; 张云乾; 丁彰雄; 冯驰; 王韶毅; 邓帮华

    2015-01-01

    本文在分析核电站LCQ阀门分流片的空蚀失效机理基础上,设计了五种合金与金属陶瓷涂层.采用氧乙炔火焰喷熔和超音速火焰喷涂(HVOF)工艺分别制备了三种Ni基合金涂层与两种WC基金属陶瓷涂层;通过超声波振动空蚀试验装置对这些涂层进行抗空蚀试验,研究这些涂层的抗空蚀性能.结果表明:NiCrBSiMo喷熔层具有最优异的抗空蚀性能,可望应用于LCQ阀门分流片.%In this paper, on basis of the cavitation erosion failure mechanism of the LCQ valve splitter at nuclear power station, five kinds of alloy and cermet coatings were designed. Three kinds of nickel-based alloy coatings and two kinds of WC based cermet coatings were respectively deposited by oxyacetylene flame spraying and fusing process and High Velocity Oxy-Fuel spray(HVOF). Then the cavitation erosion resistance of these coatings was studied by ultrasonic vibration device. Results showed thatNiCrBSiMo coating prepared by spraying and fusing process has the most excellent anti-cavitation erosion performance,it can be applied to the LCQ valve splitter.

  8. New application computer control comprehensive radiological and dosimetry of the Cofrentes nuclear power station and its integration with environment of photo realism; Nueva aplicacion informatica de control integral radiologico y dosimetrico de la central nuclear de Cofrentes y su integracion con entorno de fotorealismo

    Energy Technology Data Exchange (ETDEWEB)

    Fragio, R.; Garcia Vidal, P.; Sollet, E.; Campos, J. J. de; Martinez Avila, M.; Llana, S. de la

    2013-09-01

    At the beginning of 2012, a new integrated information system (AGER) replaced the former software applications that supported the radiation protection service (RPS) in Cofrentes Nuclear Plant. After a deep analysis coordinated by the RPS, the Cofrentes systems IT unit and Everis company, a software solution was designed and developed using the latest IT technologies in order to increase reliability, security, scalability and usability. Furthermore, the system provides new functions that covered recently imposed requirements by official organisms and also many improvements required by the RPS in order to better monitor the individual and collective doses: ALARA Jobs management, alarms for radiation dose accumulations, monitoring of dose estimates in RWPs, integration with a photo realistic model of plant, etc. (Author)

  9. 76 FR 50274 - Terrestrial Environmental Studies for Nuclear Power Stations

    Science.gov (United States)

    2011-08-12

    ... connection with items for inclusion in guides currently being developed or improvements in all published... of your comments. Comments submitted in writing or in electronic form will be posted on the NRC Web... available online in the NRC Library at http://www.nrc.gov/reading-rm/adams.html . From this page, the...

  10. Nuclear energy: current situation and prospects to 2020.

    Science.gov (United States)

    Ion, Sue

    2007-04-15

    For close to half a century nuclear fission has been providing reliable supplies of electricity to the UK, with virtually no emissions of carbon dioxide. Over that period, the UK nuclear industry has avoided the emission of over one and a half billion tonnes of CO2. Yet no nuclear plant has been built in the UK for over two decades even though many of the stations in our current fleet are now within a decade or so of the end of their lifetime. Without new plants being ordered soon, the UK's nuclear capacity will decline dramatically, from 23% today to 3% post-2020--just as considerations of supply security and climate change are becoming increasingly important. Elsewhere in the world, many countries such as China, India, Japan, South Korea, Finland and France are building new stations. Other countries such as the USA, South Africa, and some nations that currently do not have nuclear stations (such as Indonesia and Poland) are making preparations for future nuclear stations. Globally capacity factors for nuclear plants are higher than they have ever been, averaging around 85% and with the best stations achieving well over 90%. Lifetime can be 60 years. That the economics of such stations compete well with other technologies is well founded and easily verifiable--especially in the face of rising fossil fuel prices and the pricing in of costs for CO2 emissions--both of which stand to improve the economics of nuclear energy still further. Waste volumes arising from modern plants are just a fraction of those of some earlier stations, and the technologies are in place to deal with them safely and effectively. Following recent reviews and international developments, there is growing confidence that internationally available competitive designs of nuclear plant will provide part of the solution to the UK's long-term energy needs.

  11. Naval Weapons Station Earle Reassessment

    Science.gov (United States)

    2013-12-01

    surveys for their Section 110 compliance: Architectural Resources Survey, Naval Weapons Station Earle, Monmouth County, New Jersey (Louis Berger 1999...text within brackets. Berger Report 1999 Architectural Resources Survey, Naval Weapons Station Earle, Monmouth County, New Jersey (Louis Berger... architectural treatment of buildings at NWS Earle: a traditional vernacular theme with minimal decorative detailing. This so-called minimal traditional

  12. Sighting the International Space Station

    Science.gov (United States)

    Teets, Donald

    2008-01-01

    This article shows how to use six parameters describing the International Space Station's orbit to predict when and in what part of the sky observers can look for the station as it passes over their location. The method requires only a good background in trigonometry and some familiarity with elementary vector and matrix operations. An included…

  13. Stanwell power station project

    Energy Technology Data Exchange (ETDEWEB)

    Mills, David R; J Dey, Christopher [University of Sidney, Sidney (Australia); Morrison, Graham L [University of New South Wales, Sidney (Australia)

    2000-07-01

    This paper describes the Compact Linear Fresnel Reflector (CLFR) being developed for installation at the Stanwell power station in Queensland Australia. Stanwell Corporation Limited (SCL). Solahart International, Solsearch Pty. Ltd. And the universities of Sidney and New South Wales are cooperating in the project, and this first plant being partly funded by the Australian Greenhouse Office. The solar plant will be attached to a 1440 MW(e) coal fired plant. The 17000 m{sup 2} array will be the largest array in Australia, producing a peak of 13 MW of thermal energy which will offset the use of coal in the generation of electricity. It will use direct steam generation and will feed either steam or hot water at 265 Celsius degrees directly into the power station preheating cycle. The CLFR system, first developed by the University of Sidney and Solsearch Pty. Ltd., is simple and offers small reflector size, low structural cost, fixed receiver geometry. Initial installed plant costs are approximately US$1000 per kWe, but this includes the effect of high up-front design costs and the cost should drop substantially in the second and subsequent plants. [Spanish] Proyecto de la Planta Electrica Stanwell este articulo describe el Reflector Lineal Compacto Fresnel (CLFR, siglas en ingles) que se esta desarrollando para la instalacion de la planta electrica Stanwell en Queensland, Australia. La Corporacion Stanwell Limited (SCL), Solahart International, Solsearch Pty. Ltd., las universidades de Sidney y de New South Wales estan cooperando en este proyecto, y esta primera planta esta parcialmente auspiciada por la Australian Greenhouse Office. La planta solar sera anexa a una planta de carbon de 1440 MW(e). Este arreglo de 17000 m{sup 2} sera el mayor en Australia y producira un maximo de 13 MW en energia termica la cual contrarrestara el uso del carbon en la generacion de electricidad. Utilizara generacion con vapor directo y alimentara ya sea vapor o agua caliente a 265 grados

  14. Nuclear Astrophysics

    Science.gov (United States)

    Drago, Alessandro

    2005-04-01

    The activity of the Italian nuclear physicists community in the field of Nuclear Astrophysics is reported. The researches here described have been performed within the project "Fisica teorica del nucleo e dei sistemi a multi corpi", supported by the Ministero dell'Istruzione, dell'Università e della Ricerca.

  15. 75 FR 17970 - Nine Mile Point Nuclear Station, LLC; Nine Mile Point Nuclear Station, Unit No. 2; Draft...

    Science.gov (United States)

    2010-04-08

    ... systems to collect, process, recycle, and dispose of gaseous, liquid, and solid wastes that contain..., spent ion exchange resin, and dry active waste (DAW). DAW includes paper, plastic, wood, rubber,...

  16. 75 FR 13600 - Nine Mile Point Nuclear Station, LLC, Nine Mile Point Nuclear Station, Unit No. 2; Draft...

    Science.gov (United States)

    2010-03-22

    ... waste treatment systems to collect, process, recycle, and dispose of gaseous, liquid, and solid wastes..., spent ion exchange resin, and dry active waste (DAW). DAW includes paper, plastic, wood, rubber,...

  17. 47 CFR 97.109 - Station control.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Station control. 97.109 Section 97.109... SERVICE Station Operation Standards § 97.109 Station control. (a) Each amateur station must have at least one control point. (b) When a station is being locally controlled, the control operator must be at...

  18. 47 CFR 97.207 - Space station.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Space station. 97.207 Section 97.207... SERVICE Special Operations § 97.207 Space station. (a) Any amateur station may be a space station. A holder of any class operator license may be the control operator of a space station, subject to...

  19. Nuclear stress test

    Science.gov (United States)

    ... Persantine stress test; Thallium stress test; Stress test - nuclear; Adenosine stress test; Regadenoson stress test; CAD - nuclear stress; Coronary artery disease - nuclear stress; Angina - nuclear ...

  20. Nuclear Fuel Procurement Management at Nuclear Power Plant%大亚湾核电站核燃料的采购管理

    Institute of Scientific and Technical Information of China (English)

    黄建华

    2001-01-01

    本文介绍核电站核燃料采购各循环市场状况和主要特点,并结合广东大亚湾核电站的实例阐述核电站核燃料采购的合同模式和管理要点。%The market situation of nuclear fuel cycles is highlighted. Italso summarises the possible contract models and the elements of effective management for nuclear fuel procurement at nuclear power station based upon the nuclear fuel procurement practice of Guangdong Daya Bay Nuclear Power Station (GNPS).

  1. Nuclear Physics

    CERN Document Server

    Savage, Martin J

    2016-01-01

    Lattice QCD is making good progress toward calculating the structure and properties of light nuclei and the forces between nucleons. These calculations will ultimately refine the nuclear forces, particularly in the three- and four-nucleon sector and the short-distance interactions of nucleons with electroweak currents, and allow for a reduction of uncertainties in nuclear many-body calculations of nuclei and their reactions. After highlighting their importance, particularly to the Nuclear Physics and High-Energy Physics experimental programs, I discuss the progress that has been made toward achieving these goals and the challenges that remain.

  2. Biotechnology opportunities on Space Station

    Science.gov (United States)

    Deming, Jess; Henderson, Keith; Phillips, Robert W.; Dickey, Bernistine; Grounds, Phyllis

    1987-01-01

    Biotechnology applications which could be implemented on the Space Station are examined. The advances possible in biotechnology due to the favorable microgravity environment are discussed. The objectives of the Space Station Life Sciences Program are: (1) the study of human diseases, (2) biopolymer processing, and (3) the development of cryoprocessing and cryopreservation methods. The use of the microgravity environment for crystal growth, cell culturing, and the separation of biological materials is considered. The proposed Space Station research could provide benefits to the fields of medicine, pharmaceuticals, genetics, agriculture, and industrial waste management.

  3. Regulatory oversight report 2008 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2008 ueber die nukleare Sicherheit in den schweizerischen Kernanlagen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-04-15

    This annual report issued by the Swiss Federal Nuclear Inspectorate (ENSI) reports on the work carried out by the Inspectorate in 2008. This report reviews the regulatory activities in the four Swiss nuclear power stations and in four further nuclear installations in various Swiss research facilities. It deals with topics such as operational details, technologies in use, radiation protection, radioactive wastes, emergency dispositions, personnel and provides an assessment of operations from the safety point of view. Also, the transportation of nuclear materials - both nuclear fuels and nuclear wastes - is reported on. General topics discussed include probabilistic safety analyses and accident management, earthquake damage analysis and agreements on nuclear safety. The underground disposal of highly-radioactive nuclear wastes and work done in the rock laboratories are discussed, as are proposals for additional nuclear power stations.

  4. The status and prospective of environmental radiation monitoring stations in Saudi Arabia

    Science.gov (United States)

    Al-Kheliewi, Abdullah S.; Holzheimer, Clous

    2014-09-01

    The use of nuclear technology requires an environmental monitoring program to ensure the safety of the environment, and to protect people from the hazards of radioactive materials, and nuclear accidents. Nuclear accidents are unique, for they incur effects that surpass international frontiers, and can even have a long lasting impact on Earth. Such was the case of the Chernobyl accident in the Ukraine on April 6, 1986. For that purpose, international and national efforts come together to observe for any nuclear or radioactive accident. Many states, including Saudi Arabia which oversees the operation of the National Radiation, Environmental and Early Monitoring Stations, The Radiation Monitoring Stations(RMS's) are currently scattered across 35 cities in the country,. These locations are evaluated based on various technological criteria such as border cities, cities of high population density, wind direction, etc. For new nuclear power plants hovering around, it is strongly recommended to increase the number of radiation monitoring stations to warn against any threat that may arise from a nuclear leak or accident and to improve the performance of the existing RMS's. SARA (Spectroscopic Monitoring Station for air) should be implemented due to the high sensitivity to artificial radiation, automatic isotope identification, free of maintenance, and fully independent due to solar power supply (incl. battery backup) and wireless communication (GPRS).

