Sample records for daya bay reactor

  1. Daya Bay Reactor Neutrino Project at NERSC

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625govInstrumentstdmadapInactiveVisitingContract Management FermiDavid Turner David Turner David-Turner.jpg1 atDaya

  2. The muon system of the Daya Bay Reactor antineutrino experiment

    E-Print Network [OSTI]

    Daya Bay Collaboration

    2014-11-28T23:59:59.000Z

    The Daya Bay experiment consists of functionally identical antineutrino detectors immersed in pools of ultrapure water in three well-separated underground experimental halls near two nuclear reactor complexes. These pools serve both as shields against natural, low-energy radiation, and as water Cherenkov detectors that efficiently detect cosmic muons using arrays of photomultiplier tubes. Each pool is covered by a plane of resistive plate chambers as an additional means of detecting muons. Design, construction, operation, and performance of these muon detectors are described.

  3. Recent Results from Daya Bay Reactor Neutrino Experiment

    E-Print Network [OSTI]

    Hu, Bei-Zhen

    2015-01-01T23:59:59.000Z

    The Daya Bay reactor neutrino experiment announced the discovery of a non-zero value of \\sin^22\\theta_{13} with significance better than 5 \\sigma in 2012. The experiment is continuing to improve the precision of \\sin^22\\theta_{13} and explore other physics topics. In this talk, I will show the current oscillation and mass-squared difference results which are based on the combined analysis of the measured rates and energy spectra of antineutrino events, an independent measurement of \\theta_{13} using IBD events where delayed neutrons are captured on hydrogens, and a search for light sterile neutrinos.

  4. The Muon System of the Daya Bay Reactor Antineutrino Experiment

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    An, F. P.; Hackenburg, R. W.; Brown, R. E.; Chasman, C.; Dale, E.; Diwan, M. V.; Gill, R.; Hans, S.; Isvan, Z.; Jaffe, D. E.; Kettell, S. H.; Littenberg, L.; Pearson, C. E.; Qian, X.; Theman, H.; Viren, B.; Worcester, E.; Yeh, M.; Zhang, C.

    2015-02-01T23:59:59.000Z

    The Daya Bay experiment consists of functionally identical antineutrino detectors immersed in pools of ultrapure water in three well-separated underground experimental halls near two nuclear reactor complexes. These pools serve both as shields against natural, low-energy radiation, and as water Cherenkov detectors that efficiently detect cosmic muons using arrays of photomultiplier tubes. Each pool is covered by a plane of resistive plate chambers as an additional means of detecting muons. Design, construction, operation, and performance of these muon detectors are described. (auth)

  5. Recent Results From The Daya Bay Experiment

    E-Print Network [OSTI]

    Chao Zhang; for the Daya Bay Collaboration

    2015-01-20T23:59:59.000Z

    The Daya Bay reactor neutrino experiment has observed the disappearance of electron antineutrinos from nuclear reactors at $\\sim$kilometer baselines. The relative measurement of the $\\bar\

  6. Recent Results From The Daya Bay Experiment

    E-Print Network [OSTI]

    Zhang, Chao

    2015-01-01T23:59:59.000Z

    The Daya Bay reactor neutrino experiment has observed the disappearance of electron antineutrinos from nuclear reactors at $\\sim$kilometer baselines. The relative measurement of the $\\bar\

  7. Measuring Sin^22?_13 with the Daya Bay Nuclear Reactors

    E-Print Network [OSTI]

    Yifang Wang

    2006-10-09T23:59:59.000Z

    Angle \\theta_13 is one of the two unknown neutrino mixing parameters to be determined. Its value may determine the future trend of the neutrino physics. We propose to measure sin^22\\theta_13 with a sensitivity better than 0.01 (90% C.L) at the Daya Bay reactor power plant.

  8. Data processing and storage in the Daya Bay Reactor Antineutrino Experiment

    E-Print Network [OSTI]

    He, Miao

    2015-01-01T23:59:59.000Z

    The Daya Bay Reactor Antineutrino Experiment reported the first observation of the non-zero neutrino mixing angle $\\theta_{13}$ using the first 55 days of data. It has also provided the most precise measurement of $\\theta_{13}$ with the extended data to 621 days. Daya Bay will keep running for another 3 years or so. There is about 100 TB raw data produced per year, as well as several copies of reconstruction data with similar volume to the raw data for each copy. The raw data is transferred to Daya Bay onsite and two offsite clusters: IHEP in Beijing and LBNL in California, with a short latency. There is quasi-real-time data processing at both onsite and offsite clusters, for the purpose of data quality monitoring, detector calibration and preliminary data analyses. The physics data production took place a couple of times per year according to the physics analysis plan. This paper will introduce the data movement and storage, data processing and monitoring, and the automation of the calibration.

  9. Waterproofed Photomultiplier Tube Assemblies for the Daya Bay Reactor Neutrino Experiment

    E-Print Network [OSTI]

    Chow, Ken; Edwards, Emily; Edwards, William; Ely, Ry; Hoff, Matthew; Lebanowski, Logan; Li, Bo; Li, Piyi; Lin, Shih-Kai; Liu, Dawei; Liu, Jinchang; Luk, Kam-Biu; Miao, Jiayuan; Napolitano, Jim; Ochoa-Ricoux, Juan Pedro; Peng, Jen-Chieh; Qi, Ming; Steiner, Herbert; Stoler, Paul; Stuart, Mary; Wang, Lingyu; Yang, Changgen; Zhong, Weili

    2015-01-01T23:59:59.000Z

    In the Daya Bay Reactor Neutrino Experiment 960 20-cm-diameter waterproof photomultiplier tubes are used to instrument three water pools as Cherenkov detectors for detecting cosmic-ray muons. Of these 960 photomultiplier tubes, 341 are recycled from the MACRO experiment. A systematic program was undertaken to refurbish them as waterproof assemblies. In the context of passing the water leakage check, a success rate better than 97% was achieved. Details of the design, fabrication, testing, operation, and performance of these waterproofed photomultiplier-tube assemblies are presented.

  10. Leakage Tests of the Stainless Steel Vessels of the Antineutrino Detectors in the Daya Bay Reactor Neutrino Experiment

    E-Print Network [OSTI]

    Xiaohui Chen; Xiaolan Luo; Yuekun Heng; Lingshu Wang; Xiao Tang; Xiaoyan Ma; Honglin Zhuang; Henry Band; Jeff Cherwinka; Qiang Xiao; Karsten M. Heeger

    2012-03-02T23:59:59.000Z

    The antineutrino detectors in the Daya Bay reactor neutrino experiment are liquid scintillator detectors designed to detect low energy particles from antineutrino interactions with high efficiency and low backgrounds. Since the antineutrino detector will be installed in a water Cherenkov cosmic ray veto detector and will run for 3 to 5 years, ensuring water tightness is critical to the successful operation of the antineutrino detectors. We choose a special method to seal the detector. Three leak checking methods have been employed to ensure the seal quality. This paper will describe the sealing method and leak testing results.

  11. A PRECISION MEASUREMENT OF THE NEUTRINO MIXING ANGLE THETA (SUB 13) USING REACTOR ANTINEUTRINOS AT DAYA BAY.

    SciTech Connect (OSTI)

    KETTELL, S.; ET AL.

    2006-10-16T23:59:59.000Z

    This document describes the design of the Daya Bay reactor neutrino experiment. Recent discoveries in neutrino physics have shown that the Standard Model of particle physics is incomplete. The observation of neutrino oscillations has unequivocally demonstrated that the masses of neutrinos are nonzero. The smallness of the neutrino masses (<2 eV) and the two surprisingly large mixing angles measured have thus far provided important clues and constraints to extensions of the Standard Model. The third mixing angle, {delta}{sub 13}, is small and has not yet been determined; the current experimental bound is sin{sup 2} 2{theta}{sub 13} < 0.17 at 90% confidence level (from Chooz) for {Delta}m{sub 31}{sup 2} = 2.5 x 10{sup -3} eV{sup 2}. It is important to measure this angle to provide further insight on how to extend the Standard Model. A precision measurement of sin{sup 2} 2{theta}{sub 13} using nuclear reactors has been recommended by the 2004 APS Multi-divisional Study on the Future of Neutrino Physics as well as a recent Neutrino Scientific Assessment Group (NUSAG) report. We propose to perform a precision measurement of this mixing angle by searching for the disappearance of electron antineutrinos from the nuclear reactor complex in Daya Bay, China. A reactor-based determination of sin{sup 2} 2{theta}{sub 13} will be vital in resolving the neutrino-mass hierarchy and future measurements of CP violation in the lepton sector because this technique cleanly separates {theta}{sub 13} from CP violation and effects of neutrino propagation in the earth. A reactor-based determination of sin{sup 2} 2{theta}{sub 13} will provide important, complementary information to that from long-baseline, accelerator-based experiments. The goal of the Daya Bay experiment is to reach a sensitivity of 0.01 or better in sin{sup 2} 2{theta}{sub 13} at 90% confidence level.

  12. The hunt for theta13 at the Daya Bay nuclear power plant

    E-Print Network [OSTI]

    Wei Wang; for the Daya Bay collaboration

    2009-10-23T23:59:59.000Z

    The Daya Bay reactor neutrino experiment is located at the Daya Bay nuclear power plant in Shenzhen, China. The experiment deploys eight "identical" antineutrino detectors to measure antineutrino fluxes from six 2.9 GW_{th} reactor cores in three underground experimental halls at different distances. The target zone of the Daya Bay detector is filled with 20 t 0.1% Gd doped LAB liquid scintillator. The baseline uncorrelated detector uncertainty is ~0.38% using current experimental techniques. Daya Bay can reach a sensitivity of <0.01 to $sin^2 2theta_{13}$ with baseline uncertainties after 3 years of data taking.

  13. Onsite data processing and monitoring for the Daya Bay Experiment

    E-Print Network [OSTI]

    Ying-Biao Liu; Miao He; Bei-Jiang Liu; Meng Wang; Qiu-Mei Ma; Fa-Zhi Qi; Shan Zeng

    2014-06-09T23:59:59.000Z

    The Daya Bay Reactor Neutrino Experiment started running on September 23, 2011. The offline computing environment, consisting of 11 servers at Daya Bay, was built to process onsite data. With current computing ability, onsite data processing is running smoothly. The Performance Quality Monitoring system (PQM) has been developed to monitor the detector performance and data quality. Its main feature is the ability to efficiently process multi-data-stream from three experimental halls. The PQM processes raw data files from the Daya Bay data acquisition system, generates and publishes histograms via a graphical web interface by executing the user-defined algorithm modules, and saves the histograms for permanent storage. The fact that the whole process takes only around 40 minutes makes it valuable for the shift crew to monitor the running status of all the sub-detectors and the data quality.

  14. Long-Term Testing and Properties of Acrylic for the Daya Bay Antineutrino Detectors

    E-Print Network [OSTI]

    Krohn, M; Heeger, K M

    2012-01-01T23:59:59.000Z

    The Daya Bay reactor antineutrino experiment has recently measured the neutrino mixing parameter sin22{\\theta}13 by observing electron antineutrino disappearance over kilometer-scale baselines using six antineutrino detectors at near and far distances from reactor cores at the Daya Bay nuclear power complex. Liquid scintillator contained in transparent target vessels is used to detect electron antineutrinos via the inverse beta-decay reaction. The Daya Bay experiment will operate for about five years yielding a precision measurement of sin22{\\theta}13. We report on long-term studies of poly(methyl methacrylate) known as acrylic, which is the primary material used in the fabrication of the target vessels for the experiment's antineutrino detectors. In these studies, acrylic samples are subjected to gaseous and liquid environmental conditions similar to those experienced during construction, transport, and operation of the Daya Bay acrylic target vessels and detectors. Mechanical and optical stability of the ac...