  5. The status and prospective of environmental radiation monitoring stations in Saudi Arabia

    Energy Technology Data Exchange (ETDEWEB)

    Al-Kheliewi, Abdullah S. [National Center for Radiation Protection, King Abdulaziz City for Science and Technology, 11442 Riyadh (Saudi Arabia); Holzheimer, Clous [ENVINET GmbH, Environmental Radiation Detection, Hans-Pinsel-Straße 4, 85540 Haar (Munich) (Germany)

    2014-09-30

    The use of nuclear technology requires an environmental monitoring program to ensure the safety of the environment, and to protect people from the hazards of radioactive materials, and nuclear accidents. Nuclear accidents are unique, for they incur effects that surpass international frontiers, and can even have a long lasting impact on Earth. Such was the case of the Chernobyl accident in the Ukraine on April 6, 1986. For that purpose, international and national efforts come together to observe for any nuclear or radioactive accident. Many states, including Saudi Arabia which oversees the operation of the National Radiation, Environmental and Early Monitoring Stations, The Radiation Monitoring Stations(RMS’s) are currently scattered across 35 cities in the country,. These locations are evaluated based on various technological criteria such as border cities, cities of high population density, wind direction, etc. For new nuclear power plants hovering around, it is strongly recommended to increase the number of radiation monitoring stations to warn against any threat that may arise from a nuclear leak or accident and to improve the performance of the existing RMS’s. SARA (Spectroscopic Monitoring Station for air) should be implemented due to the high sensitivity to artificial radiation, automatic isotope identification, free of maintenance, and fully independent due to solar power supply (incl. battery backup) and wireless communication (GPRS)

  6. Non-Coop Station History (Unindexed)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Station history documentation for stations outside the US Cooperative Observer network. Documents should be compared with those in the Non-Coop Station History...

  7. 47 CFR 80.107 - Service of private coast stations and marine-utility stations.

    Science.gov (United States)

    2010-10-01

    ...-utility stations. 80.107 Section 80.107 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED... Operating Procedures-Land Stations § 80.107 Service of private coast stations and marine-utility stations. A private coast station or a marine-utility station is authorized to transmit messages necessary for...

  8. 47 CFR 73.6016 - Digital Class A TV station protection of TV broadcast stations.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 4 2010-10-01 2010-10-01 false Digital Class A TV station protection of TV... Class A TV station protection of TV broadcast stations. Digital Class A TV stations must protect authorized TV broadcast stations, applications for minor changes in authorized TV broadcast stations filed...

  9. Nuclear Disarmament.

    Science.gov (United States)

    Johnson, Christopher

    1982-01-01

    Material about nuclear disarmament and the arms race should be included in secondary school curricula. Teachers can present this technical, controversial, and frightening material in a balanced and comprehensible way. Resources for instructional materials are listed. (PP)

  10. Nuclear reaction

    CERN Multimedia

    Penwarden, C

    2001-01-01

    At the European Research Organization for Nuclear Research, Nobel laureates delve into the mysteries of particle physics. But when they invited artists from across the continent to visit their site in Geneva, they wanted a new kind of experiment.

  11. Nuclear Medicine

    Science.gov (United States)

    ... here Home » Science Education » Science Topics » Nuclear Medicine SCIENCE EDUCATION SCIENCE EDUCATION Science Topics Resource Links for ... administered by inhalation, by oral ingestion, or by direct injection into an organ. The mode of tracer ...

  12. Nuclear astrophysics

    Energy Technology Data Exchange (ETDEWEB)

    Arnould, M. [Institut d' Astronomie et d' Astrophysique, Universite Libre de Bruxelles, Bruxelles (Belgium); Takahashi, K. [Max-Planck-Institut fuer Astrophysik, Garching (Germany)

    1999-03-01

    Nuclear astrophysics is that branch of astrophysics which helps understanding of the Universe, or at least some of its many faces, through the knowledge of the microcosm of the atomic nucleus. It attempts to find as many nuclear physics imprints as possible in the macrocosm, and to decipher what those messages are telling us about the varied constituent objects in the Universe at present and in the past. In the last decades much advance has been made in nuclear astrophysics thanks to the sometimes spectacular progress made in the modelling of the structure and evolution of the stars, in the quality and diversity of the astronomical observations, as well as in the experimental and theoretical understanding of the atomic nucleus and of its spontaneous or induced transformations. Developments in other subfields of physics and chemistry have also contributed to that advance. Notwithstanding the accomplishment, many long-standing problems remain to be solved, and the theoretical understanding of a large variety of observational facts needs to be put on safer grounds. In addition, new questions are continuously emerging, and new facts endangering old ideas. This review shows that astrophysics has been, and still is, highly demanding to nuclear physics in both its experimental and theoretical components. On top of the fact that large varieties of nuclei have to be dealt with, these nuclei are immersed in highly unusual environments which may have a significant impact on their static properties, the diversity of their transmutation modes, and on the probabilities of these modes. In order to have a chance of solving some of the problems nuclear astrophysics is facing, the astrophysicists and nuclear physicists are obviously bound to put their competence in common, and have sometimes to benefit from the help of other fields of physics, like particle physics, plasma physics or solid-state physics. Given the highly varied and complex aspects, we pick here some specific nuclear

  13. Nuclear astrophysics

    Science.gov (United States)

    Arnould, M.; Takahashi, K.

    1999-03-01

    Nuclear astrophysics is that branch of astrophysics which helps understanding of the Universe, or at least some of its many faces, through the knowledge of the microcosm of the atomic nucleus. It attempts to find as many nuclear physics imprints as possible in the macrocosm, and to decipher what those messages are telling us about the varied constituent objects in the Universe at present and in the past. In the last decades much advance has been made in nuclear astrophysics thanks to the sometimes spectacular progress made in the modelling of the structure and evolution of the stars, in the quality and diversity of the astronomical observations, as well as in the experimental and theoretical understanding of the atomic nucleus and of its spontaneous or induced transformations. Developments in other subfields of physics and chemistry have also contributed to that advance. Notwithstanding the accomplishment, many long-standing problems remain to be solved, and the theoretical understanding of a large variety of observational facts needs to be put on safer grounds. In addition, new questions are continuously emerging, and new facts endangering old ideas. This review shows that astrophysics has been, and still is, highly demanding to nuclear physics in both its experimental and theoretical components. On top of the fact that large varieties of nuclei have to be dealt with, these nuclei are immersed in highly unusual environments which may have a significant impact on their static properties, the diversity of their transmutation modes, and on the probabilities of these modes. In order to have a chance of solving some of the problems nuclear astrophysics is facing, the astrophysicists and nuclear physicists are obviously bound to put their competence in common, and have sometimes to benefit from the help of other fields of physics, like particle physics, plasma physics or solid-state physics. Given the highly varied and complex aspects, we pick here some specific nuclear

  14. Nuclear Data

    Energy Technology Data Exchange (ETDEWEB)

    White, Morgan C. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-01-23

    PowerPoint presentation targeted for educational use. Nuclear data comes from a variety of sources and in many flavors. Understanding where the data you use comes from and what flavor it is can be essential to understand and interpret your results. This talk will discuss the nuclear data pipeline with particular emphasis on providing links to additional resources that can be used to explore the issues you will encounter.

  15. Nuclear Structure

    Science.gov (United States)

    Gargano, Angela

    2003-04-01

    An account of recent studies in the field of theoretical nuclear structure is reported. These studies concern essentially research activities performed under the Italian project "Fisica Teorica del Nucleo e dei Sistemi a Molti Corpi". Special attention is addressed to results obtained during the last two years as regards the development of new many-body techniques as well as the interpretation of new experimental aspects of nuclear structure.

  16. WVU Hydrogen Fuel Dispensing Station

    Energy Technology Data Exchange (ETDEWEB)

    Davis, William [West Virginia University Research Corporation, Morgantown, WV (United States)

    2015-09-01

    The scope of this project was changed during the course of the project. Phase I of the project was to construct a site similar to the site at Central West Virginia Regional Airport in Charleston, WV to show that duplication of the site was a feasible method of conducting hydrogen stations. Phase II of the project was necessitated due to a lack of funding that was planned for the development of the station in Morgantown. The US Department of Energy determined that the station in Charleston would be dismantled and moved to Morgantown and reassembled at the Morgantown site. This necessitated storage of the components of the station for almost a year at the NAFTC Headquarters which caused a number of issues with the equipment that will be discussed in later portions of this report. This report will consist of PHASE I and PHASE II with discussions on each of the tasks scheduled for each phase of the project.

  17. Interior Alaska Gravity Station Data

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The gravity station data total 9416 records. This data base was received in March 1997. Principal gravity parameters include Free-air Anomalies which have been...

  18. Gravity Station Data for Spain

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The gravity station data total 28493 records. This data base was received in April 1997. Principal gravity parameters include Free-air Anomalies which have been...

  19. 77 FR 30053 - Repair Stations

    Science.gov (United States)

    2012-05-21

    ... concerning this proposed rule contact John Goodwin, FAA, Repair Station Branch (AFS-340), 800 Independence....Goodwin@faa.gov . For legal questions concerning this proposed rule contact Edmund Averman, FAA, Office...

  20. Gravity Station Data for Portugal

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The gravity station data total 3064 records. This data base was received in April 1997. Principal gravity parameters include Free-air Anomalies which have been...

  1. Gas Compressor Station Economic Optimization

    Directory of Open Access Journals (Sweden)

    Rainer Kurz

    2012-01-01

    Full Text Available When considering gas compressor stations for pipeline projects, the economic success of the entire operation depends to a significant extent on the operation of the compressors involved. In this paper, the basic factors contributing to the economics are outlined, with particular emphasis on the interaction between the pipeline and the compressor station. Typical scenarios are described, highlighting the fact that pipeline operation has to take into account variations in load.

  2. Gas Compressor Station Economic Optimization

    OpenAIRE

    2012-01-01

    When considering gas compressor stations for pipeline projects, the economic success of the entire operation depends to a significant extent on the operation of the compressors involved. In this paper, the basic factors contributing to the economics are outlined, with particular emphasis on the interaction between the pipeline and the compressor station. Typical scenarios are described, highlighting the fact that pipeline operation has to take into account variations in load.

  3. Space stations systems and utilization

    CERN Document Server

    Messerschmid, Ernst

    1999-01-01

    The design of space stations like the recently launched ISS is a highly complex and interdisciplinary task. This book describes component technologies, system integration, and the potential usage of space stations in general and of the ISS in particular. It so adresses students and engineers in space technology. Ernst Messerschmid holds the chair of space systems at the University of Stuttgart and was one of the first German astronauts.

  4. Internationalization of the Space Station

    Science.gov (United States)

    Lottmann, R. V.

    1985-01-01

    Attention is given to the NASA Space Station system elements whose production is under consideration by potential foreign partners. The ESA's Columbus Program declaration encompasses studies of pressurized modules, unmanned payload carriers, and ground support facilities. Canada has expressed interest in construction and servicing facilities, solar arrays, and remote sensing facilities. Japanese studies concern a multipurpose experimental module concept. Each of these foreign investments would expand Space Station capabilities and lay the groundwork for long term partnerships.

  5. Public opinion poll on safety and regulations of nuclear energy

    Energy Technology Data Exchange (ETDEWEB)

    Park, M. I.; Park, B. I.; Lee, S. M. [Gallup Korea, Seoul (Korea, Republic of)

    2004-02-15

    The purpose of this poll is not only to research understanding on safety and regulations of nuclear energy and to compare the result by time series followed 2003 to 2002 years, also to establish the public relations strategies and to offer information for developing long-term policies. The contents of the study are on the general perception, safety, management of nuclear power station, regulations and surroundings about nuclear energy.

  6. Progress of nuclear safety research. 2002

    Energy Technology Data Exchange (ETDEWEB)

    Anoda, Yoshinari; Kudo, Tamotsu; Tobita, Tohru (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] (and others)

    2002-11-01

    JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Annual Plan for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI are the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI has taken a responsible role by providing technical experts and investigation for assistance to the government or local public body. This report summarizes the nuclear safety research activities of JAERI from April 2000 through April 2002 and utilized facilities. This report also summarizes the examination of the ruptured pipe performed for assistance to the Nuclear and Industrial Safety Agency (NISA) for investigation of the accident at the Hamaoka Nuclear Power Station Unit-1 on November, 2001. (author)

  7. Nuclear Power Plant

    Directory of Open Access Journals (Sweden)

    Analia Bonelli

    2012-01-01

    Full Text Available A description of the results for a Station Black-Out analysis for Atucha 2 Nuclear Power Plant is presented here. Calculations were performed with MELCOR 1.8.6 YV3165 Code. Atucha 2 is a pressurized heavy water reactor, cooled and moderated with heavy water, by two separate systems, presently under final construction in Argentina. The initiating event is loss of power, accompanied by the failure of four out of four diesel generators. All remaining plant safety systems are supposed to be available. It is assumed that during the Station Black-Out sequence the first pressurizer safety valve fails stuck open after 3 cycles of water release, respectively, 17 cycles in total. During the transient, the water in the fuel channels evaporates first while the moderator tank is still partially full. The moderator tank inventory acts as a temporary heat sink for the decay heat, which is evacuated through conduction and radiation heat transfer, delaying core degradation. This feature, together with the large volume of the steel filler pieces in the lower plenum and a high primary system volume to thermal power ratio, derives in a very slow transient in which RPV failure time is four to five times larger than that of other German PWRs.

  8. General Nuclear Medicine

    Science.gov (United States)

    ... Physician Resources Professions Site Index A-Z General Nuclear Medicine Nuclear medicine imaging uses small amounts of ... limitations of General Nuclear Medicine? What is General Nuclear Medicine? Nuclear medicine is a branch of medical ...

  9. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... Resources Professions Site Index A-Z Children's (Pediatric) Nuclear Medicine Children’s (pediatric) nuclear medicine imaging uses small ... of Children's Nuclear Medicine? What is Children's (Pediatric) Nuclear Medicine? Nuclear medicine is a branch of medical ...

  10. Children's (Pediatric) Nuclear Medicine

    Science.gov (United States)

    ... Professions Site Index A-Z Children's (Pediatric) Nuclear Medicine Children’s (pediatric) nuclear medicine imaging uses small amounts ... Children's Nuclear Medicine? What is Children's (Pediatric) Nuclear Medicine? Nuclear medicine is a branch of medical imaging ...

  11. 78 FR 25488 - Qualification Tests for Safety-Related Actuators in Nuclear Power Plants

    Science.gov (United States)

    2013-05-01

    ... COMMISSION Qualification Tests for Safety-Related Actuators in Nuclear Power Plants AGENCY: Nuclear..., ``Qualification Tests for Safety-Related Actuators in Nuclear Power Plants.'' DG-1235 is proposed Revision 1 of RG... Stations in order to demonstrate their ability to perform their intended safety functions under...

  12. 76 FR 56242 - Duke Energy Carolinas, LLC; Southern Nuclear Operating Company; Establishment of Atomic Safety...

    Science.gov (United States)

    2011-09-12

    ... Energy Carolinas, LLC; Southern Nuclear Operating Company; Establishment of Atomic Safety and Licensing...: Duke Energy Carolinas, LLC, (William States Lee III Nuclear Station, Units 1 and 2), Docket Nos. 52-018... From the Federal Register Online via the Government Publishing Office NUCLEAR...

  13. Behavior of primary coolant pump shaft seals during station blackout conditions

    Energy Technology Data Exchange (ETDEWEB)

    Hill, R.C.; Rhodes, D.B.

    1986-09-12

    An assessment is made of the ability of typical Reactor Coolant Pump (RCP) Shaft Seals to withstand the conditions predicted for a station blackout (loss of all alternating current power) at a nuclear power station. Several factors are identified that are key to seal stability including inlet fluid conditions, pressure downstream of the seal, and geometrical details of the seal rings. Limits for stable seal operation are determined for various combinations of these factors, and the conclusion is drawn that some RPC seals would be near the threshold of instability during a station blackout. If the threshold were exceeded, significant leakage of coolant from the primary coolant system could be expected.

  14. Parameters important to reactor coolant pump seal stability during station blackout

    Energy Technology Data Exchange (ETDEWEB)

    Hill, R.C.; Rhodes, D.B.

    1986-10-24

    An assessment is made of the ability of typical Reactor Coolant Pump (RCP) Shaft Seals to withstand the conditions predicted for a station blackout (loss of all alternating current power) at a nuclear power station. Several factors are identified that are key to seal stability including inlet fluid conditions, pressure downstream of the seal, and geometrical details of the seal rings. Limits for stable seal operation are determined for various combinations of these factors, and the conclusion is drawn that some RPC seals would be near or over the threshold of instability during a station blackout. If the threshold were exceeded, significant leakage of coolant from the primary coolant system could be expected.

  15. Nuclear astrophysics

    CERN Document Server

    Arnould, M

    1999-01-01

    Nuclear astrophysics is that branch of astrophysics which helps understanding some of the many facets of the Universe through the knowledge of the microcosm of the atomic nucleus. In the last decades much advance has been made in nuclear astrophysics thanks to the sometimes spectacular progress in the modelling of the structure and evolution of the stars, in the quality and diversity of the astronomical observations, as well as in the experimental and theoretical understanding of the atomic nucleus and of its spontaneous or induced transformations. Developments in other sub-fields of physics and chemistry have also contributed to that advance. Many long-standing problems remain to be solved, however, and the theoretical understanding of a large variety of observational facts needs to be put on safer grounds. In addition, new questions are continuously emerging, and new facts endanger old ideas. This review shows that astrophysics has been, and still is, highly demanding to nuclear physics in both its experime...

  16. Nuclear Scales

    CERN Document Server

    Friar, J L

    1998-01-01

    Nuclear scales are discussed from the nuclear physics viewpoint. The conventional nuclear potential is characterized as a black box that interpolates nucleon-nucleon (NN) data, while being constrained by the best possible theoretical input. The latter consists of the longer-range parts of the NN force (e.g., OPEP, TPEP, the $\\pi$-$\\gamma$ force), which can be calculated using chiral perturbation theory and gauged using modern phase-shift analyses. The shorter-range parts of the force are effectively parameterized by moments of the interaction that are independent of the details of the force model, in analogy to chiral perturbation theory. Results of GFMC calculations in light nuclei are interpreted in terms of fundamental scales, which are in good agreement with expectations from chiral effective field theories. Problems with spin-orbit-type observables are noted.

  17. Nuclear scales

    Energy Technology Data Exchange (ETDEWEB)

    Friar, J.L.

    1998-12-01

    Nuclear scales are discussed from the nuclear physics viewpoint. The conventional nuclear potential is characterized as a black box that interpolates nucleon-nucleon (NN) data, while being constrained by the best possible theoretical input. The latter consists of the longer-range parts of the NN force (e.g., OPEP, TPEP, the {pi}-{gamma} force), which can be calculated using chiral perturbation theory and gauged using modern phase-shift analyses. The shorter-range parts of the force are effectively parameterized by moments of the interaction that are independent of the details of the force model, in analogy to chiral perturbation theory. Results of GFMC calculations in light nuclei are interpreted in terms of fundamental scales, which are in good agreement with expectations from chiral effective field theories. Problems with spin-orbit-type observables are noted.

  18. Introduction to Space Station Freedom

    Science.gov (United States)

    Kohrs, Richard

    NASA field centers and contractors are organized to develop 'work packages' for Space Station Freedom. Marshall Space Flight Center and Boeing are building the U.S. laboratory and habitation modules, nodes, and environmental control and life support system; Johnson Space Center and McDonnell Douglas are responsible for truss structure, data management, propulsion systems, thermal control, and communications and guidance; Lewis Research Center and Rocketdyne are developing the power system. The Canadian Space Agency (CSA) is contributing a Mobile Servicing Center, Special Dextrous Manipulator, and Mobile Servicing Center Maintenance Depot. The National Space Development Agency of Japan (NASDA) is contributing a Japanese Experiment Module (JEM), which includes a pressurized module, logistics module, and exposed experiment facility. The European Space Agency (ESA) is contributing the Columbus laboratory module. NASA ground facilities, now in various stages of development to support Space Station Freedom, include: Marshall Space Flight Center's Payload Operations Integration Center and Payload Training Complex (Alabama), Johnson Space Center's Space Station Control Center and Space Station Training Facility (Texas), Lewis Research Center's Power System Facility (Ohio), and Kennedy Space Center's Space Station Processing Facility (Florida). Budget appropriations impact the development of the Space Station. In Fiscal Year 1988, Congress appropriated only half of the funds that NASA requested for the space station program ($393 million vs. $767 million). In FY 89, NASA sought $967 million for the program, and Congress appropriated $900 million. NASA's FY 90 request was $2.05 billion compared to an appropriation of $1.75 billion; the FY 91 request was $2.45 billion, and the appropriation was $1.9 billion. After NASA restructured the Space Station Freedom program in response to directions from Congress, the agency's full budget request of $2.029 billion for Space Station

  19. Nuclear Models

    Science.gov (United States)

    Fossión, Rubén

    2010-09-01

    The atomic nucleus is a typical example of a many-body problem. On the one hand, the number of nucleons (protons and neutrons) that constitute the nucleus is too large to allow for exact calculations. On the other hand, the number of constituent particles is too small for the individual nuclear excitation states to be explained by statistical methods. Another problem, particular for the atomic nucleus, is that the nucleon-nucleon (n-n) interaction is not one of the fundamental forces of Nature, and is hard to put in a single closed equation. The nucleon-nucleon interaction also behaves differently between two free nucleons (bare interaction) and between two nucleons in the nuclear medium (dressed interaction). Because of the above reasons, specific nuclear many-body models have been devised of which each one sheds light on some selected aspects of nuclear structure. Only combining the viewpoints of different models, a global insight of the atomic nucleus can be gained. In this chapter, we revise the the Nuclear Shell Model as an example of the microscopic approach, and the Collective Model as an example of the geometric approach. Finally, we study the statistical properties of nuclear spectra, basing on symmetry principles, to find out whether there is quantum chaos in the atomic nucleus. All three major approaches have been rewarded with the Nobel Prize of Physics. In the text, we will stress how each approach introduces its own series of approximations to reduce the prohibitingly large number of degrees of freedom of the full many-body problem to a smaller manageable number of effective degrees of freedom.

  20. 47 CFR 78.69 - Station records.

    Science.gov (United States)

    2010-10-01

    ... notice was given. (v) Date and time notice was given to the Flight Service Station (Federal Aviation... SERVICE General Operating Requirements § 78.69 Station records. Each licensee of a CARS station shall... time of the beginning and end of each period of transmission of each channel; (b) For all stations,...

  1. 47 CFR 73.1820 - Station log.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 4 2010-10-01 2010-10-01 false Station log. 73.1820 Section 73.1820... Rules Applicable to All Broadcast Stations § 73.1820 Station log. (a) Entries must be made in the station log either manually by a person designated by the licensee who is in actual charge of...

  2. Nuclear Assessment

    Institute of Scientific and Technical Information of China (English)

    CHARLES K.EBINGER; JOHN P.BANKS

    2010-01-01

    @@ In President Barack Obama's State of the Union address in January 2009,he called for the building of "a new generation of safe,clean nuclear power plants" This was followed by his highprofile speech in Prague in April 2009,in which he noted the need "to harness the power of nuclear energy on behalf of our efforts to combat climate change."In December 2009 in Copenhagen,he pledged the United States will reduce carbon dioxide (CO2) emissions 17 percent from 2005 levels by 2020.

  3. Nuclear effects hardened shelters

    Science.gov (United States)

    Lindke, Paul

    1990-11-01

    The Houston Fearless 76 Government Projects Group has been actively engaged for more than twenty-five years as a sub-contractor and currently as a prime contractor in the design, manufacture, repair and logistics support of custom mobile ground stations and their equipment accommodations. Other associated products include environmental control units (ECU's), mobilizers for shelters and a variety of mobile power generation units (MPU's). Since 1984, Houston Fearless 76 has designed and manufactured four 8' x 8' x 22' nuclear hardened mobile shelters. These shelters were designed to contain electronic data processing/reduction equipment. One shelter is currently being operated by the Air Force as a Defense Intelligence Agency (DIA) approved and certified Special Corrpartmented Information Facility (SCIF). During the development and manufacturing process of the shelters, we received continual technical assistance and design concept evaluations from Science Applications International Corporation (SAIC) Operations Analysis and Logistics Engineering Division and the Nondestructive Inspection Lab at McClellan AFB. SAIC was originally employed by the Air Force to design the nuclear hardening specifications applied to these shelters. The specific levels of hardening to which the shelters were designed are classified and will not be mentioned during this presentation.

  4. 77 FR 32394 - Safety Zones: Catawba Island Club Fire Works, Catawba Island Club, Port Clinton, OH; Racing for...

    Science.gov (United States)

    2012-06-01

    ... Memorial Day Fireworks event, the event known as ``Racing for Recovery, Half & Sprint,'' and for the two... & Sprint triathlon will take place on the waters of Lake Erie in the vicinity of Sterling State Park... May 27, 2012. The Racing for Recovery Half & Sprint safety zone will include all waters of Lake...

  5. The ALTCRISS project on board the International Space Station

    CERN Document Server

    Casolino, M; Minori, M; Picozza, P; Fuglesang, C; Galper, A; Popov, A; Benghin, V; Petrov, V M; Nagamatsu, A; Berger, T; Reitz, G; Durante, M; Pugliese, M; Roca, V; Cucinotta, L Sihver F; Semones, E; Shavers, M; Guarnieri, V; Lobascio, C; Castagnolo, D; Fortezza, R

    2007-01-01

    The Altcriss project aims to perform a long term survey of the radiation environment on board the International Space Station. Measurements are being performed with active and passive devices in different locations and orientations of the Russian segment of the station. The goal is to perform a detailed evaluation of the differences in particle fluence and nuclear composition due to different shielding material and attitude of the station. The Sileye-3/Alteino detector is used to identify nuclei up to Iron in the energy range above 60 MeV/n. Several passive dosimeters (TLDs, CR39) are also placed in the same location of Sileye-3 detector. Polyethylene shielding is periodically interposed in front of the detectors to evaluate the effectiveness of shielding on the nuclear component of the cosmic radiation. The project was submitted to ESA in reply to the AO in the Life and Physical Science of 2004 and data taking began in December 2005. Dosimeters and data cards are rotated every six months: up to now three lau...

  6. Nuclear Science.

    Science.gov (United States)

    Pennsylvania State Dept. of Education, Harrisburg. Bureau of Curriculum Services.