  15. Independent measurement of the neutrino mixing angle ?13 via neutron capture on hydrogen at Daya Bay

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Jaffe D. E.; Jaffe, D.E., et al. Daya Bay Collaboration

    2014-10-01T23:59:59.000Z

    A new measurement of the ?13 mixing angle has been obtained at the Daya Bay Reactor Neutrino Experiment via the detection of inverse beta decays tagged by neutron capture on hydrogen. The antineutrino events for hydrogen capture are distinct from those for gadolinium capture with largely different systematic uncertainties, allowing a determination independent of the gadolinium-capture result and an improvement on the precision of the ?13 measurement. With a 217-day antineutrino data set obtained with six antineutrino detectors and from six 2.9 GWth reactors, the rate deficit observed at the far hall is interpreted as sin22?13=0.083±0.018 in the three-flavor oscillationmore »model. When combined with the gadolinium-capture result from Daya Bay, we obtain sin22?13=0.089±0.008 as the final result for the six-antineutrino-detector configuration of the Daya Bay experiment.« less

  16. Independent measurement of the neutrino mixing angle ?13 via neutron capture on hydrogen at Daya Bay

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Jaffe D. E.; Jaffe, D.E., et al. Daya Bay Collaboration

    2014-10-01T23:59:59.000Z

    A new measurement of the ?13 mixing angle has been obtained at the Daya Bay Reactor Neutrino Experiment via the detection of inverse beta decays tagged by neutron capture on hydrogen. The antineutrino events for hydrogen capture are distinct from those for gadolinium capture with largely different systematic uncertainties, allowing a determination independent of the gadolinium-capture result and an improvement on the precision of the ?13 measurement. With a 217-day antineutrino data set obtained with six antineutrino detectors and from six 2.9 GWth reactors, the rate deficit observed at the far hall is interpreted as sin22?13=0.083±0.018 in the three-flavor oscillation model. When combined with the gadolinium-capture result from Daya Bay, we obtain sin22?13=0.089±0.008 as the final result for the six-antineutrino-detector configuration of the Daya Bay experiment.

  17. Search for a Light Sterile Neutrino at Daya Bay

    E-Print Network [OSTI]

    F. P. An; A. B. Balantekin; H. R. Band; W. Beriguete; M. Bishai; S. Blyth; I. Butorov; G. F. Cao; J. Cao; Y. L. Chan; J. F. Chang; L. C. Chang; Y. Chang; C. Chasman; H. Chen; Q. Y. Chen; S. M. Chen; X. Chen; X. Chen; Y. X. Chen; Y. Chen; Y. P. Cheng; J. J. Cherwinka; M. C. Chu; J. P. Cummings; J. de Arcos; Z. Y. Deng; Y. Y. Ding; M. V. Diwan; E. Draeger; X. F. Du; D. A. Dwyer; W. R. Edwards; S. R. Ely; J. Y. Fu; L. Q. Ge; R. Gill; M. Gonchar; G. H. Gong; H. Gong; M. Grassi; W. Q. Gu; M. Y. Guan; X. H. Guo; R. W. Hackenburg; G. H. Han; S. Hans; M. He; K. M. Heeger; Y. K. Heng; P. Hinrichs; Y. K. Hor; Y. B. Hsiung; B. Z. Hu; L. M. Hu; L. J. Hu; T. Hu; W. Hu; E. C. Huang; H. Huang; X. T. Huang; P. Huber; G. Hussain; Z. Isvan; D. E. Jaffe; P. Jaffke; K. L. Jen; S. Jetter; X. P. Ji; X. L. Ji; H. J. Jiang; J. B. Jiao; R. A. Johnson; L. Kang; S. H. Kettell; M. Kramer; K. K. Kwan; M. W. Kwok; T. Kwok; W. C. Lai; K. Lau; L. Lebanowski; J. Lee; R. T. Lei; R. Leitner; A. Leung; J. K. C. Leung; C. A. Lewis; D. J. Li; F. Li; G. S. Li; Q. J. Li; W. D. Li; X. N. Li; X. Q. Li; Y. F. Li; Z. B. Li; H. Liang; C. J. Lin; G. L. Lin; P. Y. Lin; S. K. Lin; Y. C. Lin; J. J. Ling; J. M. Link; L. Littenberg; B. R. Littlejohn; D. W. Liu; H. Liu; J. L. Liu; J. C. Liu; S. S. Liu; Y. B. Liu; C. Lu; H. Q. Lu; K. B. Luk; Q. M. Ma; X. Y. Ma; X. B. Ma; Y. Q. Ma; K. T. McDonald; M. C. McFarlane; R. D. McKeown; Y. Meng; I. Mitchell; J. Monari Kebwaro; Y. Nakajima; J. Napolitano; D. Naumov; E. Naumova; I. Nemchenok; H. Y. Ngai; Z. Ning; J. P. Ochoa-Ricoux; A. Olshevski; S. Patton; V. Pec; J. C. Peng; L. E. Piilonen; L. Pinsky; C. S. J. Pun; F. Z. Qi; M. Qi; X. Qian; N. Raper; B. Ren; J. Ren; R. Rosero; B. Roskovec; X. C. Ruan; B. B. Shao; H. Steiner; G. X. Sun; J. L. Sun; Y. H. Tam; X. Tang; H. Themann; K. V. Tsang; R. H. M. Tsang; C. E. Tull; Y. C. Tung; B. Viren; V. Vorobel; C. H. Wang; L. S. Wang; L. Y. Wang; M. Wang; N. Y. Wang; R. G. Wang; W. Wang; W. W. Wang; X. Wang; Y. F. Wang; Z. Wang; Z. Wang; Z. M. Wang; D. M. Webber; H. Y. Wei; Y. D. Wei; L. J. Wen; K. Whisnant; C. G. White; L. Whitehead; T. Wise; H. L. H. Wong; S. C. F. Wong; E. Worcester; Q. Wu; D. M. Xia; J. K. Xia; X. Xia; Z. Z. Xing; J. Y. Xu; J. L. Xu; J. Xu; Y. Xu; T. Xue; J. Yan; C. C. Yang; L. Yang; M. S. Yang; M. T. Yang; M. Ye; M. Yeh; Y. S. Yeh; B. L. Young; G. Y. Yu; J. Y. Yu; Z. Y. Yu; S. L. Zang; B. Zeng; L. Zhan; C. Zhang; F. H. Zhang; J. W. Zhang; Q. M. Zhang; Q. Zhang; S. H. Zhang; Y. C. Zhang; Y. M. Zhang; Y. H. Zhang; Y. X. Zhang; Z. J. Zhang; Z. Y. Zhang; Z. P. Zhang; J. Zhao; Q. W. Zhao; Y. Zhao; Y. B. Zhao; L. Zheng; W. L. Zhong; L. Zhou; Z. Y. Zhou; H. L. Zhuang; J. H. Zou

    2014-10-08T23:59:59.000Z

    A search for light sterile neutrino mixing was performed with the first 217 days of data from the Daya Bay Reactor Antineutrino Experiment. The experiment's unique configuration of multiple baselines from six 2.9~GW$_{\\rm th}$ nuclear reactors to six antineutrino detectors deployed in two near (effective baselines 512~m and 561~m) and one far (1579~m) underground experimental halls makes it possible to test for oscillations to a fourth (sterile) neutrino in the $10^{\\rm -3}~{\\rm eV}^{2} < |\\Delta m_{41}^{2}| < 0.3~{\\rm eV}^{2}$ range. The relative spectral distortion due to electron antineutrino disappearance was found to be consistent with that of the three-flavor oscillation model. The derived limits on $\\sin^22\\theta_{14}$ cover the $10^{-3}~{\\rm eV}^{2} \\lesssim |\\Delta m^{2}_{41}| \\lesssim 0.1~{\\rm eV}^{2}$ region, which was largely unexplored.

  18. Long-Term Testing and Properties of Acrylic for the Daya Bay Antineutrino Detectors

    E-Print Network [OSTI]

    M. Krohn; B. R. Littlejohn; K. M. Heeger

    2012-06-09T23:59:59.000Z

    The Daya Bay reactor antineutrino experiment has recently measured the neutrino mixing parameter sin22{\\theta}13 by observing electron antineutrino disappearance over kilometer-scale baselines using six antineutrino detectors at near and far distances from reactor cores at the Daya Bay nuclear power complex. Liquid scintillator contained in transparent target vessels is used to detect electron antineutrinos via the inverse beta-decay reaction. The Daya Bay experiment will operate for about five years yielding a precision measurement of sin22{\\theta}13. We report on long-term studies of poly(methyl methacrylate) known as acrylic, which is the primary material used in the fabrication of the target vessels for the experiment's antineutrino detectors. In these studies, acrylic samples are subjected to gaseous and liquid environmental conditions similar to those experienced during construction, transport, and operation of the Daya Bay acrylic target vessels and detectors. Mechanical and optical stability of the acrylic as well as its interaction with detector liquids is reported.

  19. Independent measurement of the neutrino mixing angle ?13 via neutron capture on hydrogen at Daya Bay

    SciTech Connect (OSTI)

    Jaffe D. E.; Jaffe, D.E., et al. Daya Bay Collaboration

    2014-10-01T23:59:59.000Z

    A new measurement of the ?13 mixing angle has been obtained at the Daya Bay Reactor Neutrino Experiment via the detection of inverse beta decays tagged by neutron capture on hydrogen. The antineutrino events for hydrogen capture are distinct from those for gadolinium capture with largely different systematic uncertainties, allowing a determination independent of the gadolinium-capture result and an improvement on the precision of the ?13 measurement. With a 217-day antineutrino data set obtained with six antineutrino detectors and from six 2.9 GWth reactors, the rate deficit observed at the far hall is interpreted as sin22?13=0.083±0.018 in the three-flavor oscillation model. When combined with the gadolinium-capture result from Daya Bay, we obtain sin22?13=0.089±0.008 as the final result for the six-antineutrino-detector configuration of the Daya Bay experiment.

  20. advanced fission reactors: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Daya Bay reactor core, and compare its with those calculated by the commercial reactor simulation program SCIENCE, which is used by the Daya Bay nuclear power plant, and the...

  1. Design, characterization, and sensitivity of the supernova trigger system at Daya Bay

    E-Print Network [OSTI]

    Wei, Hanyu; Li, Fei; Wang, Zhe; Chen, Shaomin

    2015-01-01T23:59:59.000Z

    Providing an early warning of galactic supernova explosions from neutrino signals is important in studying supernova dynamics and neutrino physics. A dedicated supernova trigger system has been designed and installed in the data acquisition system at Daya Bay and integrated into the worldwide Supernova Early Warning System (SNEWS). Daya Bay's unique feature of eight identically-designed detectors deployed in three separate experimental halls makes the trigger system naturally robust against cosmogenic backgrounds, enabling a prompt analysis of online triggers and a tight control of the false-alert rate. The trigger system is estimated to be fully sensitive to 1987A-type supernova bursts throughout most of the Milky Way. The significant gain in sensitivity of the eight-detector configuration over a mass-equivalent single detector is also estimated. The experience of this online trigger system is applicable to future projects with spatially distributed detectors.

  2. Design, characterization, and sensitivity of the supernova trigger system at Daya Bay

    E-Print Network [OSTI]

    Hanyu Wei; Logan Lebanowski; Fei Li; Zhe Wang; Shaomin Chen

    2015-05-11T23:59:59.000Z

    Providing an early warning of galactic supernova explosions from neutrino signals is important in studying supernova dynamics and neutrino physics. A dedicated supernova trigger system has been designed and installed in the data acquisition system at Daya Bay and integrated into the worldwide Supernova Early Warning System (SNEWS). Daya Bay's unique feature of eight identically-designed detectors deployed in three separate experimental halls makes the trigger system naturally robust against cosmogenic backgrounds, enabling a prompt analysis of online triggers and a tight control of the false-alert rate. The trigger system is estimated to be fully sensitive to 1987A-type supernova bursts throughout most of the Milky Way. The significant gain in sensitivity of the eight-detector configuration over a mass-equivalent single detector is also estimated. The experience of this online trigger system is applicable to future projects with spatially distributed detectors.

  3. Daya Bay

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625govInstrumentstdmadapInactiveVisitingContract Management FermiDavid Turner David Turner David-Turner.jpg1 at

  4. The Daya Bay Reactor Neutrino Experiment Sees Evidence that Electron

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over Our InstagramStructureProposedPAGESafetyTed5, 2015ComputingTotal Wind89 060520

  5. The Daya Bay Nuclear Plant Project in the Light of International Environmental Law

    E-Print Network [OSTI]

    Mushkat, Roda

    1990-01-01T23:59:59.000Z

    result from locating a nuclear plant so close to the Hongat 1292 (1975). THE DA YA BAY NUCLEAR PLANT PROJECT national1986) (H.K. ). THE DA YA BAY NUCLEAR PLANT PROJECT IV. THE "

  6. Preparation of Gd Loaded Liquid Scintillator for Daya Bay Neutrino Experiment

    SciTech Connect (OSTI)

    Ding Yayun; Zhang Zhiyong [Key Laboratory of Nuclear Analytical Techniques, Institute of High Energy Physics, the Chinese Academy of Sciences, Beijing 100049 (China)

    2010-05-12T23:59:59.000Z

    Gadolinium loaded liquid scintillator (Gd-LS) is an excellent target material for reactor antineutrino experiments. Ideal Gd-LS should have long attenuation length, high light yield, long term stability, low toxicity, and should be compatible with the material used to build the detector. We have developed a new Gd-LS recipe in which carboxylic acid 3,5,5-trimethylhexanoic acid is used as the complexing ligand to gadolinium, 2,5-diphenyloxazole (PPO) and 1,4-bis[2-methylstyryl]benzene (bis-MSB) are used as primary fluor and wavelength shifter, respectively. The scintillator base is linear alkyl benzene (LAB). Eight hundred liters of Gd-LS has been synthesized and tested in a prototype detector. Results show that the Gd-LS has high quality and is suitable for underground experiments in large quantity. Large scale production facility has been built. A full batch production of 4 t Gd-LS has been produced and monitored for several months. The production of 180 t Gd-LS will be carried out in the near future.