    This document is a report on a course in nuclear science for the high school curriculum. The course is designed to provide a basic but comprehensive understanding of the atom in the light of modern knowledge, and to show how people attempt to harness the tremendous energy liberated through fission and fusion reactions. The course crosses what are…

  7. Nuclear Assessment

    Institute of Scientific and Technical Information of China (English)

    CHARLES; K.; EBINGER; JOHN; P.; BANKS

    2010-01-01

    The United States needs a comprehensive policy and market-based solutions to address the challenges and demands of energy provision in President Barack Obama’s State of the Union address in January 2009, he called for the building of "a new generation of safe, clean nuclear power plants." This was followed by his high- profile speech in Prague in April 2009,

  8. Space Station technology testbed: 2010 deep space transport

    Science.gov (United States)

    Holt, Alan C.

    1993-12-01

    telepresence/kinetic processes), (3) subsystem tests of advanced nuclear power, nuclear propulsion and communication systems (using boom extensions, remote station-keeping platforms and mobile EVA crew and robots), and (4) logistics support (crew and equipment) and command and control of deep space transport assembly, maintenance, and refueling (using a station-keeping platform).

  9. Business earth stations for telecommunications

    Science.gov (United States)

    Morgan, Walter L.; Rouffet, Denis

    The current status of technology for small commercial satellite-communication earth stations is reviewed on the basis of an application study undertaken in the U.S. and Europe. Chapters are devoted to an overview of satellite communication networks, microterminal design and hardware implementation, microterminal applications, the advantages of microterminals, typical users, services provided, the U.S. market for small earth stations, network operators, and the economics of satellite and terrestrial communication services. Consideration is given to the operation of a microterminal network, standards and regulations, technological factors, space-segment requirements, and insurance aspects. Diagrams, graphs, tables of numerical data, and a glossary of terms are provided.

  10. Station blackout with reactor coolant pump seal leakage

    Energy Technology Data Exchange (ETDEWEB)

    Evinay, A. (Southern California Edison, Irvine, CA (United States))

    1993-01-01

    The U.S. Nuclear Regulatory Commission (NRC) amended its regulations in 10CFR50 with the addition of a new section, 50.63, [open quotes]Loss of All Alternating Current Power.[close quotes] The objective of these requirements is to ensure that all nuclear plants have the capability to withstand a station blackout (SBO) and maintain adequate reactor core cooling and containment integrity for a specified period of time. The NRC also issued Regulatory Guide (RG) 1.155, [open quotes]Station Blackout,[close quotes] to provide guidance for meeting the requirements of 10CFR50.63. Concurrent with RG-1.155, the Nuclear Utility Management and Resources Council (NUMARC) has developed NUMARC 87-00 to address SBO-coping duration and capabilities at light water reactors. Licensees are required to submit a topical report based on NUMARC 87-00 guidelines, to demonstrate compliance with the SBO rule. One of the key compliance criteria is the ability of the plant to maintain adequate reactor coolant system (RCS) inventory to ensure core cooling for the required coping duration, assuming a leak rate of 25 gal/min per reactor coolant pump (RCP) seal in addition to technical specification (TS) leak rate.

  11. 78 FR 784 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station; Exemption

    Science.gov (United States)

    2013-01-04

    ....F.2.c, is to ensure that licensees test and maintain interfaces among themselves and affected State... offsite authority participation, is to test and maintain interfaces among affected State and local..., published by FEMA on January 26, 2011 (ADAMS Accession No. ML11223A279). Under 10 CFR...

  12. 75 FR 11205 - Entergy Nuclear Operations, Inc; Pilgrim Nuclear Power Station Environmental Assessment and...

    Science.gov (United States)

    2010-03-10

    ... Requirements, 74 FR 13926, 13967 (March 27, 2009)]. The NRC staff's safety evaluation will be provided in the... accordance with the licensee=s application dated January 22, 2010 (Agencywide Documents Access and Management... logistical impacts. The request for an exemption from the March 31, 2010, implementation date to September...

  13. 75 FR 80549 - FirstEnergy Nuclear Operating Company, Davis-Besse Nuclear Power Station; Exemption

    Science.gov (United States)

    2010-12-22

    ... license provides, among other things, that the facility is subject to all rules, regulations, and orders... ``determination of adjusted/indexing reference temperatures.'' The licensee proposes to use ASME Code Case N-629... determining adjusted/indexing reference temperatures, thus, the probability of postulated accidents is...

  14. 75 FR 76498 - Firstenergy Nuclear Operating Company, Davis-Besse Nuclear Power Station; Environmental...

    Science.gov (United States)

    2010-12-08

    ..., including anticipated operational occurrences and system hydrostatic tests, to which the pressure boundary... application dated April 15, 2009, as supplemented by letters dated December 18, 2009, August 26 and October 8... action (i.e., the ``no-action'' alternative). Denial of the application would result in no change...

  15. The Medicina Station Status Report

    Science.gov (United States)

    Orfei, Alessandro; Orlati, Andrea; Maccaferri, Giuseppe

    2013-01-01

    General information about the Medicina Radio Astronomy Station, the 32-m antenna status, and the staff in charge of the VLBI observations is provided. In 2012, the data from geodetic VLBI observations were acquired using the Mark 5A recording system with good results. Updates of the hardware were performed and are briefly described.

  16. 77 FR 16175 - Station Blackout

    Science.gov (United States)

    2012-03-20

    ... turbine trip and unavailability of the onsite emergency ac power system). Station blackout does not... plant achieves safe shutdown by relying on components that are not ac powered, such as turbine- or..., or seismic activity and that preexisting licensing requirements specified sufficient...

  17. Mobile Alternative Fueling Station Locator

    Energy Technology Data Exchange (ETDEWEB)

    2009-04-01

    The Department of Energy's Alternative Fueling Station Locator is available on-the-go via cell phones, BlackBerrys, or other personal handheld devices. The mobile locator allows users to find the five closest biodiesel, electricity, E85, hydrogen, natural gas, and propane fueling sites using Google technology.

  18. Mobile Lunar Laser Ranging Station

    Science.gov (United States)

    Intellect, 1977

    1977-01-01

    Harlan Smith, chairman of the University of Texas's Astronomy Department, discusses a mobile lunar laser ranging station which could help determine the exact rates of movement between continents and help geophysicists understand earthquakes. He also discusses its application for studying fundamental concepts of cosmology and physics. (Editor/RK)

  19. Remote input/output station

    CERN Multimedia

    1972-01-01

    A general view of the remote input/output station installed in building 112 (ISR) and used for submitting jobs to the CDC 6500 and 6600. The card reader on the left and the line printer on the right are operated by programmers on a self-service basis.

  20. Automatic Weather Station (AWS) Lidar

    Science.gov (United States)

    Rall, Jonathan A.R.; Abshire, James B.; Spinhirne, James D.; Smith, David E. (Technical Monitor)

    2000-01-01

    An autonomous, low-power atmospheric lidar instrument is being developed at NASA Goddard Space Flight Center. This compact, portable lidar will operate continuously in a temperature controlled enclosure, charge its own batteries through a combination of a small rugged wind generator and solar panels, and transmit its data from remote locations to ground stations via satellite. A network of these instruments will be established by co-locating them at remote Automatic Weather Station (AWS) sites in Antarctica under the auspices of the National Science Foundation (NSF). The NSF Office of Polar Programs provides support to place the weather stations in remote areas of Antarctica in support of meteorological research and operations. The AWS meteorological data will directly benefit the analysis of the lidar data while a network of ground based atmospheric lidar will provide knowledge regarding the temporal evolution and spatial extent of Type la polar stratospheric clouds (PSC). These clouds play a crucial role in the annual austral springtime destruction of stratospheric ozone over Antarctica, i.e. the ozone hole. In addition, the lidar will monitor and record the general atmospheric conditions (transmission and backscatter) of the overlying atmosphere which will benefit the Geoscience Laser Altimeter System (GLAS). Prototype lidar instruments have been deployed to the Amundsen-Scott South Pole Station (1995-96, 2000) and to an Automated Geophysical Observatory site (AGO 1) in January 1999. We report on data acquired with these instruments, instrument performance, and anticipated performance of the AWS Lidar.

  1. Barrow Meteoroloigcal Station (BMET) Handbook

    Energy Technology Data Exchange (ETDEWEB)

    Ritsche, MT

    2004-11-01

    The Barrow meteorology station (BMET) uses mainly conventional in situ sensors mounted at four different heights on a 40 m tower to obtain profiles of wind speed, wind direction, air temperature, and humidity. It also obtains barometric pressure, visibility, and precipitation data.

  2. Reactor coolant pump shaft seal behavior during station blackout

    Energy Technology Data Exchange (ETDEWEB)

    Kittmer, C.A.; Wensel, R.G.; Rhodes, D.B.; Metcalfe, R.; Cotnam, B.M.; Gentili, H.; Mings, W.J.

    1985-04-01

    A testing program designed to provide fundamental information pertaining to the behavior of reactor coolant pump (RCP) shaft seals during a postulated nuclear power plant station blackout has been completed. One seal assembly, utilizing both hydrodynamic and hydrostatic types of seals, was modeled and tested. Extrusion tests were conducted to determine if seal materials could withstand predicted temperatures and pressures. A taper-face seal model was tested for seal stability under conditions when leaking water flashes to steam across the seal face. Test information was then used as the basis for a station blackout analysis. Test results indicate a potential problem with an elastomer material used for O-rings by a pump vendor; that vendor is considering a change in material specification. Test results also indicate a need for further research on the generic issue of RCP seal integrity and its possible consideration for designation as an unresolved safety issue.

  3. Nuclear Physics

    Science.gov (United States)

    Contents: V Dinucleons, published in The Physical Review , v93 n4 p908-909, 15 Feb 1954; Concentration of a Cyclotron Beam by Strong Focusing Lenses...published in The Review of Scientific Instruments, v25 n4 p365-367, Apr 1954; and Photon Splitting in a Nuclear Electrostatic Field, published in The Physical Review , v94 n2 p367-368, 15 Apr 1954.

  4. Estimating end of life liabilities for plant licensing and financial planning for similarly configured stations

    Energy Technology Data Exchange (ETDEWEB)

    Griffiths, G. [TLG Services, Inc. an Entergy Nuclear Co. (United States); Kennard, J. [Ontario Power Generation Inc. (Canada)

    2008-07-01

    Ontario Power Generation (OPG) is required to update estimated waste management and decommissioning costs on a 5-year cycle within the Canadian Nuclear Safety Commission's (CNSC) regulatory framework and provide a decommissioning cost update and provisions funds status to the Province of Ontario on a similar five-year cycle under the terms of the Ontario Nuclear Funds Agreement (ONFA). The following is an overview of the important steps used to develop OPG's nuclear power station decommissioning cost estimates, including a discussion of the responsibilities of both the owner (OPG) and estimating services vendor (TLG Services). This presentation is related to decommissioning estimating for multi-unit stations; therefore the discussion will be focused on identifying those activities that may be particularly impacted by multi-unit configuration or multiple stations. It should be noted that simultaneously developing decommissioning estimates for multiple multi-unit stations creates the opportunity to achieve economies of scale to more efficiently produce the estimates, and enables the owner and vendor to compare results between stations to identify inconsistencies. However, without careful attention to detail at the planning and execution stage, it also creates the potential liability of backtracking and developing the estimate multiple times, should significant assumptions be revised in mid-project. (authors)

  5. Nuclear Waffles

    CERN Document Server

    Schneider, A S; Briggs, C M; Caplan, M E; Horowitz, C J

    2014-01-01

    The dense neutron-rich matter found in supernovae and neutron stars is expected to form complex nonuniform phases referred to as nuclear pasta. The pasta shapes depend on density, temperature and proton fraction and determine many transport properties in supernovae and neutron star crusts. We use two recently developed hybrid CPU/GPU codes to perform large scale molecular dynamics (MD) simulations with $51200$ and $409600$ nucleons of nuclear pasta. From the output of the MD simulations we characterize the topology and compute two observables, the radial distribution function $g(r)$ and the structure factor $S(q)$, for systems with proton fractions $Y_p=0.10, 0.20, 0.30$ and $0.40$ at about one third of nuclear saturation density and temperatures near $1.0$ MeV. We observe that the two lowest proton fraction systems simulated, $Y_p=0.10$ and $0.20$, equilibrate quickly and form liquid-like structures. Meanwhile, the two higher proton fraction systems, $Y_p=0.30$ and $0.40$, take a longer time to equilibrate a...

  6. Nuclear photonics

    Science.gov (United States)

    Habs, D.; Günther, M. M.; Jentschel, M.; Thirolf, P. G.

    2012-07-01

    With the planned new γ-beam facilities like MEGa-ray at LLNL (USA) or ELI-NP at Bucharest (Romania) with 1013 γ/s and a band width of ΔEγ/Eγ≈10-3, a new era of γ beams with energies up to 20MeV comes into operation, compared to the present world-leading HIγS facility at Duke University (USA) with 108 γ/s and ΔEγ/Eγ≈3ṡ10-2. In the long run even a seeded quantum FEL for γ beams may become possible, with much higher brilliance and spectral flux. At the same time new exciting possibilities open up for focused γ beams. Here we describe a new experiment at the γ beam of the ILL reactor (Grenoble, France), where we observed for the first time that the index of refraction for γ beams is determined by virtual pair creation. Using a combination of refractive and reflective optics, efficient monochromators for γ beams are being developed. Thus, we have to optimize the total system: the γ-beam facility, the γ-beam optics and γ detectors. We can trade γ intensity for band width, going down to ΔEγ/Eγ≈10-6 and address individual nuclear levels. The term "nuclear photonics" stresses the importance of nuclear applications. We can address with γ-beams individual nuclear isotopes and not just elements like with X-ray beams. Compared to X rays, γ beams can penetrate much deeper into big samples like radioactive waste barrels, motors or batteries. We can perform tomography and microscopy studies by focusing down to μm resolution using Nuclear Resonance Fluorescence (NRF) for detection with eV resolution and high spatial resolution at the same time. We discuss the dominating M1 and E1 excitations like the scissors mode, two-phonon quadrupole octupole excitations, pygmy dipole excitations or giant dipole excitations under the new facet of applications. We find many new applications in biomedicine, green energy, radioactive waste management or homeland security. Also more brilliant secondary beams of neutrons and positrons can be produced.

  7. 77 FR 31895 - Energy Northwest, Columbia Generating Station; Record of Decision and Issuance of Renewed...

    Science.gov (United States)

    2012-05-30

    ...; (11) hydroelectric power; (12) ocean wave and current energy; (13) geothermal power; (14) municipal... COMMISSION Energy Northwest, Columbia Generating Station; Record of Decision and Issuance of Renewed Facility... renewal application; issuance. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC or the Commission)...

  8. 75 FR 15744 - Omaha Public Power District; Fort Calhoun Station, Unit 1; Exemption

    Science.gov (United States)

    2010-03-30

    ... From the Federal Register Online via the Government Publishing Office NUCLEAR REGULATORY COMMISSION Omaha Public Power District; Fort Calhoun Station, Unit 1; Exemption 1.0 Background Omaha Public Power District (OPPD, the licensee) is the holder of Renewed Facility Operating License No. DPR-40 which authorizes operation of the Fort...

  9. 77 FR 22361 - Energy Northwest, Columbia Generating Station; Final Supplement 47 to the Generic Environmental...

    Science.gov (United States)

    2012-04-13

    ... COMMISSION Energy Northwest, Columbia Generating Station; Final Supplement 47 to the Generic Environmental...: Final Supplement 47 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants... Commission) has published the final plant- specific supplement 47 to the ``Generic Environmental...

  10. Neutron production station ESS-BILBAO; Estacion de produccion de neutrones de ESS-BILBAO

    Energy Technology Data Exchange (ETDEWEB)

    Vicente Bueno, J. Pe. de; Bermejo, J.; Fraile Santiago, T.

    2012-07-01

    The ESS-Bilbao installation produces neutrons by nuclear reactions stripping energy 50 MeV protons on a target of beryllium. the Neutron Production Station would have a target and would allow condition the neutron energy, maximize their performance, provide structural support to the whole, the high power cooling and radiation shielding received abroad.

  11. Extended station blackout analyses of an APR1400 with MARS-KS

    Directory of Open Access Journals (Sweden)

    Kim Woongbae

    2016-01-01

    Full Text Available The Fukushima Daiichi nuclear power plant accident shows that natural disasters such as earthquakes and the subsequent tsunamis can cause station blackout for several days. The electric energy required for essential systems during a station blackout is provided from emergency backup batteries installed at the nuclear power plant. In South Korea, in the event of an extended station blackout, the life of these emergency backup batteries has recently been extended from 8 hours to 24 hours at Shin-Kori 5, 6, and APR1400 for design certification. For a battery life of 24 hours, available safety means system, equipment and procedures are studied and analyzed in their ability to cope with an extended station blackout. A sensitivity study of reactor coolant pump seal leakage is performed to verify how different seal leakages could affect the system. For simulating extended station blackout scenarios, the best estimate MARS-KS computer code was used. In this paper, an APR1400 RELAP5 input deck was developed for station blackout scenario to analyze operation strategy by manually depressurizing the reactor coolant system through the steam generator's secondary side. Additionally, a sensitivity study on reactor coolant pump seal leakage was carried out.

  12. Technical Application of Nuclear Fission

    Science.gov (United States)

    Denschlag, J. O.

    The chapter is devoted to the practical application of the fission process, mainly in nuclear reactors. After a historical discussion covering the natural reactors at Oklo and the first attempts to build artificial reactors, the fundamental principles of chain reactions are discussed. In this context chain reactions with fast and thermal neutrons are covered as well as the process of neutron moderation. Criticality concepts (fission factor η, criticality factor k) are discussed as well as reactor kinetics and the role of delayed neutrons. Examples of specific nuclear reactor types are presented briefly: research reactors (TRIGA and ILL High Flux Reactor), and some reactor types used to drive nuclear power stations (pressurized water reactor [PWR], boiling water reactor [BWR], Reaktor Bolshoi Moshchnosti Kanalny [RBMK], fast breeder reactor [FBR]). The new concept of the accelerator-driven systems (ADS) is presented. The principle of fission weapons is outlined. Finally, the nuclear fuel cycle is briefly covered from mining, chemical isolation of the fuel and preparation of the fuel elements to reprocessing the spent fuel and conditioning for deposit in a final repository.

  13. Nuclear tele medicine; Telemedicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Vargas, L.; Hernandez, F.; Fernandez, R. [Departamento de Medicina Nuclear, Imagenologia Diagnostica, Xalapa, Veracruz (Mexico)

    2005-07-01

    The great majority of the digital images of nuclear medicine are susceptible of being sent through internet. This has allowed that the work in diagnosis cabinets by image it can benefit of this modern technology. We have presented in previous congresses works related with tele medicine, however, due to the speed in the evolution of the computer programs and the internet, becomes necessary to make a current position in this modality of work. (Author)

  14. HSIP Fire Stations in New Mexico

    Data.gov (United States)

    Earth Data Analysis Center, University of New Mexico — Fire Stations in New Mexico Any location where fire fighters are stationed or based out of, or where equipment that such personnel use in carrying out their jobs is...

  15. Open System of Agile Ground Stations Project

    Data.gov (United States)

    National Aeronautics and Space Administration — There is an opportunity to build the HETE-2/TESS network of ground stations into an innovative and powerful Open System of Agile Stations, by developing a low-cost...

  16. 47 CFR 74.783 - Station identification.

    Science.gov (United States)

    2010-10-01

    ... made at a code speed not in excess of 20 words per minute; or (2) By arranging for the primary station... visual presentation or a clearly understandable aural presentation of the translator station's...

  17. Determination of steam wetness in the steam-generating equipment of nuclear power plants

    Science.gov (United States)

    Gorburov, V. I.; Gorburov, D. V.; Kuz'min, A. V.

    2012-05-01

    Calculation and experimental methods for determining steam wetness in horizontal steam generators for nuclear power stations equipped with VVER reactors, namely, the classic salt technique and calculations based on operating parameters are discussed considered and compared.

  18. Tracing Utopia in 'Utopia Station'

    DEFF Research Database (Denmark)

    Schwarzbart, Judith

    Art (Publication due in 2012)). But it seems to differ noticeable from the ideologically driven concept(s) of the 20th century avant-garde. The paper will suggest that we in experiments with openness and structure, with an ambivalent engagement in popular culture and everyday life, and complex double......This paper will discuss how avant-garde rhetoric and working methods are used to rethink exhibition-making in the wake of the ‘relational aesthetics’ and visual art of the 90s. With Utopia Station curated by Molly Nesbit, Hans Ulrich Obrist, and Rirkrit Tiravanija as key example, we will look...... carries the same meaning and function in a contemporary culture. Utopia Station unfolded over a long period of time, starting with different gatherings in 2002, continuing with diverse ‘stations’ at the Venice Biennial (2003), Haus der Kunst in Munich (2004), and the World Social Forum in Porte Alegre...

  19. Space Station tethered elevator system

    Science.gov (United States)

    Haddock, Michael H.; Anderson, Loren A.; Hosterman, K.; Decresie, E.; Miranda, P.; Hamilton, R.

    1989-01-01

    The optimized conceptual engineering design of a space station tethered elevator is presented. The tethered elevator is an unmanned, mobile structure which operates on a ten-kilometer tether spanning the distance between Space Station Freedom and a platform. Its capabilities include providing access to residual gravity levels, remote servicing, and transportation to any point along a tether. The report discusses the potential uses, parameters, and evolution of the spacecraft design. Emphasis is placed on the elevator's structural configuration and three major subsystem designs. First, the design of elevator robotics used to aid in elevator operations and tethered experimentation is presented. Second, the design of drive mechanisms used to propel the vehicle is discussed. Third, the design of an onboard self-sufficient power generation and transmission system is addressed.

  20. Manned space stations - A perspective

    Science.gov (United States)

    Disher, J. H.

    1981-09-01

    The findings from the Skylab missions are discussed as they relate to the operations planning of future space stations such as Spacelab and the proposed Space Operations Center. Following a brief description of the Skylab spacecraft, the significance of the mission as a demonstration of the possibility of effecting emergency repairs in space is pointed out. Specific recommendations made by Skylab personnel concerning capabilities for future in-flight maintenance are presented relating to the areas of spacecraft design criteria, tool selection and spares carried. Attention is then given to relevant physiological findings, and to habitability considerations in the areas of sleep arrangements, hygiene, waste management, clothing, and food. The issue of contamination control is examined in detail as a potential major system to be integrated into future design criteria. The importance of the Skylab results to the designers of future space stations is emphasized.

  1. Stations

    Data.gov (United States)

    Earth Data Analysis Center, University of New Mexico — The National Flood Hazard Layer (NFHL) data incorporates all Digital Flood Insurance Rate Map(DFIRM) databases published by FEMA, and any Letters Of Map Revision...

  2. The nuclear arsenals and nuclear disarmament.

    Science.gov (United States)

    Barnaby, F

    1998-01-01

    Current world stockpiles of nuclear weapons and the status of treaties for nuclear disarmament and the ultimate elimination of nuclear weapons are summarised. The need for including stockpiles of civil plutonium in a programme for ending production and disposing of fissile materials is emphasized, and the ultimate difficulty of disposing of the last few nuclear weapons discussed.

  3. Design and construction of nuclear power plants

    CERN Document Server

    Schnell, Jürgen; Meiswinkel, Rüdiger; Bergmeister, Konrad; Fingerloos, Frank; Wörner, Johann-Dietrich

    2013-01-01

    Despite all the efforts being put into expanding renewable energy sources, large-scale power stations will be essential as part of a reliable energy supply strategy for a longer period. Given that they are low on CO2 emissions, many countries are moving into or expanding nuclear energy to cover their baseload supply.Building structures required for nuclear installations whose protective function means they are classified as safety-related, have to meet particular construction requirements more stringent than those involved in conventional construction. This book gives a comprehensive overv

  4. Station Climatic Summaries, Latin America

    Science.gov (United States)

    1990-06-01

    1 ARUBA Reina Beatrix 789820 Dec 86 (OCDS) --....................................... 5 ARGENTINA Buenos Alres/Ezeiza 875760 Apr 89 (CB...74 Oruro/Mendoza 852420 Feb 87 (OCDS) ...................................... 78 Potosi/ Rojas 852930 Feb 87 (OCDS...F 0 0 0 f 21-23 LST 0 0 0 0 # 0 F 1 0 0 0 F ALL HOURS # f F 0 0 # 0 F F 0 0 0 F 004 OPERATIONAL CLIMATIC DATA SUMMARY STATION: REINA BEATRIX INTL

  5. Automatic Control of Water Pumping Stations

    Institute of Scientific and Technical Information of China (English)

    Muhannad Alrheeh; JIANG Zhengfeng

    2006-01-01

    Automatic Control of pumps is an interesting proposal to operate water pumping stations among many kinds of water pumping stations according to their functions.In this paper, our pumping station is being used for water supply system. This paper is to introduce the idea of pump controller and the important factors that must be considering when we want to design automatic control system of water pumping stations. Then the automatic control circuit with the function of all components will be introduced.

  6. Nuclear energy.

    Science.gov (United States)

    Grandin, Karl; Jagers, Peter; Kullander, Sven

    2010-01-01

    Nuclear energy can play a role in carbon free production of electrical energy, thus making it interesting for tomorrow's energy mix. However, several issues have to be addressed. In fission technology, the design of so-called fourth generation reactors show great promise, in particular in addressing materials efficiency and safety issues. If successfully developed, such reactors may have an important and sustainable part in future energy production. Working fusion reactors may be even more materials efficient and environmental friendly, but also need more development and research. The roadmap for development of fourth generation fission and fusion reactors, therefore, asks for attention and research in these fields must be strengthened.

  7. Package power stations for export

    Energy Technology Data Exchange (ETDEWEB)

    1985-01-01

    The cheap and efficient generation of power is an essential requirement for the success and prosperity of any community and is especially important to third world countries. It is therefore logical that the more technologically advanced nations should seek to produce power stations for the developing countries. Power plant can now be designed into a packaged form that may be readily exported and commissioned. This valuable and interesting collection of papers were originally presented at a seminar organised by the Power Industries Division of the Institution of Mechanical Engineers. Topics considered include the developing world market for packaged power stations using indigenous fuels; multi-fuel systems for power generation; packaging, modularisation, and containerisation of equipment for power boilers for export; compact coal-fired industrial plant; rural woodburning power stations; biomass gasification based power generation technology and potential; gas fed reciprocating engine development; packaged heavy duty gas turbines for power generation; and criteria for assessing the appropriateness of package power technologies in developing countries.