  7. The Water Purification System for the Daya Bay Reactor Neutrino Experiment

    E-Print Network [OSTI]

    J. Wilhelmi; R. Bopp; R. Brown; J. Cherwinka; J. Cummings; E. Dale; M. Diwan; J. Goett; R. W. Hackenburg; J. Kilduff; L. Littenberg; G. S. Li; X. N. Li; J. C. Liu; H. Q. Lu; J. Napolitano; C. Pearson; N. Raper; R. Rosero; P. Stoler; Q. Xiao; C. G. Yang; Y. Yang; M. Yeh

    2014-08-06T23:59:59.000Z

    We describe the design, installation, and operation of a purification system that is able to provide large volumes of high purity ASTM (D1193-91) Type-I water to a high energy physics experiment. The water environment is underground in a lightly sealed system, and this provides significant challenges to maintaining high purity in the storage pools, each of which contains several thousand cubic meters. High purity is dictated by the need for large optical absorption length, which is critical for the operation of the experiment. The system is largely successful, and the water clarity criteria are met. We also include a discussion of lessons learned.

  8. Uncertainties analysis of fission fraction for reactor antineutrino experiments using DRAGON

    E-Print Network [OSTI]

    X. B. Ma; L. Z. Wang; Y. X. Chen; W. L. Zhong; F. P. An

    2014-05-27T23:59:59.000Z

    Rising interest in nuclear reactors as a source of antineutrinos for experiments motivates validated, fast, and accessible simulation to predict reactor rates. First, DRAGON was developed to calculate the fission rates of the four most important isotopes in fissions,235U,238U,239Pu and141Pu, and it was validated for PWRs using the Takahama benchmark. The fission fraction calculation function was validated through comparing our calculation results with MIT's results. we calculate the fission fraction of the Daya Bay reactor core, and compare its with those calculated by the commercial reactor simulation program SCIENCE, which is used by the Daya Bay nuclear power plant, and the results was consist with each other. The uncertainty of the antineutrino flux by the fission fraction was studied, and the uncertainty of the antineutrino flux by the fission fraction simulation is 0.6% per core for Daya Bay antineutrino experiment.

  9. Uncertainties analysis of fission fraction for reactor antineutrino experiments

    E-Print Network [OSTI]

    X. B. Ma; F. Lu; L. Z. Wang; Y. X. Chen; W. L. Zhong; F. P. An

    2015-03-17T23:59:59.000Z

    Reactor antineutrino experiment are used to study neutrino oscillation, search for signatures of nonstandard neutrino interaction, and monitor reactor operation for safeguard application. Reactor simulation is an important source of uncertainties for a reactor neutrino experiment. Commercial code is used for reactor simulation to evaluate fission fraction in Daya Bay neutrino experiment, but the source code doesn't open to our researcher results from commercial secret. In this study, The open source code DRAGON was improved to calculate the fission rates of the four most important isotopes in fissions, $^{235}$U,$^{238}$U,$^{239}$Pu and $^{241}$Pu, and then was validated for PWRs using the Takahama-3 benchmark. The fission fraction results are consistent with those of MIT's results. Then, fission fraction of Daya Bay reactor core was calculated by using improved DRAGON code, and the fission fraction calculated by DRAGON agreed well with these calculated by SCIENCE. The average deviation less than 5\\% for all the four isotopes. The correlation coefficient matrix between $^{235}$U,$^{238}$U,$^{239}$Pu and $^{241}$Pu were also studied using DRAGON, and then the uncertainty of the antineutrino flux by the fission fraction was calculated by using the correlation coefficient matrix. The uncertainty of the antineutrino flux by the fission fraction simulation is 0.6\\% per core for Daya Bay antineutrino experiment. The uncertainties source of fission fraction calculation need further to be studied in the future.

  10. Reactor Neutrino Experiments

    E-Print Network [OSTI]

    Jun Cao

    2007-12-06T23:59:59.000Z

    Precisely measuring $\\theta_{13}$ is one of the highest priority in neutrino oscillation study. Reactor experiments can cleanly determine $\\theta_{13}$. Past reactor neutrino experiments are reviewed and status of next precision $\\theta_{13}$ experiments are presented. Daya Bay is designed to measure $\\sin^22\\theta_{13}$ to better than 0.01 and Double Chooz and RENO are designed to measure it to 0.02-0.03. All are heading to full operation in 2010. Recent improvements in neutrino moment measurement are also briefed.

  11. Yale High Energy Physics Research: Precision Studies of Reactor Antineutrinos

    SciTech Connect (OSTI)

    Heeger, Karsten M [Yale University

    2014-09-13T23:59:59.000Z

    This reports presents experimental research at the intensity frontier of particle physics with particular focus on the study of reactor antineutrinos and the precision measurement of neutrino oscillations. The experimental neutrino physics group of Professor Heeger and Senior Scientist Band at Yale University has had leading responsibilities in the construction and operation of the Daya Bay Reactor Antineutrino Experiment and made critical contributions to the discovery of non-zero$\\theta_{13}$. Heeger and Band led the Daya Bay detector management team and are now overseeing the operations of the antineutrino detectors. Postdoctoral researchers and students in this group have made leading contributions to the Daya Bay analysis including the prediction of the reactor antineutrino flux and spectrum, the analysis of the oscillation signal, and the precision determination of the target mass yielding unprecedented precision in the relative detector uncertainty. Heeger's group is now leading an R\\&D effort towards a short-baseline oscillation experiment, called PROSPECT, at a US research reactor and the development of antineutrino detectors with advanced background discrimination.

  12. Four-neutrino analysis of 1.5km-baseline reactor antineutrino oscillations

    E-Print Network [OSTI]

    Kang, Sin Kyu; Ko, Young-Ju; Siyeon, Kim

    2014-01-01T23:59:59.000Z

    The masses of sterile neutrinos are not yet known, and depending on the orders of magnitudes, their existence may explain reactor anomalies or the spectral shape of reactor neutrino events at 1.5km-baseline detector. Here, we present four-neutrino analysis of the results announced by RENO and Daya Bay, which performed the definitive measurements of $\\theta_{13}$ based on the disappearance of reactor antineutrinos at km-order baselines. Our results using 3+1 scheme include the exclusion curve of $\\Delta m^2_{41}$ vs. $\\theta_{14}$ and the adjustment of $\\theta_{13}$ due to correlation with $\\theta_{14}$. The value of $\\theta_{13}$ obtained by RENO and Daya Bay with a three-neutrino oscillation analysis is included in the $1\\sigma$ interval of $\\theta_{13}$ allowed by our four-neutrino analysis.

  13. Four-neutrino analysis of 1.5km-baseline reactor antineutrino oscillations

    E-Print Network [OSTI]

    Sin Kyu Kang; Yeong-Duk Kim; Young-Ju Ko; Kim Siyeon

    2014-08-19T23:59:59.000Z

    The masses of sterile neutrinos are not yet known, and depending on the orders of magnitudes, their existence may explain reactor anomalies or the spectral shape of reactor neutrino events at 1.5km-baseline detector. Here, we present four-neutrino analysis of the results announced by RENO and Daya Bay, which performed the definitive measurements of $\\theta_{13}$ based on the disappearance of reactor antineutrinos at km-order baselines. Our results using 3+1 scheme include the exclusion curve of $\\Delta m^2_{41}$ vs. $\\theta_{14}$ and the adjustment of $\\theta_{13}$ due to correlation with $\\theta_{14}$. The value of $\\theta_{13}$ obtained by RENO and Daya Bay with a three-neutrino oscillation analysis is included in the $1\\sigma$ interval of $\\theta_{13}$ allowed by our four-neutrino analysis.

  14. Observations of Fallout from the Fukushima Reactor Accident in San Francisco Bay Area Rainwater

    E-Print Network [OSTI]

    Eric B. Norman; Christopher T. Angell; Perry A. Chodash

    2011-03-30T23:59:59.000Z

    We have observed fallout from the recent Fukushima Dai-ichi reactor accident in samples of rainwater collected in the San Francisco Bay area. Gamma ray spectra measured from these samples show clear evidence of fission products - 131,132I, 132Te, and 134,137Cs. The activity levels we have measured for these isotopes are very low and pose no health risk to the public.

  15. Reactor Antineutrino Anomaly with known ?_{13}

    E-Print Network [OSTI]

    C. Zhang; X. Qian; P. Vogel

    2013-04-18T23:59:59.000Z

    We revisit the reactor antineutrino anomaly using the recent reactor flux independent determination of sizable theta?13 by considering the full set of the absolute reactor electron antineutrino flux measurements. When normalized to the predicted flux of Mueller et al. [1], the new world average, after including results from Palo Verde, Chooz, and Double Chooz, is 0.959 +- 0.009 (experiment uncertainty) +- 0.027 (flux systematics). Including the data with kilometer baseline, the new world average is only about 1.4 sigma lower than the unity, weakening the significance of the reactor antineutrino anomaly. The upcoming results from Daya Bay, RENO, and the Double Chooz will provide further information about this issue.

  16. Review of Reactor Neutrino Oscillation Experiments

    E-Print Network [OSTI]

    C. Mariani

    2012-02-05T23:59:59.000Z

    In this document we will review the current status of reactor neutrino oscillation experiments and present their physics potentials for measuring the $\\theta_{13}$ neutrino mixing angle. The neutrino mixing angle $\\theta_{13}$ is currently a high-priority topic in the field of neutrino physics. There are currently three different reactor neutrino experiments, \\textsc{Double Chooz}, \\textsc{Daya Bay} and \\textsc{Reno} and a few accelerator neutrino experiments searching for neutrino oscillations induced by this angle. A description of the reactor experiments searching for a non-zero value of $\\theta_{13}$ is given, along with a discussion of the sensitivities that these experiments can reach in the near future.

  17. Constraining Sterile Neutrinos Using Reactor Neutrino Experiments

    E-Print Network [OSTI]

    Ivan Girardi; Davide Meloni; Tommy Ohlsson; He Zhang; Shun Zhou

    2014-08-21T23:59:59.000Z

    Models of neutrino mixing involving one or more sterile neutrinos have resurrected their importance in the light of recent cosmological data. In this case, reactor antineutrino experiments offer an ideal place to look for signatures of sterile neutrinos due to their impact on neutrino flavor transitions. In this work, we show that the high-precision data of the Daya Bay experi\\-ment constrain the 3+1 neutrino scenario imposing upper bounds on the relevant active-sterile mixing angle $\\sin^2 2 \\theta_{14} \\lesssim 0.06$ at 3$\\sigma$ confidence level for the mass-squared difference $\\Delta m^2_{41}$ in the range $(10^{-3},10^{-1}) \\, {\\rm eV^2}$. The latter bound can be improved by six years of running of the JUNO experiment, $\\sin^22\\theta_{14} \\lesssim 0.016$, although in the smaller mass range $ \\Delta m^2_{41} \\in (10^{-4} ,10^{-3}) \\, {\\rm eV}^2$. We have also investigated the impact of sterile neutrinos on precision measurements of the standard neutrino oscillation parameters $\\theta_{13}$ and $\\Delta m^2_{31}$ (at Daya Bay and JUNO), $\\theta_{12}$ and $\\Delta m^2_{21}$ (at JUNO), and most importantly, the neutrino mass hierarchy (at JUNO). We find that, except for the obvious situation where $\\Delta m^2_{41}\\sim \\Delta m^2_{31}$, sterile states do not affect these measurements substantially.

  18. Reactor Neutrino Flux Uncertainty Suppression on Multiple Detector Experiments

    E-Print Network [OSTI]

    Cucoanes, Andi; Cabrera, Anatael; Fallot, Muriel; Onillon, Anthony; Obolensky, Michel; Yermia, Frederic

    2015-01-01T23:59:59.000Z

    This publication provides a coherent treatment for the reactor neutrino flux uncertainties suppression, specially focussed on the latest $\\theta_{13}$ measurement. The treatment starts with single detector in single reactor site, most relevant for all reactor experiments beyond $\\theta_{13}$. We demonstrate there is no trivial error cancellation, thus the flux systematic error can remain dominant even after the adoption of multi-detector configurations. However, three mechanisms for flux error suppression have been identified and calculated in the context of Double Chooz, Daya Bay and RENO sites. Our analysis computes the error {\\it suppression fraction} using simplified scenarios to maximise relative comparison among experiments. We have validated the only mechanism exploited so far by experiments to improve the precision of the published $\\theta_{13}$. The other two newly identified mechanisms could lead to total error flux cancellation under specific conditions and are expected to have major implications o...