  8. Design data and safety features of commerical nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Heddleson, F.A.

    1976-06-01

    Design data, safety features, and site characteristics are summarized for 34 nuclear power units in 17 power stations in the United States. Six pages of data are presented for each plant, consisting of thermal-hydraulic and nuclear factors, containment features, emergency-core-cooling systems, site features, circulating water system data, and miscellaneous factors. An aerial perspective is also presented for each plant. This volume covers Light Water Reactors (LWRs) with dockets 50-508 through 50-549, four HTGRs--50-171, 50-267, 50-450/451, 50-463/464, the Atlantic Floating Station 50-477/478, and the Clinch River Breeder 50-537.

  9. A historical perspective on space station

    Science.gov (United States)

    Hook, W. Ray

    1991-01-01

    The historical development of space stations is presented through a series of various spacecraft configurations including: (1) Salut 6; (2) Skylab; (3) the Space Operations Center (SOC); (4) the Manned Science and Applications Space Platform; (5) Space Station Freedom; and (4) the Mir Space Station.

  10. 47 CFR 97.203 - Beacon station.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Beacon station. 97.203 Section 97.203... SERVICE Special Operations § 97.203 Beacon station. (a) Any amateur station licensed to a holder of a Technician, Technician Plus, General, Advanced or Amateur Extra Class operator license may be a beacon....

  11. 47 CFR 22.313 - Station identification.

    Science.gov (United States)

    2010-10-01

    ... for transmission by: (1) Stations in the Cellular Radiotelephone Service; (2) General aviation ground... continuity of any public communication in progress, provided that station identification is transmitted at... carrier; (2) For general aviation airborne mobile stations in the Air-Ground Radiotelephone Service,...

  12. 47 CFR 97.205 - Repeater station.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Repeater station. 97.205 Section 97.205... SERVICE Special Operations § 97.205 Repeater station. (a) Any amateur station licensed to a holder of a Technician, General, Advanced or Amateur Extra Class operator license may be a repeater. A holder of...

  13. 47 CFR 87.109 - Station logs.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Station logs. 87.109 Section 87.109... Operating Requirements and Procedures Operating Procedures § 87.109 Station logs. (a) A station at a fixed location in the international aeronautical mobile service must maintain a log in accordance with Annex...

  14. 49 CFR 195.128 - Station piping.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 3 2010-10-01 2010-10-01 false Station piping. 195.128 Section 195.128 Transportation Other Regulations Relating to Transportation (Continued) PIPELINE AND HAZARDOUS MATERIALS SAFETY... PIPELINE Design Requirements § 195.128 Station piping. Any pipe to be installed in a station that...

  15. 30 CFR 57.12085 - Transformer stations.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Transformer stations. 57.12085 Section 57.12085 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR METAL AND NONMETAL MINE... Underground Only § 57.12085 Transformer stations. Transformer stations shall be enclosed to prevent...

  16. Applications of nuclear physics

    Science.gov (United States)

    Hayes, A. C.

    2017-02-01

    Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that underlie the physics involved in designs of nuclear explosions, controlled nuclear energy, and nuclear fusion. The review then moves to focus on modern applications of these concepts, including the basic concepts and diagnostics developed for the forensics of nuclear explosions, the nuclear diagnostics at the National Ignition Facility, nuclear reactor safeguards, and the detection of nuclear material production and trafficking. The review also summarizes recent developments in nuclear geophysics and nuclear medicine. The nuclear geophysics areas discussed include geo-chronology, nuclear logging for industry, the Oklo reactor, and geo-neutrinos. The section on nuclear medicine summarizes the critical advances in nuclear imaging, including PET and SPECT imaging, targeted radionuclide therapy, and the nuclear physics of medical isotope production. Each subfield discussed requires a review article unto itself, which is not the intention of the current review; rather, the current review is intended for readers who wish to get a broad understanding of applied nuclear physics.

  17. Nuclear Photonics

    CERN Document Server

    Habs, D; Jentschel, M; Thirolf, P G

    2012-01-01

    With new gamma-beam facilities like MEGa-ray at LLNL (USA) or ELI-NP at Bucharest with 10^13 g/s and a bandwidth of Delta E_g/E_g ~10^-3, a new era of g-beams with energies <=20 MeV comes into operation, compared to the present world-leading HIGS facility (Duke Univ., USA) with 10^8 g/s and Delta E_g/E_g~0.03. Even a seeded quantum FEL for g-beams may become possible, with much higher brilliance and spectral flux. At the same time new exciting possibilities open up for focused g-beams. We describe a new experiment at the g-beam of the ILL reactor (Grenoble), where we observed for the first time that the index of refraction for g-beams is determined by virtual pair creation. Using a combination of refractive and reflective optics, efficient monochromators for g-beams are being developed. Thus we have to optimize the system of the g-beam facility, the g-beam optics and g-detectors. We can trade g-intensity for band width, going down to Delta E_g/E_g ~ 10^-6 and address individual nuclear levels. 'Nuclear pho...

  18. 47 CFR 90.476 - Interconnection of fixed stations and certain mobile stations.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Interconnection of fixed stations and certain... Systems § 90.476 Interconnection of fixed stations and certain mobile stations. (a) Fixed stations and...)(11), 90.35(c)(42), and 90.267 are not subject to the interconnection provisions of §§ 90.477 and...

  19. Dictionary of nuclear engineering

    Energy Technology Data Exchange (ETDEWEB)

    Sube, R.

    1985-01-01

    Ralf Sube, an experienced compiler of three wellknown four-language reference works has now prepared this glossary of nuclear engineering terms in English, German, French and Russian. Based on the proven lexicography of the Technik-Worterbuch series, it comprises about 30,000 terms in each language covering the following: Nuclear and Atomic Physics; Nuclear Radiation and Isotopes; Nuclear Materials; Nuclear Facilties; Nuclear Power Industry; Nuclear Weapons.

  20. A customer-friendly Space Station

    Science.gov (United States)

    Pivirotto, D. S.

    1984-01-01

    This paper discusses the relationship of customers to the Space Station Program currently being defined by NASA. Emphasis is on definition of the Program such that the Space Station will be conducive to use by customers, that is by people who utilize the services provided by the Space Station and its associated platforms and vehicles. Potential types of customers are identified. Scenarios are developed for ways in which different types of customers can utilize the Space Station. Both management and technical issues involved in making the Station 'customer friendly' are discussed.

  1. Arduino adventures escape from Gemini station

    CERN Document Server

    Kelly, James Floyd

    2013-01-01

    Arduino Adventures: Escape from Gemini Station provides a fun introduction to the Arduino microcontroller by putting you (the reader) into the action of a science fiction adventure story.  You'll find yourself following along as Cade and Elle explore Gemini Station-an orbiting museum dedicated to preserving and sharing technology throughout the centuries. Trouble ensues. The station is evacuated, including Cade and Elle's class that was visiting the station on a field trip. Cade and Elle don't make it aboard their shuttle and are trapped on the station along with a friendly artificial intellig

  2. Nuclear "waffles"

    Science.gov (United States)

    Schneider, A. S.; Berry, D. K.; Briggs, C. M.; Caplan, M. E.; Horowitz, C. J.

    2014-11-01

    Background: The dense neutron-rich matter found in supernovae and inside neutron stars is expected to form complex nonuniform phases, often referred to as nuclear pasta. The pasta shapes depend on density, temperature and proton fraction and determine many transport properties in supernovae and neutron star crusts. Purpose: To characterize the topology and compute two observables, the radial distribution function (RDF) g (r ) and the structure factor S (q ) , for systems with proton fractions Yp=0.10 ,0.20 ,0.30 , and 0.40 at about one-third of nuclear saturation density, n =0.050 fm-3 , and temperatures near k T =1 MeV . Methods: We use two recently developed hybrid CPU/GPU codes to perform large scale molecular dynamics (MD) simulations with 51 200 and 409 600 nucleons. From the output of the MD simulations we obtain the two desired observables. Results: We compute and discuss the differences in topology and observables for each simulation. We observe that the two lowest proton fraction systems simulated, Yp=0.10 and 0.20 , equilibrate quickly and form liquidlike structures. Meanwhile, the two higher proton fraction systems, Yp=0.30 and 0.40 , take a longer time to equilibrate and organize themselves in solidlike periodic structures. Furthermore, the Yp=0.40 system is made up of slabs, lasagna phase, interconnected by defects while the Yp=0.30 systems consist of a stack of perforated plates, the nuclear waffle phase. Conclusions: The periodic configurations observed in our MD simulations for proton fractions Yp≥0.30 have important consequences for the structure factors S (q ) of protons and neutrons, which relate to many transport properties of supernovae and neutron star crust. A detailed study of the waffle phase and how its structure depends on temperature, size of the simulation, and the screening length showed that finite-size effects appear to be under control and, also, that the plates in the waffle phase merge at temperatures slightly above 1.0 MeV and

  3. Political crisis poses problems for nuclear industry

    Energy Technology Data Exchange (ETDEWEB)

    Mitev, Lubomir [NucNet, Brussels (Belgium)

    2014-11-15

    The political crisis in Ukraine has given rise to several problematic issues for the nuclear industry, including the country's obvious dependence on Russia for nuclear fuel supplies and the transport of nuclear material. A 2013 report by the Polish Institute of International Affairs (PIIA) concluded that Ukraine will lean towards the development of ''intensive cooperation'' with Western nuclear regulators and companies as it seeks to increase its control over the sector and reduce its dependency on Russia. The PIIA report said the gas crises of 2006 and 2009, and especially the current destabilisation of the country, have highlighted Ukraine's ''excessive and problematic dependence'' on energy supply from Russia. The 'Energy Strategy of Ukraine Until 2030' assumes that the share of nuclear energy will remain the same in 2030 as it was in 2005 - about 50 % of the energy mix. To achieve its goals, Ukraine's strategy envisages several priority actions. Firstly, work should begin on identification of three or four sites for new nuclear stations. Secondly, the plan says that Khmelnistki-3 and -4 should be completed by 2016. Thirdly, the plan envisages six gigawatts of new nuclear capacity becoming operational between 2019 and 2021. Finally, lifetime extensions are planned for South Ukraine units 1 to 3, Zaporozhye units 1 to 6, Rovno units 2 and 3 and Khmelnitski-1.

  4. A source term estimation method for a nuclear accident using atmospheric dispersion models

    DEFF Research Database (Denmark)

    Kim, Minsik; Ohba, Ryohji; Oura, Masamichi

    2015-01-01

    The objective of this study is to develop an operational source term estimation (STE) method applicable for a nuclear accident like the incident that occurred at the Fukushima Dai-ichi nuclear power station in 2011. The new STE method presented here is based on data from atmospheric dispersion...... models and short-range observational data around the nuclear power plants.The accuracy of this method is validated with data from a wind tunnel study that involved a tracer gas release from a scaled model experiment at Tokai Daini nuclear power station in Japan. We then use the methodology developed...... and validated through the effort described in this manuscript to estimate the release rate of radioactive material from the Fukushima Dai-ichi nuclear power station....

  5. NUCLEAR REACTOR

    Science.gov (United States)

    Miller, H.I.; Smith, R.C.

    1958-01-21

    This patent relates to nuclear reactors of the type which use a liquid fuel, such as a solution of uranyl sulfate in ordinary water which acts as the moderator. The reactor is comprised of a spherical vessel having a diameter of about 12 inches substantially surrounded by a reflector of beryllium oxide. Conventionnl control rods and safety rods are operated in slots in the reflector outside the vessel to control the operation of the reactor. An additional means for increasing the safety factor of the reactor by raising the ratio of delayed neutrons to prompt neutrons, is provided and consists of a soluble sulfate salt of beryllium dissolved in the liquid fuel in the proper proportion to obtain the result desired.

  6. Nuclear exoticism

    Science.gov (United States)

    Penionzhkevich, Yu. E.

    2016-07-01

    Extreme states of nuclearmatter (such that feature high spins, large deformations, high density and temperature, or a large excess of neutrons and protons) play an important role in studying fundamental properties of nuclei and are helpful in solving the problem of constructing the equation of state for nuclear matter. The synthesis of neutron-rich nuclei near the nucleon drip lines and investigation of their properties permit drawing conclusions about the positions of these boundaries and deducing information about unusual states of such nuclei and about their decays. At the present time, experimental investigations along these lines can only be performed via the cooperation of leading research centers that possess powerful heavy-ion accelerators, such as the Large Hadron Collider (LHC) at CERN and the heavy-ion cyclotrons at the Joint Institute for Nuclear Research (JINR, Dubna), where respective experiments are being conducted by physicists from about 20 JINR member countries. The present article gives a survey of the most recent results in the realms of super neutron-rich nuclei. Implications of the change in the structure of such nuclei near the nucleon drip lines are discussed. Information about the results obtained by measuring the masses (binding energies) of exotic nuclei, the nucleon-distribution radii (neutron halo) and momentum distributions in them, and their deformations and quantum properties is presented. It is shown that the properties of nuclei lying near the stability boundaries differ strongly from the properties of other nuclei. The problem of the stability of nuclei that is associated with the magic numbers of 20 and 28 is discussed along with the effect of new magic numbers.

  7. Reconversion of nuclear weapons

    CERN Document Server

    Kapitza, Sergei P

    1993-01-01

    The nuclear predicament or nuclear option. Synopsis of three lectures : 1- The physical basis of nuclear technology. Physics of fission. Chain reaction in reactors and weapons. Fission fragments. Separration of isotopes. Radiochemistry.2- Nuclear reactors with slow and fast neutrons. Power, size, fuel and waste. Plutonium production. Dose rate, shielding and health hazard. The lessons of Chernobyl3- Nuclear weapons. Types, energy, blast and fallout. Fusion and hydrogen bombs. What to do with nuclear weapons when you cannot use them? Testing. Nonmilittary use. Can we get rid of the nuclear weapon? Nuclear proliferation. Is there a nuclear future?

  8. Overview of IMS infrasound station and engineering projects

    Science.gov (United States)

    Marty, J.; Doury, B.; Kramer, A.; Martysevich, P.

    2015-12-01

    The Provisional Technical Secretariat (PTS) of the Comprehensive Nuclear-Test-Ban Treaty (CTBTO) has a continuous interest in enhancing its capability in acoustic source detection, localization and characterization. The infrasound component of the International Monitoring System (IMS) constitutes the only worldwide ground-based infrasound network. It consists of sixty stations, among which forty-eight are already certified and continuously transmit data to the International Data Centre (IDC) in Vienna, Austria. Each infrasound station is composed of an array of infrasound sensors capable of measuring micro-pressure changes produced at ground level by infrasonic waves. The characteristics of infrasonic waves are computed in near real-time by IDC automatic detection software and are used as an input to IDC source categorization and localization algorithms. The PTS is continuously working towards the completion and sustainment of the IMS infrasound network. The objective of this presentation is to review the main activities performed in the IMS infrasound network over the last five years. This includes construction, installation, certification, major upgrade and revalidation activities. Major technology development projects to improve the reliability and robustness of IMS infrasound stations as well as their compliance with IMS Operational Manual requirements will also be presented. This includes advances in array geometry, wind noise reduction, system calibration, meteorological data as well as power and communication infrastructures. Finally the impact of all these changes on the overall detection capability of the IMS infrasound network will be highlighted.

  9. No Nuclear Worries

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    China National Nuclear Corp.will learn lessons from the Fukushima accident while expanding its operations As Japan’s Fukushima nuclear crisis sparks a global debate over nuclear safety,China National Nuclear Corp.(CNNC),the country’s largest nuclear power operator,comes under

  10. Trends in Nuclear Astrophysics

    OpenAIRE

    Schatz, Hendrik

    2016-01-01

    Nuclear Astrophysics is a vibrant field at the intersection of nuclear physics and astrophysics that encompasses research in nuclear physics, astrophysics, astronomy, and computational science. This paper is not a review. It is intended to provide an incomplete personal perspective on current trends in nuclear astrophysics and the specific role of nuclear physics in this field.

  11. Neutron proton crystallography station (PCS)

    Energy Technology Data Exchange (ETDEWEB)

    Fisher, Zoe [Los Alamos National Laboratory; Kovalevsky, Andrey [Los Alamos National Laboratory; Johnson, Hannah [Los Alamos National Laboratory; Mustyakimov, Marat [Los Alamos National Laboratory

    2009-01-01

    The PCS (Protein Crystallography Station) at Los Alamos Neutron Science Center (LANSCE) is a unique facility in the USA that is designed and optimized for detecting and collecting neutron diffraction data from macromolecular crystals. PCS utilizes the 20 Hz spallation neutron source at LANSCE to enable time-of-flight measurements using 0.6-7.0 {angstrom} neutrons. This increases the neutron flux on the sample by using a wavelength range that is optimal for studying macromolecular crystal structures. The diagram below show a schematic of PCS and photos of the detector and instrument cave.

  12. Weather Monitoring Station: A Review

    Directory of Open Access Journals (Sweden)

    Mr. Dipak V. Sose

    2016-06-01

    Full Text Available Weather monitoring plays a very important role in human life hence study of weather system is necessary. Currently there are two types of the weather monitoring stations available i.e. wired and wireless. Wireless system has some advantages over the wired one hence popular now a days. The parameters are include in weather monitoring usually temperature, humidity atmospheric pressure, light intensity, rainfall etc. There are many techniques existed using different processor such as PIC, AVR, ARM etc. Analog to digital channel are used to fetch the analog output of the sensors. The wireless techniques used in the weather monitoring having GSM, FM channel, Zigbee, RF etc Protocols

  13. Environmental interactions on Space Station

    Science.gov (United States)

    Garrett, Henry B.; Gabriel, Stephen B.; Murphy, Gerald B.

    1990-01-01

    This paper describes the key environment/system interactions associated with the Space Station and its companion polar platform and defines the range of test environments that will need to be simulated. These environments include the neutral atmosphere, the ionospheric plasma, natural and man-made particulates, the ambient magnetic field, the South Atlantic Anomaly, and the ram/wake environment. The system/environment interactions include glow, oxygen erosion, drag, radiation effects, induced electric fields, high-voltage solar-array effects, and EMC/EMI associated with plasma/neutral gas operations. The Space Station and its associated systems pose unique demands on the ability to simulate these effects; synergistic effects require multiple environments to be simulated simultaneously, and the long life requirements require proper scaling of the exposure time. The analysis of specific effects and the calibration or improvement of ground test techniques will likely require in situ evaluation. Qualification and acceptance testing, because of cost and the impractically of extensive on-orbit analysis/modification, will likely remain ground test objectives except in very rare cases.

  14. Space station operating system study

    Science.gov (United States)

    Horn, Albert E.; Harwell, Morris C.

    1988-01-01

    The current phase of the Space Station Operating System study is based on the analysis, evaluation, and comparison of the operating systems implemented on the computer systems and workstations in the software development laboratory. Primary emphasis has been placed on the DEC MicroVMS operating system as implemented on the MicroVax II computer, with comparative analysis of the SUN UNIX system on the SUN 3/260 workstation computer, and to a limited extent, the IBM PC/AT microcomputer running PC-DOS. Some benchmark development and testing was also done for the Motorola MC68010 (VM03 system) before the system was taken from the laboratory. These systems were studied with the objective of determining their capability to support Space Station software development requirements, specifically for multi-tasking and real-time applications. The methodology utilized consisted of development, execution, and analysis of benchmark programs and test software, and the experimentation and analysis of specific features of the system or compilers in the study.

  15. Nuclear analytical chemistry

    Energy Technology Data Exchange (ETDEWEB)

    Brune, D.; Forkman, B.; Persson, B.

    1984-01-01

    This book covers the general theories and techniques of nuclear chemical analysis, directed at applications in analytical chemistry, nuclear medicine, radiophysics, agriculture, environmental sciences, geological exploration, industrial process control, etc. The main principles of nuclear physics and nuclear detection on which the analysis is based are briefly outlined. An attempt is made to emphasise the fundamentals of activation analysis, detection and activation methods, as well as their applications. The book provides guidance in analytical chemistry, agriculture, environmental and biomedical sciences, etc. The contents include: the nuclear periodic system; nuclear decay; nuclear reactions; nuclear radiation sources; interaction of radiation with matter; principles of radiation detectors; nuclear electronics; statistical methods and spectral analysis; methods of radiation detection; neutron activation analysis; charged particle activation analysis; photon activation analysis; sample preparation and chemical separation; nuclear chemical analysis in biological and medical research; the use of nuclear chemical analysis in the field of criminology; nuclear chemical analysis in environmental sciences, geology and mineral exploration; and radiation protection.

  16. Mean nuclear volume

    DEFF Research Database (Denmark)

    Mogensen, O.; Sørensen, Flemming Brandt; Bichel, P.

    1999-01-01

    We evaluated the following nine parameters with respect to their prognostic value in females with endometrial cancer: four stereologic parameters [mean nuclear volume (MNV), nuclear volume fraction, nuclear index and mitotic index], the immunohistochemical expression of cancer antigen (CA125...

  17. Nuclear Quadrupole Moments and Nuclear Shell Structure

    Science.gov (United States)

    Townes, C. H.; Foley, H. M.; Low, W.

    1950-06-23

    Describes a simple model, based on nuclear shell considerations, which leads to the proper behavior of known nuclear quadrupole moments, although predictions of the magnitudes of some quadrupole moments are seriously in error.

  18. Nuclear energy data 2010

    CERN Document Server

    2010-01-01

    This 2010 edition of Nuclear Energy Data , the OECD Nuclear Energy Agency's annual compilation of official statistics and country reports on nuclear energy, provides key information on plans for new nuclear plant construction, nuclear fuel cycle developments as well as current and projected nuclear generating capacity to 2035 in OECD member countries. This comprehensive overview provides authoritative information for policy makers, experts and other interested stakeholders.

  19. Nuclear Fuel Cycle & Vulnerabilities

    Energy Technology Data Exchange (ETDEWEB)

    Boyer, Brian D. [Los Alamos National Laboratory

    2012-06-18

    The objective of safeguards is the timely detection of diversion of significant quantities of nuclear material from peaceful nuclear activities to the manufacture of nuclear weapons or of other nuclear explosive devices or for purposes unknown, and deterrence of such diversion by the risk of early detection. The safeguards system should be designed to provide credible assurances that there has been no diversion of declared nuclear material and no undeclared nuclear material and activities.

  20. Nuclear Entalpies

    CERN Document Server

    Rozynek, J

    2013-01-01

    In a compressed Nuclear Matter (NM) an increasing pressure between the nucleons starts to increase the ratio of a nucleon Fermi to average single particle energy and in accordance with the Hugenholtz-van Hove theorem the longitudinal Momentum Sum Rule (MSR) is broken in a Relativistic Mean Field (RMF) approach. We propose to benefit from the concept of enthalpy in order to show how to fulfill the MSR above a saturation density with pressure corrections. As a result a nucleon mass can decrease with density, making the Equation of State (EoS) softer. The course of the EoS in our modified RMF model is close to a semi-empirical estimate and to results obtained from extensive DBHF calculations with a Bonn A potential, which produce the EoS stiff enough to describe neutron star properties (mass-radius constraint), especially the most massive known neutron star. The presented model has proper saturation properties, including good values of a compressibility and a spin-orbit term.

  1. Nuclear Data and Nuclear Model Methods

    Institute of Scientific and Technical Information of China (English)

    2001-01-01

    Developing nuclear data needs towards to sustainable development on fission reactor design and many nuclear applications out the field of fission reactor technology that are growing economicsignificance and that have substantial data requirements are introduced. International standard codes used in nuclear data evaluations and calculations are introduced and compared each other. Generally

  2. Nuclear energy data 2011

    CERN Document Server

    2011-01-01

     . Nuclear Energy Data, the OECD Nuclear Energy Agency's annual compilation of statistics and country reports on nuclear energy, contains official information provided by OECD member country governments on plans for new nuclear plant construction, nuclear fuel cycle developments as well as current and projected nuclear generating capacity to 2035. For the first time, it includes data for Chile, Estonia, Israel and Slovenia, which recently became OECD members. Key elements of this edition show a 2% increase in nuclear and total electricity production and a 0.5% increase in nuclear generating ca

  3. Nuclear weapons modernizations

    Energy Technology Data Exchange (ETDEWEB)

    Kristensen, Hans M. [Federation of American Scientists, Washington, DC (United States)

    2014-05-09

    This article reviews the nuclear weapons modernization programs underway in the world's nine nuclear weapons states. It concludes that despite significant reductions in overall weapons inventories since the end of the Cold War, the pace of reductions is slowing - four of the nuclear weapons states are even increasing their arsenals, and all the nuclear weapons states are busy modernizing their remaining arsenals in what appears to be a dynamic and counterproductive nuclear competition. The author questions whether perpetual modernization combined with no specific plan for the elimination of nuclear weapons is consistent with the nuclear Non-Proliferation Treaty and concludes that new limits on nuclear modernizations are needed.

  4. Recent Advances in Ocean Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    Kang-Heon Lee

    2015-10-01

    Full Text Available In this paper, recent advances in Ocean Nuclear Power Plants (ONPPs are reviewed, including their general arrangement, design parameters, and safety features. The development of ONPP concepts have continued due to initiatives taking place in France, Russia, South Korea, and the United States. Russia’s first floating nuclear power stations utilizing the PWR technology (KLT-40S and the spar-type offshore floating nuclear power plant designed by a research group in United States are considered herein. The APR1400 and SMART mounted Gravity Based Structure (GBS-type ONPPs proposed by a research group in South Korea are also considered. In addition, a submerged-type ONPP designed by DCNS of France is taken into account. Last, issues and challenges related to ONPPs are discussed and summarized.

  5. Study and characterization of noble metal deposits on similar rusty surfaces to those of the reactor U-1 type BWR of nuclear power station of Laguna Verde; Estudio y caracterizacion de depositos de metales nobles sobre superficies oxidadas similares a las del reactor de la Central de Laguna Verde (CNLV) U1 del tipo BWR

    Energy Technology Data Exchange (ETDEWEB)

    Flores S, V. H.