  19. Reactor Neutrino Flux Uncertainty Suppression on Multiple Detector Experiments

    E-Print Network [OSTI]

    Andi Cucoanes; Pau Novella; Anatael Cabrera; Muriel Fallot; Anthony Onillon; Michel Obolensky; Frederic Yermia

    2015-01-02T23:59:59.000Z

    This publication provides a coherent treatment for the reactor neutrino flux uncertainties suppression, specially focussed on the latest $\\theta_{13}$ measurement. The treatment starts with single detector in single reactor site, most relevant for all reactor experiments beyond $\\theta_{13}$. We demonstrate there is no trivial error cancellation, thus the flux systematic error can remain dominant even after the adoption of multi-detector configurations. However, three mechanisms for flux error suppression have been identified and calculated in the context of Double Chooz, Daya Bay and RENO sites. Our analysis computes the error {\\it suppression fraction} using simplified scenarios to maximise relative comparison among experiments. We have validated the only mechanism exploited so far by experiments to improve the precision of the published $\\theta_{13}$. The other two newly identified mechanisms could lead to total error flux cancellation under specific conditions and are expected to have major implications on the global $\\theta_{13}$ knowledge today. First, Double Chooz, in its final configuration, is the only experiment benefiting from a negligible reactor flux error due to a $\\sim$90\\% geometrical suppression. Second, Daya Bay and RENO could benefit from their partial geometrical cancellation, yielding a potential $\\sim$50\\% error suppression, thus significantly improving the global $\\theta_{13}$ precision today. And third, we illustrate the rationale behind further error suppression upon the exploitation of the inter-reactor error correlations, so far neglected. So, our publication is a key step forward in the context of high precision neutrino reactor experiments providing insight on the suppression of their intrinsic flux error uncertainty, thus affecting past and current experimental results, as well as the design of future experiments.

  20. Supplementary Data to Global risk of radioactive fallout after nuclear reactor accidents

    E-Print Network [OSTI]

    Meskhidze, Nicholas

    Afrika Koeberg 1 PWR operational 900 944 04.04.1984 (14.08.2024) 127.092 Koeberg 2 PWR operational 900 under construction since 2010 610 650 ­ ­ ­ Daya Bay (Guangdong) 1 PWR operational 944 984 31.08.1993 (06.05.2034) 93.096 Daya Bay (Guangdong) 2 PWR operational 944 984 07.02.1994 (31.01.2034) 91

  1. Assessing conformance to safety goals using nonparametric empirical Bayes methods: A nuclear reactor application

    SciTech Connect (OSTI)

    Martz, H.F.; Johnson, J.W. [Los Alamos National Lab., NM (United States)

    1997-01-01T23:59:59.000Z

    Nonparametric empirical Bayes methods are used to develop decision criteria for use in deciding whether the risk of a given facility is compatible with a corresponding specified quantitative safety goal. The criteria utilize the uncertain results of a probabilistic risk assessment (PRA) and are derived from an empirical Bayes point of view in which the results from a set of similar facilities are used to estimate the population variability curve (PVC) for the parameter of interest. The PVC is estimated nonparametrically in the sense that the distributional family to which the PVC belongs is completely unknown and unspecified. For the assumed model, the method guarantees that all facilities ultimately accepted as being compatible with the goal have a prespecified exact assurance probability that the goal is not exceeded. The method also accounts for two possible biases in the PRA results. Criteria are developed for use in assessing the compatibility of nuclear power plant PRA-produced severe core damage frequency estimates with a corresponding subsidiary objective.

  2. 42484 secretarys achievement award - 5 x 6 - Building 51

    Office of Environmental Management (EM)

    Daya Bay Reactor Neutrino Detector Project Daniel B. Poneman Acting Secretary of Energy Secretary's Achievement Award United States Department of Energy Presented to May 2013 The...

  3. Geek-Up[2.24.2011]: Dynamical Fingerprints and Daya Bay

    Broader source: Energy.gov [DOE]

    Researchers at Oak Ridge National Lab have a developed “fingerprints” to match the results of experiments with data from supercomputer simulations that investigates how molecules move and interact. This technology will help researchers tackle scientific challenges in areas like biofuels, drug development, materials design and fundamental biological processes -- all of which require deep understanding of molecular movement.

  4. Photo of the Week: The Daya Bay Antineutrino Detector | Department of

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed offOCHCO Overview OCHCO Overview OCHCO OCHCOControlGuide to aEnergy Living Large

  5. Key Neutrino behavior observed at Daya Bay (The College of William and

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes |Is Your Home as ReadyAppointed toCAMD TargetsKevinAna Moore

  6. university-logo Bayes's theorem

    E-Print Network [OSTI]

    McCullagh, Peter

    university-logo Bayes's theorem Poisson processes Improper mixtures and Bayes's theorem Peter Mc McCullagh Improper mixtures #12;university-logo Bayes's theorem Poisson processes Outline 1 BayesCullagh Improper mixtures #12;university-logo Bayes's theorem Poisson processes Improper mixtures Bayes's theorem

  7. San Diego Bay Bibliography

    E-Print Network [OSTI]

    Brueggeman, Peter

    1994-01-01T23:59:59.000Z

    oil-fired steam-electric stations (South Bay, Silvergate, and Encina); their pH adjustment and clarification, sludge

  8. RICHMOND BAY CAMPUS RICHMOND BAY CAMPUS

    E-Print Network [OSTI]

    Lee, Jason R.

    will be excavated in advance of Phase 1 development. · Other soil contamination at the RFS to be managed CAMPUS #12;RICHMOND BAY CAMPUS #12;RICHMOND BAY CAMPUS Multi-Modal Access · Transportation Demand Management program would be in place prior to completion of first phase development, with priority

  9. San Diego Bay Bibliography

    E-Print Network [OSTI]

    Brueggeman, Peter

    1994-01-01T23:59:59.000Z

    South Bay Power Plant, San Diego, California. Woodward-Station B Power Plant in San Diego, California, operated byPower Plant Receiving Water Monitoring Program. Prepared for the California

  10. Nonlinear Wavelet Shrinkage With Bayes Rules and Bayes Brani Vidakovic

    E-Print Network [OSTI]

    West, Mike

    Nonlinear Wavelet Shrinkage With Bayes Rules and Bayes Factors Brani Vidakovic 1 #12; Brani, associate editor, and the two anonymous referees for insightful comments. 2 #12; Wavelet shrinkage of denoising data. Shrinking wavelet coefficients was proposed from several optimality criteria

  11. Chesapeake Bay Restoration Act (Maryland)

    Broader source: Energy.gov [DOE]

    This legislation sets limits on development near Chesapeake Bay as well as on dredging and the deposition of dredged material into the bay. The legislation establishes the Cox Creek Citizens...

  12. Cedar Bay overview

    SciTech Connect (OSTI)

    Garvey, J.F.

    1994-12-31T23:59:59.000Z

    The Cedar Bay Cogeneration Facility is located on the north side of Jacksonville, Florida adjacent to the Broward River and Eastport Road. The facility is co-located on a site with the Seminole Kraft Paper Mill. The facility is owned by Cedar Bay Generating Company (CBGC) Limited Partnership, managed by US Generating Company and Operated by US Operating Services Company. The engineering, procurement and construction (EPC) of the facility was contracted through Multipower Associates. Multipower is a joint venture comprised of Pyropower Corporation, National Power Development, Inc. (NPDI) and the Pritchard Corporation. Black & Veatch provided turnkey construction management services and the prime contractor was H.B. Zachry.

  13. 360 NATURE PHYSICS | VOL 8 | MAY 2012 | www.nature.com/naturephysics news & views

    E-Print Network [OSTI]

    Loss, Daniel

    as Double Chooz and Daya Bay, but it has two 16-ton detectors and six reactors. RENO has upped the ante of experiment (that is, for accelerator-generated neutrino beams as well as reactor-generated neutrino fluxes, Bottke et al. were able to infer the probable ages of lunar and terrestrial basins. Their inferences

  14. Chesapeake Bay Preservation Programs (Multiple States)

    Broader source: Energy.gov [DOE]

    The Chesapeake Bay Program is a unique regional partnership that has led and directed the restoration of the Chesapeake Bay since 1983. The Chesapeake Bay Program partners include the states of...

  15. Field's Point Wastewater Treatment Facility (Narragansett Bay...

    Open Energy Info (EERE)

    Field's Point Wastewater Treatment Facility (Narragansett Bay Commission) Jump to: navigation, search Name Field's Point Wastewater Treatment Facility (Narragansett Bay Commission)...

  16. Richmond Bay Campus: Project Update

    E-Print Network [OSTI]

    Lee, Jason R.

    Coordinate with City of Richmond South Shoreline Area planning #12;Richmond Bay Campus Vision A stateRichmond Bay Campus: Project Update Prepared for the Richmond City Council October 1, 2013 #12 and UCB · City of Richmond Updates · Summary · Questions & Answers #12;LBNL Project Update #12;University

  17. Land Cover, Land Use of twoLand Cover, Land Use of two bioluminescent bays in Puerto Ricobioluminescent bays in Puerto Ricobioluminescent bays in Puerto Ricobioluminescent bays in Puerto Rico

    E-Print Network [OSTI]

    Gilbes, Fernando

    Bay inin ViequesVieques andandLandLand aroundaround PuertoPuerto MosquitoMosquito BayBay inin ViequesVieques andand LaLa PargueraParguera BioluminescenceBioluminescence BayBay inin Lajas,Lajas, PuertoPuerto RicoBioluminescent BayBay hashas shownshown aa decreasedecrease inin itsits bioluminescencebioluminescence byby

  18. Supernova Neutrinos Detection On Earth

    E-Print Network [OSTI]

    Xin-Heng Guo; Ming-Yang Huang; Bing-Lin Young

    2009-05-12T23:59:59.000Z

    In this paper, we first discuss the detection of supernova neutrino on Earth. Then we propose a possible method to acquire information about $\\theta_{13}$ smaller than $1.5^\\circ$ by detecting the ratio of the event numbers of different flavor supernova neutrinos. Such an sensitivity cannot yet be achieved by the Daya Bay reactor neutrino experiment.

  19. Acoustic characteristics of bay bottom sediments in Lavaca Bay, TX

    E-Print Network [OSTI]

    Patch, Mary Catherine

    2005-08-29T23:59:59.000Z

    acoustic return of the bay bottom, and 2) strong, shallow reflectors??surface strong, mounds, buried strong, andburied multiples, which describe strong acoustic returns in the upper 5 m of stratigraphy. Within the lower package, four categories were...

  20. Marcus Hutter -1 -Online Prediction Bayes versus Experts Online Prediction

    E-Print Network [OSTI]

    Hutter, Marcus

    Marcus Hutter - 1 - Online Prediction ­ Bayes versus Experts Online Prediction: Bayes versus;Marcus Hutter - 2 - Online Prediction ­ Bayes versus Experts Table of Contents · Sequential/online prediction: Setup · Bayesian Sequence Prediction (Bayes) · Prediction with Expert Advice (PEA) · PEA Bounds

  1. Jamaica Bay New York's Conflicted Backyard

    E-Print Network [OSTI]

    Columbia University

    Jamaica Bay ­ New York's Conflicted Backyard Kevin Olsen Drew Symposium October 2008 #12;Why Study Jamaica Bay's History? Jamaica Bay has served many uses for the people of New York. At one time or another shoals, mudflats, sand bars, open water (littoral zone), intertidal zones (low and high marshes

  2. Empirical Bayes Estimation of Reliability

    E-Print Network [OSTI]

    Pensky, Marianna

    types of equipment relies on statistical inference about char- acteristics of reliabilityEmpirical Bayes Estimation of Reliability Introduction Assessment of the reliability of various such as reliability function, mean lifetime of the devices, or failure rate. Gen- eral techniques of statistical

  3. MODELING THE FATE AND TRANSPORT OF ATRAZINE IN THE UPPER CHESAPEAKE BAY

    E-Print Network [OSTI]

    Frei, Allan

    for agrochemicals in the Upper Chesapeake Bay. Keywords: Chesapeake Bay, hydrodynamic model, atrazine, photolysis

  4. Background Bayes Factor Simulation Study BF And PPP Using Bayes Factors for Model Selection in

    E-Print Network [OSTI]

    Wolfe, Patrick J.

    Background Bayes Factor Simulation Study BF And PPP Using Bayes Factors for Model Selection in High Study BF And PPP Model Comparison in Astrophysics Nested models (line detection in spectral analysis" to formally compare or select a model. #12;Background Bayes Factor Simulation Study BF And PPP Spectral

  5. Recent Sediments of Monterey Bay, California

    E-Print Network [OSTI]

    Yancey, T. E.

    1968-01-01T23:59:59.000Z

    metamorphic ciscan in the Salinas basin. The Salinian whichstations, The Salinas Salinas Basin all water basin canof the Salinas Valley Range, drainage and basin. N BAY SCALE

  6. altona bay st: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    stochastic planning. 1 Introduction Dekhtyar, Alexander 83 BAY AREA PARK RELATIONAL CREEK Computer Technologies and Information Sciences Websites Summary: BAY AREA PARK CODD...

  7. admiralty bay antarctica: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    E. Distefano; S. Messina; G. Cutispoto 2008-07-18 103 BAY AREA PARK RELATIONAL CREEK Computer Technologies and Information Sciences Websites Summary: BAY AREA PARK CODD...

  8. apalachicola bay usa: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    of 192 NAME: Habitat Restoration in Kaneohe Bay, Hawaii LOCATION: Kaneohe Bay, County of Honolulu, Hawaii Engineering Websites Summary: ACRES: 13 acres coral reef...

  9. ariake bay japan: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Bay: Episodic growth of the Laurentian mantle keel Geosciences Websites Summary: Seismic imaging of the lithosphere beneath Hudson Bay: Episodic growth of the Laurentian...

  10. Bay Bridge Lights Presentation prepared by Zoon Engineering

    Energy Savers [EERE]

    2015 BAY BRIDGE LIGHTS Presentation prepared by Zoon Engineering Presentation Outline Lighting of the New East Span of the Bay Bridge Brief Over view Lighting Facts ...

  11. ARRA Proposed Award: Retrofit Bay Area

    E-Print Network [OSTI]

    ARRA Proposed Award: Retrofit Bay Area Counties of Alameda, Contra Costa, Marin, San Francisco per year Prime contractor: Association of Bay Area Governments (ABAG) Sub contractors: Alameda County Waste Management Authority (StopWaste.org) County of Contra Costa County of Marin City

  12. Low Oxygen Environments in Chesapeake Bay

    E-Print Network [OSTI]

    Boynton, Walter R.

    Low Oxygen Environments in Chesapeake Bay Jeremy Testa Chesapeake Biological Laboratory University of Maryland Center for Environmental Science Why we care about low oxygen? What causes low oxygen? Where and When does Chesapeake Bay lose oxygen? #12;#12;Hypoxia and Chesapeake Animals Low dissolved oxygen

  13. Nuclear reactor engineering

    SciTech Connect (OSTI)

    Glasstone, S.; Sesonske, A.

    1981-01-01T23:59:59.000Z

    Chapters are presented concerning energy from nuclear fission; nuclear reactions and radiations; diffusion and slowing-down of neutrons; principles of reactor analysis; nuclear reactor kinetics and control; energy removal; non-fuel reactor materials; the reactor fuel system; radiation protection and environmental effects; nuclear reactor shielding; nuclear reactor safety; and power reactor systems.

  14. New and Underutilized Technology: High Bay LED Lighting

    Broader source: Energy.gov [DOE]

    The following information outlines key deployment considerations for high bay LED lighting within the Federal sector.

  15. A study of the Galveston Bay bait-shrimp fishery

    E-Print Network [OSTI]

    Lamkin, John Tillman

    1984-01-01T23:59:59.000Z

    :1 with a yearly average of 4:1. Watts and pellegrin (1982) working off Texas and Louisiana reported ratios ranging from 3. 8:1 (& 10 fm) and 13. 9:1 (0-10 fm) in 1981 to 1. 7:1 and 4. 6:1, respectively, in 1982. Composition of the incidental catch... AREA Offatts Bayou West Bay Offatts Bayou West Bay Offatts Bayou West Bay Offatts Bayou West Bay % OF TOWS 26 74 50 50 7 93 6 94 November 1981 Lower Galveston Bay 28 West Bay 72 December 1981 Lower Galveston Bay 100 May 1982 June...

  16. Bioconversion reactor

    DOE Patents [OSTI]

    McCarty, Perry L. (Stanford, CA); Bachmann, Andre (Palo Alto, CA)

    1992-01-01T23:59:59.000Z

    A bioconversion reactor for the anaerobic fermentation of organic material. The bioconversion reactor comprises a shell enclosing a predetermined volume, an inlet port through which a liquid stream containing organic materials enters the shell, and an outlet port through which the stream exits the shell. A series of vertical and spaced-apart baffles are positioned within the shell to force the stream to flow under and over them as it passes from the inlet to the outlet port. The baffles present a barrier to the microorganisms within the shell causing them to rise and fall within the reactor but to move horizontally at a very slow rate. Treatment detention times of one day or less are possible.

  17. Catalytic reactor

    DOE Patents [OSTI]

    Aaron, Timothy Mark (East Amherst, NY); Shah, Minish Mahendra (East Amherst, NY); Jibb, Richard John (Amherst, NY)

    2009-03-10T23:59:59.000Z

    A catalytic reactor is provided with one or more reaction zones each formed of set(s) of reaction tubes containing a catalyst to promote chemical reaction within a feed stream. The reaction tubes are of helical configuration and are arranged in a substantially coaxial relationship to form a coil-like structure. Heat exchangers and steam generators can be formed by similar tube arrangements. In such manner, the reaction zone(s) and hence, the reactor is compact and the pressure drop through components is minimized. The resultant compact form has improved heat transfer characteristics and is far easier to thermally insulate than prior art compact reactor designs. Various chemical reactions are contemplated within such coil-like structures such that as steam methane reforming followed by water-gas shift. The coil-like structures can be housed within annular chambers of a cylindrical housing that also provide flow paths for various heat exchange fluids to heat and cool components.

  18. Reactor operation environmental information document

    SciTech Connect (OSTI)

    Wike, L.D.; Specht, W.L.; Mackey, H.E.; Paller, M.H.; Wilde, E.W.; Dicks, A.S.

    1989-12-01T23:59:59.000Z

    The Savannah River Site (SRS) is a large United States Department of Energy installation on the upper Atlantic Coastal Plain of South Carolina. The SRS contains diverse habitats, flora, and fauna. Habitats include upland terrestrial areas, varied wetlands including Carolina Bays, the Savannah River swamp system, and impoundment related and riparian wetlands, and the aquatic habitats of several stream systems, two large cooling reservoirs, and the Savannah River. These diverse habitats support a large variety of plants and animals including many commercially or recreational valuable species and several rare, threatened or endangered species. This volume describes the major habitats and their biota found on the SRS, and discuss the impacts of continued operation of the K, L, and P production reactors.

  19. Neutronic reactor

    DOE Patents [OSTI]

    Wende, Charles W. J. (Augusta, GA); Babcock, Dale F. (Wilmington, DE); Menegus, Robert L. (Wilmington, DE)

    1983-01-01T23:59:59.000Z

    A nuclear reactor includes an active portion with fissionable fuel and neutron moderating material surrounded by neutron reflecting material. A control element in the active portion includes a group of movable rods constructed of neutron-absorbing material. Each rod is movable with respect to the other rods to vary the absorption of neutrons and effect control over neutron flux.

  20. Bayes, Asymptotics, Simulation and the Bootstrap

    E-Print Network [OSTI]

    Fletcher, David

    Bayes, Asymptotics, Simulation and the Bootstrap David Fletcher Department of Mathematics Bootstrapping and Bayesian Methods #12;Bayesian Methods and Asymptotics Bayesian methods Conceptually simple for lognormal cases Insight: studentized bootstrap better than percentile Simulations useful for checking actual

  1. Introduction The bay scallop, Argopecten irradi-

    E-Print Network [OSTI]

    71(3) 17 Introduction The bay scallop, Argopecten irradi- ans amplicostatus, has been present (Garcia-Cubas, 1968). Historical Uses Mollusks were used by the pre-Co- lumbian cultures in Mexico as food

  2. PARTICIPATION IN HIGH ENERGY PHYSICS

    SciTech Connect (OSTI)

    White, Christopher

    2012-12-20T23:59:59.000Z

    This grant funded experimental and theoretical activities in elementary particles physics at the Illinois Institute of Technology (IIT). The experiments in which IIT faculty collaborated included the Daya Bay Reactor Neutrino Experiment, the MINOS experiment, the Double Chooz experiment, and FNAL E871 - HyperCP experiment. Funds were used to support summer salary for faculty, salary for postdocs, and general support for graduate and undergraduate students. Funds were also used for travel expenses related to these projects and general supplies.

  3. Risk Management for Sodium Fast Reactors.

    SciTech Connect (OSTI)

    Denman, Matthew R; Groth, Katrina; Cardoni, Jeffrey N; Wheeler, Timothy A.

    2015-01-01T23:59:59.000Z

    Accident management is an important component to maintaining risk at acceptable levels for all complex systems, such as nuclear power plants. With the introduction of self - correcting, or inherently safe, reactor designs the focus has shifted from management by operators to allowing the syste m's design to manage the accident. While inherently and passively safe designs are laudable, extreme boundary conditions can interfere with the design attributes which facilitate inherent safety , thus resulting in unanticipated and undesirable end states. This report examines an inherently safe and small sodium fast reactor experiencing a beyond design basis seismic event with the intend of exploring two issues : (1) can human intervention either improve or worsen the potential end states and (2) can a Bayes ian Network be constructed to infer the state of the reactor to inform (1). ACKNOWLEDGEMENTS The author s would like to acknowledge the U.S. Department of E nergy's Office of Nuclear Energy for funding this research through Work Package SR - 14SN100303 under the Advanced Reactor Concepts program. The authors also acknowledge the PRA teams at A rgonne N ational L aborator y , O ak R idge N ational L aborator y , and I daho N ational L aborator y for their continue d contributions to the advanced reactor PRA mission area.

  4. Structure of processes in flow reactor and closed reactor: Flow reactor

    E-Print Network [OSTI]

    Greifswald, Ernst-Moritz-Arndt-Universität

    Structure of processes in flow reactor and closed reactor: Flow reactor Closed reactor Active Zone -- chemical quasi- equilibria, similarity principles and macroscopic kinetics", in: Lectures on Plasma Physics

  5. IMPACTS OF CLIMATE CHANGE ON SAN FRANCISCO BAY AREA

    E-Print Network [OSTI]

    IMPACTS OF CLIMATE CHANGE ON SAN FRANCISCO BAY AREA RESIDENTIAL ELECTRICITY CONSUMPTION anthropogenic climate change on residential electricity consumption for the nine San Francisco Bay Area counties with different meant temperatures on households' electricity consumption. The estimation uses a comprehensive

  6. Development of Parameterized Surge Response Functions for Coastal Bays

    E-Print Network [OSTI]

    Katyal, Rajat

    2011-02-22T23:59:59.000Z

    ). The surge inside bays tends to be different from that at the open coast due to local geometric factors like shape, center of gravity, and characteristic size of the bay. To predict accurately the surge levels inside the bay, scaling laws are developed based...

  7. Hybrid adsorptive membrane reactor

    DOE Patents [OSTI]

    Tsotsis, Theodore T. (Huntington Beach, CA); Sahimi, Muhammad (Altadena, CA); Fayyaz-Najafi, Babak (Richmond, CA); Harale, Aadesh (Los Angeles, CA); Park, Byoung-Gi (Yeosu, KR); Liu, Paul K. T. (Lafayette Hill, PA)

    2011-03-01T23:59:59.000Z

    A hybrid adsorbent-membrane reactor in which the chemical reaction, membrane separation, and product adsorption are coupled. Also disclosed are a dual-reactor apparatus and a process using the reactor or the apparatus.

  8. Nuclear reactor engineering

    SciTech Connect (OSTI)

    Glasstone, S.; Sesonske, A.

    1982-07-01T23:59:59.000Z

    A book is reviewed which emphasizes topics directly related to the light water reactor power plant and the fast reactor power system. Current real-world problems are addressed throughout the text, and a chapter on safety includes much of the postThree Mile Island impact on operating systems. Topics covered include Doppler broadening, neutron resonances, multigroup diffusion theory, reactor kinetics, reactor control, energy removal, nonfuel materials, reactor fuel, radiation protection, environmental effects, and reactor safety.