    2011-07-01

    In the present investigation work, were determined the parameters to simulate the conditions of internal oxidation reactor circulation pipes of the nuclear power plant of Laguna Verde in Veracruz. We used 304l stainless steel cylinders with two faces prepared with abrasive paper of No. 600, with the finality to obtain similar surface to the internal circulation piping nuclear reactor. Oxides was formed within an autoclave (Autoclave MEX-02 unit B), which is a device that simulates the working conditions of the nuclear reactor, but without radiation generated by the fission reaction within the reactor. The oxidation conditions were a temperature of 280 C and pressure of 8 MPa, similar conditions to the reactor operating in nuclear power plant of Laguna Verde in Veracruz, Mexico (BWR conditions), with an average conductivity of 4.58 ms / cm and 2352 ppb oxygen to simulate normal water chemistry NWC. Were obtained deposits of noble metal oxides formed on 304l stainless steel samples, in a 250 ml autoclave at a temperature range of 180 to 200 C. The elements that were used to deposit platinum-rhodium (Pt-Rh) with aqueous Na{sub 2}Pt (OH){sub 6} and Na{sub 3}Rh (NO{sub 2}){sub 6}, Silver (Ag) with an aqueous solution of AgNO{sub 3}, zirconium (Zr) with aqueous Zr O (NO{sub 3}) and ZrO{sub 2}, and zinc (Zn) in aqueous solution of Zn (NO{sub 3}){sub 2} under conditions of normal water chemistry. Also there was the oxidation of 304l stainless steel specimens in normal water chemistry with a solution of Zinc (Zn) (NWC + Zn). Oxidation of the specimens in water chemistry with a solution of zinc (Zn + NWC) was prepared in two ways: within the MEX-02 autoclave unit A in a solution of zinc and a flask at constant temperature in zinc solution. The oxides formed and deposits were characterized by scanning electron microscopy, energy dispersive X-ray analysis, elemental field analysis and X-ray diffraction. By other hand was evaluated the electrochemical behavior of the oxides

  6. UK 2009-2010 repeat station report

    Directory of Open Access Journals (Sweden)

    Thomas J.G. Shanahan

    2013-03-01

    Full Text Available The British Geological Survey is responsible for conducting the UK geomagnetic repeat station programme. Measurements made at the UK repeat station sites are used in conjunction with the three UK magnetic observatories: Hartland, Eskdalemuir and Lerwick, to produce a regional model of the local field each year. The UK network of repeat stations comprises 41 stations which are occupied at approximately 3-4 year intervals. Practices for conducting repeat station measurements continue to evolve as advances are made in survey instrumentation and as the usage of the data continues to change. Here, a summary of the 2009 and 2010 UK repeat station surveys is presented, highlighting the measurement process and techniques, density of network, reduction process and recent results.

  7. STRUVE arc and EUPOS® stations

    Science.gov (United States)

    Lasmane, Ieva; Kaminskis, Janis; Balodis, Janis; Haritonova, Diana

    2013-04-01

    The Struve Geodetic Arc was developed in Years 1816 to 1855, 200 years ago. Historic information on the points of the Struve Geodetic Arc are included in the UNESCO World Heritage list in 2005. Nevertheless, the sites of many points are still not identified nor included in the data bases nowadays. Originally STRUVE arc consisted of 258 main triangles with 265 triangulation points. Currently 34 of the original station points are identified and included in the in the UNESCO World Heritage list. identified original measurement points of the Meridian Arc are located in Sweden (7 points), Norway (15), Finland (83), Russia (1), Estonia (22), Latvia (16), Lithuania (18), Belorussia (28), Ukraine (59) and Moldova (27). In Year 2002 was initiated another large coverage project - European Position Determination System "EUPOS®". Currently there are about 400 continuously operating GNSS (Global Navigation Satellite Systems) stations covering EU countries Estonia, Latvia, Lithuania, Poland, Czech Republic, Slovakia, Hungary, Bulgaria, Romania and East European countries Ukraine and Moldavia. EUPOS® network is a ground based GNSS augmentation system widely used for geodesy, land surveying, geophysics and navigation. It gives the opportunity for fast and accurate position determination never available before. It is an honorable task to use the EUPOS® system for research of the Struve triangulation former sites. Projects with Struve arc can popularize geodesy, geo-information and its meaning in nowadays GIS and GNSS systems. Struve Arc and its points is unique cooperation cross-border object which deserve special attention because of their natural beauty and historical value for mankind. GNSS in geodesy discovers a powerful tool for the verification and validation of the height values of geodetic leveling benchmarks established historically almost 200 years ago. The differential GNSS and RTK methods appear very useful to identify vertical displacement of landscape by means of

  8. Nuclear Waste Cross Site Transfer Pump Operational Resonance Resolution

    Energy Technology Data Exchange (ETDEWEB)

    HAUCK, F.M.

    1999-12-01

    Two single-volute, multi-stage centrifugal pumps are installed at a nuclear waste transfer station operated by the Department of Energy in Hanford, WA. The two parallel 100% pumps are Variable Frequency Drive operated and designed to transport waste etc.

  9. Snow Drift Management: Summit Station Greenland

    Science.gov (United States)

    2016-05-01

    ER D C/ CR RE L TR -1 6- 6 Engineering for Polar Operations, Logistics, and Research (EPOLAR) Snow Drift Management Summit Station...Drift Management Summit Station Greenland Robert B. Haehnel and Matthew F. Bigl U.S. Army Engineer Research and Development Center (ERDC) Cold...Engineering for Polar Operations, Logistics, and Research (EPOLAR) EP-ARC-15-33, “Monitoring and Managing Snow Drifting at Summit Station, Greenland” ERDC

  10. METALLOGRAPHIC SAMPLE PREPARATION STATION-CONSTRUCTIVE CONCEPT

    Directory of Open Access Journals (Sweden)

    AVRAM Florin Timotei

    2016-11-01

    Full Text Available In this paper we propose to present the issues involved in the case of the constructive conception of a station for metallographic sample preparation. This station is destined for laboratory work. The metallographic station is composed of a robot ABB IRB1600, a metallographic microscope, a gripping device, a manipulator, a laboratory grinding and polishing machine. The robot will be used for manipulation of the sample preparation and the manipulator take the sample preparation for processing.

  11. ACSSB land mobile earth station

    Science.gov (United States)

    Taira, Shinichi; Ikegami, Tetsushi; Suzuki, Ryutaro; Suzuki, Shoichi; Kawahara, Hideki; Tada, Shun-Ichi

    1990-03-01

    This paper describes the performance of the land mobile earth station using the Amplitude Companded Single Sideband (ACSSB) modulation technique developed for mobile satellite communications and results of the field experiments which were conducted in rural, suburban, and urban areas. This ACSSB system uses a 3-kHz pilot tone, and the voice frequency band is from 300 to 2500 Hz. The experiments show that the required C/N0 for voice communications is 40 dBHz and the required C/N0 for pilot signal tracking is 34 dBHz. Voice quality in rural and suburban areas was degraded slightly. In urban areas shadowings due to the presence of large buildings and trees caused signal losses. A comparison of the ACSSB system with the conventional narrow-band frequency-modulation system indicates that the ACSSB system can transmit voice signals more efficiently.

  12. Station Program Note Pull Automation

    Science.gov (United States)

    Delgado, Ivan

    2016-01-01

    Upon commencement of my internship, I was in charge of maintaining the CoFR (Certificate of Flight Readiness) Tool. The tool acquires data from existing Excel workbooks on NASA's and Boeing's databases to create a new spreadsheet listing out all the potential safety concerns for upcoming flights and software transitions. Since the application was written in Visual Basic, I had to learn a new programming language and prepare to handle any malfunctions within the program. Shortly afterwards, I was given the assignment to automate the Station Program Note (SPN) Pull process. I developed an application, in Python, that generated a GUI (Graphical User Interface) that will be used by the International Space Station Safety & Mission Assurance team here at Johnson Space Center. The application will allow its users to download online files with the click of a button, import SPN's based on three different pulls, instantly manipulate and filter spreadsheets, and compare the three sources to determine which active SPN's (Station Program Notes) must be reviewed for any upcoming flights, missions, and/or software transitions. Initially, to perform the NASA SPN pull (one of three), I had created the program to allow the user to login to a secure webpage that stores data, input specific parameters, and retrieve the desired SPN's based on their inputs. However, to avoid any conflicts with sustainment, I altered it so that the user may login and download the NASA file independently. After the user has downloaded the file with the click of a button, I defined the program to check for any outdated or pre-existing files, for successful downloads, to acquire the spreadsheet, convert it from a text file to a comma separated file and finally into an Excel spreadsheet to be filtered and later scrutinized for specific SPN numbers. Once this file has been automatically manipulated to provide only the SPN numbers that are desired, they are stored in a global variable, shown on the GUI, and

  13. Live From Space Station Outreach Payload Project

    Data.gov (United States)

    National Aeronautics and Space Administration — The Live from Space Station? Outreach Payload (LFSSOP) is a technologically challenging, exciting opportunity for university students to conduct significant research...

  14. China Tightens Control over Petrol Stations

    Institute of Scientific and Technical Information of China (English)

    Sun Huiping

    2002-01-01

    @@ China has recently mounted a nationwide campaign to standardize petrol stations. Based on the reports from China Central Television, all the petrol station that have not been licensed with "Oil Products Retail Permit" issued by the provincial economic and trade commission will be halted for business operation. Such petrol stations will be allowed to resume business if they are in line with the local industrial development plan and obtain the permits after going though all the necessary formalities. The petrol stations that are not in line with the development plan will be closed before August 31,2002.

  15. Weather station with a web server

    OpenAIRE

    Repinc, Matej

    2013-01-01

    In this diploma thesis we present the process of making a cheap weather station using Arduino prototyping platform and its functionality. The weather station monitors current temperature, humidity of air and air pressure. The station has its own simple HTTP server that is used to relay current data in two different formats: JSON encoded data and simple HTML website. The weather station can also send data to a pre-defined server used for data collection. We implemented a web site where data an...

  16. Nuclear electric power safety, operation, and control aspects

    CERN Document Server

    Knowles, J Brian

    2013-01-01

    Assesses the engineering of renewable sources for commercial power generation and discusses the safety, operation, and control aspects of nuclear electric power From an expert who advised the European Commission and UK government in the aftermath of Three Mile Island and Chernobyl comes a book that contains experienced engineering assessments of the options for replacing the existing, aged, fossil-fired power stations with renewable, gas-fired, or nuclear plants. From geothermal, solar, and wind to tidal and hydro generation, Nuclear Electric Power: Safety, Operation, and Control Aspects ass

  17. Local control stations: Human engineering issues and insights

    Energy Technology Data Exchange (ETDEWEB)

    Brown, W.S.; Higgins, J.C.; O`Hara, J.M. [Brookhaven National Lab., Upton, NY (United States)

    1994-09-01

    The objective of this research project was to evaluate current human engineering at local control stations (LCSs) in nuclear power plants, and to identify good human engineering practices relevant to the design of these operator interfaces. General literature and reports of operating experience were reviewed to determine the extent and type of human engineering deficiencies at LCSs in nuclear power plants. In-plant assessments were made of human engineering at single-function as well as multifunction LCSs. Besides confirming the existence of human engineering deficiencies at LCSs, the in-plant assessments provided information about the human engineering upgrades that have been made at nuclear power plants. Upgrades were typically the result of any of three influences regulatory activity, broad industry initiatives such as INPO, and specific in-plant programs (e.g. activities related to training). It is concluded that the quality of LCSs is quite variable and might be improved if there were greater awareness of good practices and existing human engineering guidance relevant to these operator interfaces, which is available from a variety of sources. To make such human engineering guidance more readily accessible, guidelines were compiled from such sources and included in the report as an appendix.

  18. Seasonal changes in H/V spectral ratio at high-latitude seismic stations

    Science.gov (United States)

    Lee, R. F.; Abbott, R. E.; Knox, H. A.; Pancha, A.

    2014-12-01

    We present results demonstrating seasonal variations in the Horizontal-to-Vertical Spectral Ratio (HVSR) at high-latitude seismic stations. We analyze data from two sites at Poker Flat Research Range, near Fairbanks, Alaska. From the first site, we analyze 3 stations installed by Sandia National Labs (SNL) in a valley with marshy summer conditions. We also analyze the PASSCAL Instrument Center station PIC2, which is installed on rock approximately 3.2 km from the SNL stations. These stations continuously record data at 125 (SNL) and 200 (PIC2) samples per second. Seasonal changes in HVSR at high frequencies (> 20 Hz) appear to be caused by impedance contrasts between frozen and thawed ground. Thawed active layers are known to have slower shear-wave velocities than frozen layers or bedrock. An estimate of active layer thickness at each station is obtained from the quarter-wavelength approximation. We verify the accuracy of this technique by obtaining ground-truth measurements at the sites for both thickness and shear-wave velocity. We use physical probing for the thickness measurements and active-source Refraction-Microtremor (ReMi) surveys for the shear-wave velocities. Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000

  19. Next Generation Hydrogen Station Composite Data Products: Retail Stations, Data Through Quarter 3 of 2016

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-03-07

    This publication includes 80 composite data products (CDPs) produced in Spring 2016 for next generation hydrogen stations, with data through the third quarter of 2016. These CDPs include data from retail stations only.

  20. East Baton Rouge Fire Stations, UTM15 NAD83, LAGIC (2002) [ebr_fire_stations

    Data.gov (United States)

    Louisiana Geographic Information Center — This dataset consists of twenty-nine (29) geocoded points representing fire stations in East Baton Rouge parish, Louisiana. Thirty (30) fire station, disctrict, and...