  9. Sedimentary parameters of upper Barataria Bay, Louisiana

    E-Print Network [OSTI]

    Siegert, Rudolf B

    1961-01-01T23:59:59.000Z

    SEDIMENTARY PARAMETERS OF UPPER BARATARIA BAY, LOUISIANA A Thesis Rudolf Bernhardt Siegert Submitted to the Graduate School of the Agricultural snd Mechanical College of Texas in partial fulfillment of the reGulremente for the d. agree... of MASTER OF SCIENCE August 1961 Ma)or Sub)ect GeologP SEDYIKNTARY PARAI'ZTEHS OF DT'PBR BARATARIA BAY, LOUISIANA A Thesis By Rudolf Bernhardt Siegert Approved as to style and content by: Chairman of C 'tice Bea of Department or Student Advisor...

  10. A geologic study of Matagorda Bay, Texas

    E-Print Network [OSTI]

    Fagg, David Bruce

    1957-01-01T23:59:59.000Z

    3ecent-I'leistoccnc contact $9 33 Piston Core 33 snoN. inI. - iiecent-Pleistocene contact-- 91 34 I'iston Core 3r3 s&ro&r &ng Hecerrt-Pleistocene contaci. -- 92 35 "Sand Silt Clay 3(atro 1'rian3. "les"- ? -107 Plate 1 Matai, "o& da Hay... 5 The Eunice formation alon the west shore of Matagorda Bay north of LaSalle Bayou----------- 29 6 Eunice sands overlying Eunice clayey silts on the west shore of hiatagorda Bay north of LaSalle Bayou 29 7 Eunice sand overlying Eunice clayey...

  11. Chesapeake Bay anoxia: origin, development, and significance

    SciTech Connect (OSTI)

    Officer, C.B.; Biggs, R.B.; Taft, J.L.; Cronin, L.E.; Tyler, M.A.; Boynton, W.R.

    1984-01-06T23:59:59.000Z

    Anoxia occurs annually in deeper waters of the central portion of the Chesapeake Bay and presently extends from Baltimore to the mouth of the Potomac estuary. This condition, which encompasses some 5 billion cubic meters of water and lasts from May to September, is the result of increased stratification of the water column in early spring, with consequent curtailment of reoxygenation of the bottom waters across the halocline, and benthic decay of organic detritus accumulated from plankton blooms of the previous summer and fall. The Chesapeake Bay anoxia appears to have had significant ecological effects on many marine species, including several of economic importance. 43 references, 7 figures, 1 table.

  12. BayWa Group | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand Jump to:EzfeedflagBiomass Conversions IncBay County, Florida: Energy ResourcesBayWa Group Jump to:

  13. Sonar imaging of bay bottom sediments and anthropogenic impacts in Galveston Bay, Texas

    E-Print Network [OSTI]

    Maddox, Donald Shea

    2007-04-25T23:59:59.000Z

    based on changes in amplitude and stratigraphy. Parallel, layered sediments are seen filling the bay valley and resting atop a sharp contact at which the acoustic signal fades out. Along the flanks of the valley fill the acoustic response revealed...

  14. Fuzzy decision and control, the Bayes context

    E-Print Network [OSTI]

    Painter, John H.

    1993-12-15T23:59:59.000Z

    This paper shows how it is that fuzzy control may be viewed as a particular kind of stochastic (Bayesian) control. With the Bayes approach, fuzzy control may be viewed as an ensembled-average control, where the average is taken over a set...

  15. Carolina bays of the Savannah River Plant

    SciTech Connect (OSTI)

    Schalles, J.F. (Creighton Univ., Omaha, NE (USA)); Sharitz, R.R.; Gibbons, J.W.; Leversee, G.J.; Knox, J.N. (Savannah River Ecology Lab., Aiken, SC (USA))

    1989-01-01T23:59:59.000Z

    Much of the research to date on the Carolina bays of the Savannah River Plant and elsewhere has focused on certain species or on environmental features. Different levels of detail exist for different groups of organisms and reflect the diverse interests of previous investigators. This report summarizes aspects of research to date and presents data from numerous studies. 70 refs., 14 figs., 12 tabs.

  16. Prudhoe Bay Oil Production Optimization: Using Virtual

    E-Print Network [OSTI]

    Mohaghegh, Shahab

    1 Prudhoe Bay Oil Production Optimization: Using Virtual Intelligence Techniques, Stage One: Neural total field oil production by optimizing the gas discharge rates and pressures at the separation handling capacity and subsequent oil production. 10 YEAR AVERAGE AMBIENT 1990-2000 & 2001, 2002 Averages

  17. Bayes Nets Representation: joint distribution and conditional

    E-Print Network [OSTI]

    Mitchell, Tom

    Bayes Nets Representation: joint distribution and conditional independence Yi Zhang 10-701, Machine joint distribution of BNs Infer C. I. from factored joint distributions D-separation (motivation) 2 structure All about the joint distribution of variables ! Conditional independence assumptions are useful

  18. SRS Small Modular Reactors

    SciTech Connect (OSTI)

    None

    2012-04-27T23:59:59.000Z

    The small modular reactor program at the Savannah River Site and the Savannah River National Laboratory.

  19. SRS Small Modular Reactors

    ScienceCinema (OSTI)

    None

    2014-05-21T23:59:59.000Z

    The small modular reactor program at the Savannah River Site and the Savannah River National Laboratory.

  20. Reactor safety method

    DOE Patents [OSTI]

    Vachon, Lawrence J. (Clairton, PA)

    1980-03-11T23:59:59.000Z

    This invention relates to safety means for preventing a gas cooled nuclear reactor from attaining criticality prior to start up in the event the reactor core is immersed in hydrogenous liquid. This is accomplished by coating the inside surface of the reactor coolant channels with a neutral absorbing material that will vaporize at the reactor's operating temperature.

  1. Nuclear reactor

    DOE Patents [OSTI]

    Thomson, Wallace B. (Severna Park, MD)

    2004-03-16T23:59:59.000Z

    A nuclear reactor comprising a cylindrical pressure vessel, an elongated annular core centrally disposed within and spaced from the pressure vessel, and a plurality of ducts disposed longitudinally of the pressure vessel about the periphery thereof, said core comprising an annular active portion, an annular reflector just inside the active portion, and an annular reflector just outside the active a portion, said annular active portion comprising rectangular slab, porous fuel elements radially disposed around the inner reflector and extending the length of the active portion, wedge-shaped, porous moderator elements disposed adjacent one face of each fuel element and extending the length of the fuel element, the fuel and moderator elements being oriented so that the fuel elements face each other and the moderator elements do likewise, adjacent moderator elements being spaced to provide air inlet channels, and adjacent fuel elements being spaced to provide air outlet channels which communicate with the interior of the peripheral ducts, and means for introducing air into the air inlet channels which passes through the porous moderator elements and porous fuel elements to the outlet channel.

  2. Atmospheric Pressure Reactor System | EMSL

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Atmospheric Pressure Reactor System Atmospheric Pressure Reactor System The atmospheric pressure reactor system is designed for testing the efficiency of various catalysts for the...

  3. Mercury bioaccumulation in Lavaca Bay, Texas

    E-Print Network [OSTI]

    Palmer, Sally Jo

    1992-01-01T23:59:59.000Z

    (waves), and human activities (dredging and shrimping) can potentially release mercury to the overlying water (LINDBERG and HARRISS, 1977; CRANSTON, 1976). The solubility, reactivity, and toxicity of mercury is dependent on its form. Divalent mercury... MERCURY BIOACCUMULATION IN LAVACA BAY, TEXAS A Thesis by SALLY JO PALMER Submitted to the Office of Graduate Studies of Texas ABM University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE August 1992 Major...

  4. Petroleum hydrocarbon-degrading bacteria in the Galveston Bay system

    E-Print Network [OSTI]

    Schropp, Steven James

    1979-01-01T23:59:59.000Z

    of Department) (Membge' ) I, (Member) December, 1979 ABSTRACT Petroleum Hydrocarbon-Degrading Bacteria in the Galveston Bay System {December 1979) Steven James Schropp: B. S. , Texas A&M University Co-Chairmen of Advisory Committee: Dr. John R. Schwarz... about the distribution and abundance of petroleum hydrocarbon-degrad- ing bacteria in the Galveston Bay system. Several parts of the Galveston Bay system were sampled during this study. Petroleum input to the study area ranged from relatively small...

  5. Wind-wave measurements in a shallow estuary: Trinity Bay, Texas

    E-Print Network [OSTI]

    Dupuis, Keith Wade

    2009-05-15T23:59:59.000Z

    Acoustic current meter data collected in the shallow ( 3m depth) Trinity Bay, (TB a sub-bay in Galveston Bay), TX, estuary were used to characterize locally generated windwaves. Significant wave heights, periods, and directions were estimated from...

  6. Appendix B. Selected Web Pages Related to MHB 1. NARRAGANSETT BAY PORTS DATA: (CONDUCTIVITY, SALINITY,

    E-Print Network [OSTI]

    Chen, Changsheng

    Power Plant Canal Station Power Plant Mystic Power Plant http://www.pirg.org/masspirg/enviro of Narragansett Bay fish and fisheries, a survey of sediment pollution in Narragansett Bay, a study of Bay

  7. arcachon bay france: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Bay Area Environmental Sciences and Ecology Websites Summary: Soulejule Stevens Creek TotalMercury(ppmwetweight) Mercury Concentrations in Channel Catfish 12;0.00 0.50...

  8. Chesapeake Bay, Drilling for Oil or Gas Prohibited (Virginia)

    Broader source: Energy.gov [DOE]

    Drilling for oil or gas in the waters or within 500 hundred feet from the shoreline of the Chesapeake Bay or any of its tributaries is prohibited.

  9. Humboldt Bay Initiative: Adaptive Management in a Changing World

    E-Print Network [OSTI]

    Schlosser, Susan

    2009-01-01T23:59:59.000Z

    annual maintenance dredging (2007-2011). NMFS, Southwestdevelopment, diking, and dredging. The Bay and itsor is directly removed by dredging. Watersheds adjacent to

  10. Control of hardwood regeneration in restored carolina bay depression wetlands.

    SciTech Connect (OSTI)

    Moser, Lee, J.; Barton, Christopher, D.; Blake, John, I.

    2012-06-01T23:59:59.000Z

    Carolina bays are depression wetlands located in the coastal plain region of the eastern United States. Disturbance of this wetland type has been widespread, and many sites contain one or more drainage ditches. Restoration of bays is of interest because they are important habitats for rare flora and fauna. Previous bay restoration projects have identified flood-tolerant woody competitors in the seedbank and re-sprouting as impediments to the establishment of desired herbaceous wetland vegetation communities. We restored 3 bays on the Savannah River Site, South Carolina, by plugging drainage ditches, harvesting residual pine/hardwood stands within the bays, and monitoring the vegetative response of the seedbank to the hydrologic change. We applied a foliar herbicide on one-half of each bay to control red maple (Acerrubrum), sweetgum (Liquidambar styraciflua), and water oak (Quercus nigra) sprouting, and we tested its effectiveness across a hydrologic gradient in each bay. Hardwood regeneration was partially controlled by flooding in bays that exhibited long growing season hydroperiods. The findings also indicated that herbicide application was an effective means for managing hardwood regeneration and re-sprouting in areas where hydrologic control was ineffective. Herbicide use had no effect on species richness in the emerging vegetation community. In late-season drawdown periods, or in bays where hydroperiods are short, more than one herbicide application may be necessary.

  11. Modeling nitrogen cycling in forested watersheds of Chesapeake Bay

    SciTech Connect (OSTI)

    Hunsaker, C.T.; Garten, C.T.; Mulholland, P.J.

    1995-03-01T23:59:59.000Z

    The Chesapeake Bay Agreement calls for a 40% reduction of controllable phosphorus and nitrogen to the tidal Bay by the year 2000. To accomplish this goal the Chesapeake Bay Program needs accurate estimates of nutrient loadings, including atmospheric deposition, from various land uses. The literature was reviewed on forest nitrogen pools and fluxes, and nitrogen data from research catchments in the Chesapeake Basin were identified. The structure of a nitrogen module for forests is recommended for the Chesapeake Bay Watershed Model along with the possible functional forms for fluxes.

  12. Mercury-Contaminated Hydraulic Mining Debris in San Francisco Bay

    E-Print Network [OSTI]

    Bouse, Robin M; Fuller, Christopher C; Luoma, Sam; Hornberger, Michelle I; Jaffe, Bruce E; Smith, Richard E

    2010-01-01T23:59:59.000Z

    Contaminated Hydraulic Mining Debris in San Francisco BayAbstract The hydraulic gold-mining process used during thecreated by hydraulic gold mining in the Sierra Nevada,

  13. astrophyllite bay complex: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    to N qubits. Finally, we show that quantum state estimates derived via the principle of maximum entropy are fundamentally different from those obtained via the quantum Bayes...

  14. activator bay k8644: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    to N qubits. Finally, we show that quantum state estimates derived via the principle of maximum entropy are fundamentally different from those obtained via the quantum Bayes...

  15. Reactor Sharing Program

    SciTech Connect (OSTI)

    Vernetson, W.G.

    1993-01-01T23:59:59.000Z

    Progress achieved at the University of Florida Training Reactor (UFTR) facility through the US Department of Energy's University Reactor Sharing Program is reported for the period of 1991--1992.

  16. Undergraduate reactor control experiment

    SciTech Connect (OSTI)

    Edwards, R.M.; Power, M.A.; Bryan, M. (Pennsylvania State Univ., University Park (United States))

    1992-01-01T23:59:59.000Z

    A sequence of reactor and related experiments has been a central element of a senior-level laboratory course at Pennsylvania State University (Penn State) for more than 20 yr. A new experiment has been developed where the students program and operate a computer controller that manipulates the speed of a secondary control rod to regulate TRIGA reactor power. Elementary feedback control theory is introduced to explain the experiment, which emphasizes the nonlinear aspect of reactor control where power level changes are equivalent to a change in control loop gain. Digital control of nuclear reactors has become more visible at Penn State with the replacement of the original analog-based TRIGA reactor control console with a modern computer-based digital control console. Several TRIGA reactor dynamics experiments, which comprise half of the three-credit laboratory course, lead to the control experiment finale: (a) digital simulation, (b) control rod calibration, (c) reactor pulsing, (d) reactivity oscillator, and (e) reactor noise.

  17. Attrition reactor system

    DOE Patents [OSTI]

    Scott, Charles D. (Oak Ridge, TN); Davison, Brian H. (Knoxvile, TN)

    1993-01-01T23:59:59.000Z

    A reactor vessel for reacting a solid particulate with a liquid reactant has a centrifugal pump in circulatory flow communication with the reactor vessel for providing particulate attrition, resulting in additional fresh surface where the reaction can occur.

  18. Attrition reactor system

    DOE Patents [OSTI]

    Scott, C.D.; Davison, B.H.

    1993-09-28T23:59:59.000Z

    A reactor vessel for reacting a solid particulate with a liquid reactant has a centrifugal pump in circulatory flow communication with the reactor vessel for providing particulate attrition, resulting in additional fresh surface where the reaction can occur. 2 figures.

  19. Effects and impacts of vessel activity on the Kittlitz's Murrelet (Brachyramphus brevirostris) in Glacier Bay, Alaska

    E-Print Network [OSTI]

    Washington at Seattle, University of

    ) in Glacier Bay, Alaska Alison M. Agness A thesis submitted in partial fulfillment of the requirements (Brachyramphus brevirostris) in Glacier Bay, Alaska.....35 Summary

  20. Targeting Net Zero Energy at Marine Corps Base Kaneohe Bay, Hawaii...

    Broader source: Energy.gov (indexed) [DOE]

    Targeting Net Zero Energy at Marine Corps Base Kaneohe Bay, Hawaii: Assessment and Recommendations Targeting Net Zero Energy at Marine Corps Base Kaneohe Bay, Hawaii: Assessment...

  1. Advanced Test Reactor Tour

    SciTech Connect (OSTI)

    Miley, Don

    2011-01-01T23:59:59.000Z

    The Advanced Test Reactor at Idaho National Laboratory is the foremost nuclear materials test reactor in the world. This virtual tour describes the reactor, how experiments are conducted, and how spent nuclear fuel is handled and stored. For more information about INL research, visit http://www.facebook.com/idahonationallaboratory.

  2. High solids fermentation reactor

    DOE Patents [OSTI]

    Wyman, Charles E.; Grohmann, Karel; Himmel, Michael E.; Richard, Christopher J.

    1993-03-02T23:59:59.000Z

    A fermentation reactor and method for fermentation of materials having greater than about 10% solids. The reactor includes a rotatable shaft along the central axis, the shaft including rods extending outwardly to mix the materials. The reactor and method are useful for anaerobic digestion of municipal solid wastes to produce methane, for production of commodity chemicals from organic materials, and for microbial fermentation processes.

  3. High solids fermentation reactor

    DOE Patents [OSTI]

    Wyman, Charles E. (Lakewood, CO); Grohmann, Karel (Littleton, CO); Himmel, Michael E. (Littleton, CO); Richard, Christopher J. (Lakewood, CO)

    1993-01-01T23:59:59.000Z

    A fermentation reactor and method for fermentation of materials having greater than about 10% solids. The reactor includes a rotatable shaft along the central axis, the shaft including rods extending outwardly to mix the materials. The reactor and method are useful for anaerobic digestion of municipal solid wastes to produce methane, for production of commodity chemicals from organic materials, and for microbial fermentation processes.

  4. Improved vortex reactor system

    DOE Patents [OSTI]

    Diebold, James P. (Lakewood, CO); Scahill, John W. (Evergreen, CO)

    1995-01-01T23:59:59.000Z

    An improved vortex reactor system for affecting fast pyrolysis of biomass and Refuse Derived Fuel (RDF) feed materials comprising: a vortex reactor having its axis vertically disposed in relation to a jet of a horizontally disposed steam ejector that impels feed materials from a feeder and solids from a recycle loop along with a motive gas into a top part of said reactor.

  5. Advanced Test Reactor Tour

    ScienceCinema (OSTI)

    Miley, Don

    2013-05-28T23:59:59.000Z

    The Advanced Test Reactor at Idaho National Laboratory is the foremost nuclear materials test reactor in the world. This virtual tour describes the reactor, how experiments are conducted, and how spent nuclear fuel is handled and stored. For more information about INL research, visit http://www.facebook.com/idahonationallaboratory.

  6. Neutron behavior, reactor control, and reactor heat transfer. Volume four

    SciTech Connect (OSTI)

    Not Available

    1986-01-01T23:59:59.000Z

    Volume four covers neutron behavior (neutron absorption, how big are nuclei, neutron slowing down, neutron losses, the self-sustaining reactor), reactor control (what is controlled in a reactor, controlling neutron population, is it easy to control a reactor, range of reactor control, what happens when the fuel burns up, controlling a PWR, controlling a BWR, inherent safety of reactors), and reactor heat transfer (heat generation in a nuclear reactor, how is heat removed from a reactor core, heat transfer rate, heat transfer properties of the reactor coolant).

  7. Analysis of Empirical MAP and Empirical Partially Bayes: Can They be Alternatives to Variational Bayes?

    E-Print Network [OSTI]

    Sugiyama, Masashi

    Bayes? Shinichi Nakajima Masashi Sugiyama Nikon Corporation Tokyo Institute of Technology Abstract Bayesian scenario, where the hyperpa- rameters are also estimated from observation, are trivial and useless, although the global solutions of empirical PB and empirical MAP are useless, the local solutions behave

  8. Reactor vessel support system

    DOE Patents [OSTI]

    Golden, Martin P. (Trafford, PA); Holley, John C. (McKeesport, PA)

    1982-01-01T23:59:59.000Z

    A reactor vessel support system includes a support ring at the reactor top supported through a box ring on a ledge of the reactor containment. The box ring includes an annular space in the center of its cross-section to reduce heat flow and is keyed to the support ledge to transmit seismic forces from the reactor vessel to the containment structure. A coolant channel is provided at the outside circumference of the support ring to supply coolant gas through the keyways to channels between the reactor vessel and support ledge into the containment space.

  9. San Francisco Bay Map Collection / Neal Harlow (collector)

    E-Print Network [OSTI]

    Handy, Todd C.

    San Francisco Bay Map Collection / Neal Harlow (collector) Last revised October 2011 University / Physical Description o Collector's Biographical Sketch o Scope and Content o Notes Catalogue entry (UBC Library catalogue) #12;Collection Description San Francisco Bay Map Collection / Neal Harlow (collector

  10. Observations of remote and local forcing in Galveston Bay, Texas 

    E-Print Network [OSTI]

    Guannel, Gregory

    2001-01-01T23:59:59.000Z

    Lcvcl Subtidal Variability. Water Level: Contour Plots, . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Water Level: E/W and N/S Wind Stress. Water Level: SP and SN Wind Stress. . . . . . . . . . . . , . . . . . . . Water Level...: Conclusions. Response of Galveston Bay to Forcing: Water Surface Setup Subtidal Variability. Water Surlace Setup: Contour Plots Water Surl ace Setup: SP and SN Wind Stress. . . . . . . . . Water Surface Setup: Conclusions Response of Galveston Bay...

  11. MFR PAPER 1074 Effects of Prudhoe Bay Crude Oil on

    E-Print Network [OSTI]

    MFR PAPER 1074 Effects of Prudhoe Bay Crude Oil on Molting Tanner Crabs, Chionoecetes bairdi JOHN F bairdi , from Alaska walers were exposed 10 Prudhoe Bay crude oil in sIalic bioassays ill Ih e laboralory. Crabs in bOlh slages were similarly susceplible 10 crude oil; Ihe eSlimaled 48-hour TLIIl (Illedian

  12. Reactor water cleanup system

    DOE Patents [OSTI]

    Gluntz, D.M.; Taft, W.E.

    1994-12-20T23:59:59.000Z

    A reactor water cleanup system includes a reactor pressure vessel containing a reactor core submerged in reactor water. First and second parallel cleanup trains are provided for extracting portions of the reactor water from the pressure vessel, cleaning the extracted water, and returning the cleaned water to the pressure vessel. Each of the cleanup trains includes a heat exchanger for cooling the reactor water, and a cleaner for cleaning the cooled reactor water. A return line is disposed between the cleaner and the pressure vessel for channeling the cleaned water thereto in a first mode of operation. A portion of the cooled water is bypassed around the cleaner during a second mode of operation and returned through the pressure vessel for shutdown cooling. 1 figure.

  13. Spinning fluids reactor

    SciTech Connect (OSTI)

    Miller, Jan D; Hupka, Jan; Aranowski, Robert

    2012-11-20T23:59:59.000Z

    A spinning fluids reactor, includes a reactor body (24) having a circular cross-section and a fluid contactor screen (26) within the reactor body (24). The fluid contactor screen (26) having a plurality of apertures and a circular cross-section concentric with the reactor body (24) for a length thus forming an inner volume (28) bound by the fluid contactor screen (26) and an outer volume (30) bound by the reactor body (24) and the fluid contactor screen (26). A primary inlet (20) can be operatively connected to the reactor body (24) and can be configured to produce flow-through first spinning flow of a first fluid within the inner volume (28). A secondary inlet (22) can similarly be operatively connected to the reactor body (24) and can be configured to produce a second flow of a second fluid within the outer volume (30) which is optionally spinning.

  14. Determining Reactor Neutrino Flux

    E-Print Network [OSTI]

    Jun Cao

    2012-03-08T23:59:59.000Z

    Flux is an important source of uncertainties for a reactor neutrino experiment. It is determined from thermal power measurements, reactor core simulation, and knowledge of neutrino spectra of fuel isotopes. Past reactor neutrino experiments have determined the flux to (2-3)% precision. Precision measurements of mixing angle $\\theta_{13}$ by reactor neutrino experiments in the coming years will use near-far detector configurations. Most uncertainties from reactor will be canceled out. Understanding of the correlation of uncertainties is required for $\\theta_{13}$ experiments. Precise determination of reactor neutrino flux will also improve the sensitivity of the non-proliferation monitoring and future reactor experiments. We will discuss the flux calculation and recent progresses.

  15. Glacier Bay Inc | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand Jump to: navigation, search OpenEI Reference LibraryAdd toWell2008) |GigaCrete Inc JumpGillardGinerBay

  16. Clean Cities: Tampa Bay Clean Cities coalition

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office511041clothAdvanced Materials Advanced. C o w l i t z CPlasma0 12DenverNorthernSouthTampa Bay Clean Cities

  17. Tuscola Bay Wind | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand Jump to:Ezfeedflag JumpID-fTri Global Energy LLC Place: Dallas, Texas2022Wind Farm Jump to:Tuscola Bay

  18. Massachusetts Bay Transportation Authority | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnual SiteofEvaluatingGroup |JilinLu an Group JumpNewMassachusetts Bay Transportation Authority Jump

  19. Chesapeake Bay Test Site | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnualProperty EditCalifornia:PowerCER.png El CER es unaChelmsford,Volcanic NationalValleyBay Test

  20. Bay Solar Power Design | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnual Siteof EnergyInnovation in Carbon CaptureAtriaPower SystemsRhode Island:BatteryBatticBay

  1. China Energy Databook -- User Guide and Documentation, Version 7.0

    E-Print Network [OSTI]

    Fridley, Ed., David

    2008-01-01T23:59:59.000Z

    Total Hydro Steam [1] The Daya Bay nuclear power plant inTotal Hydro Steam [1] The Daya Bay nuclear power plant inPower Plants under Construction Qinshan Zhejiang Ling'ao Fossil Plants under Consturction Shang'an Steam

  2. Improved vortex reactor system

    DOE Patents [OSTI]

    Diebold, J.P.; Scahill, J.W.

    1995-05-09T23:59:59.000Z

    An improved vortex reactor system is described for affecting fast pyrolysis of biomass and Refuse Derived Fuel (RDF) feed materials comprising: a vortex reactor having its axis vertically disposed in relation to a jet of a horizontally disposed steam ejector that impels feed materials from a feeder and solids from a recycle loop along with a motive gas into a top part of said reactor. 12 figs.

  3. Tokamak reactor first wall

    DOE Patents [OSTI]

    Creedon, R.L.; Levine, H.E.; Wong, C.; Battaglia, J.

    1984-11-20T23:59:59.000Z

    This invention relates to an improved first wall construction for a tokamak fusion reactor vessel, or other vessels subjected to similar pressure and thermal stresses.

  4. Pressurized fluidized bed reactor

    DOE Patents [OSTI]

    Isaksson, Juhani (Karhula, FI)

    1996-01-01T23:59:59.000Z

    A pressurized fluid bed reactor power plant includes a fluidized bed reactor contained within a pressure vessel with a pressurized gas volume between the reactor and the vessel. A first conduit supplies primary gas from the gas volume to the reactor, passing outside the pressure vessel and then returning through the pressure vessel to the reactor, and pressurized gas is supplied from a compressor through a second conduit to the gas volume. A third conduit, comprising a hot gas discharge, carries gases from the reactor, through a filter, and ultimately to a turbine. During normal operation of the plant, pressurized gas is withdrawn from the gas volume through the first conduit and introduced into the reactor at a substantially continuously controlled rate as the primary gas to the reactor. In response to an operational disturbance of the plant, the flow of gas in the first, second, and third conduits is terminated, and thereafter the pressure in the gas volume and in the reactor is substantially simultaneously reduced by opening pressure relief valves in the first and third conduits, and optionally by passing air directly from the second conduit to the turbine.

  5. Pressurized fluidized bed reactor

    DOE Patents [OSTI]

    Isaksson, J.

    1996-03-19T23:59:59.000Z

    A pressurized fluid bed reactor power plant includes a fluidized bed reactor contained within a pressure vessel with a pressurized gas volume between the reactor and the vessel. A first conduit supplies primary gas from the gas volume to the reactor, passing outside the pressure vessel and then returning through the pressure vessel to the reactor, and pressurized gas is supplied from a compressor through a second conduit to the gas volume. A third conduit, comprising a hot gas discharge, carries gases from the reactor, through a filter, and ultimately to a turbine. During normal operation of the plant, pressurized gas is withdrawn from the gas volume through the first conduit and introduced into the reactor at a substantially continuously controlled rate as the primary gas to the reactor. In response to an operational disturbance of the plant, the flow of gas in the first, second, and third conduits is terminated, and thereafter the pressure in the gas volume and in the reactor is substantially simultaneously reduced by opening pressure relief valves in the first and third conduits, and optionally by passing air directly from the second conduit to the turbine. 1 fig.

  6. Subenvironments of deposition in San Antonio Bay, Texas

    E-Print Network [OSTI]

    Hall, Gary Lynn

    1973-01-01T23:59:59.000Z

    with the Muddy Sandstone at Bell Creek Field, Montana. CONCLUSIONS. REFERENCES CITED VITA 107 108 108 ill 117 117 121 122 123 124 124 126 128 128 128 132 135 138 142 LIST OF TABLES TABLE 1 Mineralogical Composition of Montmori lloni tie.... The usual source of high salinity water enters from the Gulf of Mexico through Pass Cavallo and mixes with Matagorda Bay waters. This water passes westward through Espiritu Santo Bay into San Antonio Bay, where it appears to turn and move northwestward...

  7. Brookhaven Graphite Research Reactor Workshop

    Broader source: Energy.gov [DOE]

    The Brookhaven Graphite Research Reactor (BGRR) was the first reactor built in the U.S. for peacetime atomic research following World War II.  Construction began in 1947 and the reactor started...

  8. REACTOR OPERATIONS AND CONTROL

    E-Print Network [OSTI]

    Pázsit, Imre

    REACTOR OPERATIONS AND CONTROL KEYWORDS: core calculations, neural networks, control rod elevation of a control rod, or a group of control rods, is an important parameter from the viewpoint of reactor control DETERMINATION OF PWR CONTROL ROD POSITION BY CORE PHYSICS AND NEURAL NETWORK METHODS NINOS S. GARIS* and IMRE

  9. Reed Reactor Facility. Final report

    SciTech Connect (OSTI)

    Frantz, S.G.

    1994-12-31T23:59:59.000Z

    This report discusses the operation and maintenance of the Reed Reactor Facility. The Reed reactor is mostly used for education and train purposes.

  10. Reactor & Nuclear Systems Publications | ORNL

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Science Home | Science & Discovery | Nuclear Science | Publications and Reports | Reactor and Nuclear Systems Publications SHARE Reactor and Nuclear Systems Publications The...

  11. admiralty bay king: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    influence May Point, a distance of 2O,miles, the crabs are sought at Ewing Neck, West Creek, East Creek 123 Nonparametric Bayes Applications to Biostatistics David B. Dunson...

  12. BayesDB : querying the probable implications of tabular data

    E-Print Network [OSTI]

    Baxter, Jay

    2014-01-01T23:59:59.000Z

    BayesDB, a Bayesian database table, lets users query the probable implications of their tabular data as easily as an SQL database lets them query the data itself. Using the built-in Bayesian Query Language (BQL), users ...

  13. atlantic lisbon bay: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    guests of the Hudsons Bay Company, and on the second of the Royal Canadian Mounted Police. In addition the Royal Canadian Air Force kindly flew us to several areas well away...

  14. WIND EFFECTS ON CHEMICAL SPILL IN ST ANDREW BAY SYSTEM

    E-Print Network [OSTI]

    Chu, Peter C.

    WIND EFFECTS ON CHEMICAL SPILL IN ST ANDREW BAY SYSTEM PETER C. CHU, PATRICE PAULY Naval Can easily reach 20 m/s and more during hurricane events #12;Water Quality Management and Analysis

  15. Seagrass habitat utilization by fishes in Christmas Bay, Texas 

    E-Print Network [OSTI]

    Crotwell, Patricia Lynn

    1997-01-01T23:59:59.000Z

    Fishes in Christmas Bay, TX were collected during April 1994 through March 1995 to: 1) assess temporal variability in their density, biomass, and diversity; 2) define the relationship between variability in fish population parameters...

  16. Seagrass habitat utilization by fishes in Christmas Bay, Texas

    E-Print Network [OSTI]

    Crotwell, Patricia Lynn

    1997-01-01T23:59:59.000Z

    Fishes in Christmas Bay, TX were collected during April 1994 through March 1995 to: 1) assess temporal variability in their density, biomass, and diversity; 2) define the relationship between variability in fish population parameters...

  17. Radionuclide distributions and sorption behavior in the Susquehanna--Chesapeake Bay System

    SciTech Connect (OSTI)

    Olsen, C.R.; Larsen, I.L.; Lowry, P.D.; McLean, R.I.; Domotor, S.L.

    1989-01-01T23:59:59.000Z

    Radionuclides released into the Susquehanna--Chesapeake System from the Three Mile Island, Peach Bottom, and Calvert Cliffs nuclear power plants are partitioned among dissolved, particulate, and biological phases and may thus exist in a number of physical and chemical forms. In this project, we have measured the dissolved and particulate distributions of fallout /sup 137/Cs; reactor-released /sup 137/Cs, /sup 134/Cs, /sup 65/Zn, /sup 60/Co, and /sup 58/Co; and naturally occurring /sup 7/Be and /sup 210/Pb in the lower Susquehanna River and Upper Chesapeake Bay. In addition, we chemically leached suspended particles and bottom sediments in the laboratory to determine radionuclide partitioning among different particulate-sorbing phases to complement the site-specific field data. This information has been used to document the important geochemical processes that affect the transport, sorption, distribution, and fate of reactor-released radionuclides (and by analogy, other trace contaminants) in this river-estuarine system. Knowledge of the mechanisms, kinetic factors, and processes that affect radionuclide distributions is crucial for predicting their biological availability, toxicity, chemical behavior, physical transport, and accumulation in aquatic systems. The results from this project provide the information necessary for developing accurate radionuclide-transport and biological-uptake models. 76 refs., 12 figs.

  18. Investigation of tidal power, cobscook bay, maine. Reconnaissance report

    SciTech Connect (OSTI)

    Not Available

    1980-08-01T23:59:59.000Z

    Cobscook Bay is located in Eastern, Maine, near Eastport. The bay experiences an average tide range of 18 feet and has a surface area of about 40 square miles at high tide. Single pool, single effect projects have been analyzed. Two projects, one having an installed capacity of 165 Mw and the other, 195 Mw were found to be economically feasible when forecasted, fuel escalation costs were considered.

  19. Fish assemblages on coral reefs in Guanaja, Bay Islands, Honduras

    E-Print Network [OSTI]

    Mahendran, Christopher Kandiah

    1999-01-01T23:59:59.000Z

    FISH ASSEMBLAGES ON CORAL REEFS IN GUANAJA, BAY ISLANDS, HONDURAS A Thesis by CHRISTOPHER KANDIAH MAHENDRAN Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree... of MASTER OF SCIENCE August 1999 Major Subject: Wildlife and Fisheries Sciences FISH ASSEMBLAGES ON CORAL REEFS IN GUANAJA, BAY ISLANDS, HONDURAS A Thesis by CHRISTOPHER KANDIAH MAHENDRAN Submitted to Texas A&M University in partial fulfillment...

  20. Petroleum hydrocarbon-degrading bacteria in the Galveston Bay system 

    E-Print Network [OSTI]

    Schropp, Steven James

    1979-01-01T23:59:59.000Z

    PETROLEUM HYDRQCARBOiV-DEGRADING BACTERIA IN THE GALVESTON BAY SYSTEM A Thesis by STEVEN JAMES SCHROPP Submitted to the Graduate College of Texas ASM University in partial fulfillment of the requirement for the degree of MASTER OF SCIFNCE... December 1979 Major Subject: Biology PETROLEUM HYDROCARBON-DEGRADING BACTERIA IN THE GALVESTON BAY SYSTEM A Thesis by STEVEN JAMES SCHROPP Approved as to style and content by: (Co-Chairman of Committee) '( ~CA. ( -Chairman of Committee) (Head...

  1. Nuclear reactor control column

    SciTech Connect (OSTI)

    Bachovchin, D.M.

    1982-08-10T23:59:59.000Z

    The nuclear reactor control column comprises a column disposed within the nuclear reactor core having a variable cross-section hollow channel and containing balls whose vertical location is determined by the flow of the reactor coolant through the column. The control column is divided into three basic sections wherein each of the sections has a different cross-sectional area. The uppermost section of the control column has the greatest crosssectional area, the intermediate section of the control column has the smallest cross-sectional area, and the lowermost section of the control column has the intermediate cross-sectional area. In this manner, the area of the uppermost section can be established such that when the reactor coolant is flowing under normal conditions therethrough, the absorber balls will be lifted and suspended in a fluidized bed manner in the upper section. However, when the reactor coolant flow falls below a predetermined value, the absorber balls will fall through the intermediate section and into the lowermost section, thereby reducing the reactivity of the reactor core and shutting down the reactor.

  2. Reactor Safety Research Programs

    SciTech Connect (OSTI)

    Edler, S. K.

    1981-07-01T23:59:59.000Z

    This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from January 1 through March 31, 1981, for the Division of Reactor Safety Research within the U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipeto- pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-ofcoolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation, severe fuel damage, and postaccident coolability tests for the ESSOR reactor Super Sara Test Program, Ispra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL). These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  3. Nuclear reactor control column

    DOE Patents [OSTI]

    Bachovchin, Dennis M. (Plum Borough, PA)

    1982-01-01T23:59:59.000Z

    The nuclear reactor control column comprises a column disposed within the nuclear reactor core having a variable cross-section hollow channel and containing balls whose vertical location is determined by the flow of the reactor coolant through the column. The control column is divided into three basic sections wherein each of the sections has a different cross-sectional area. The uppermost section of the control column has the greatest cross-sectional area, the intermediate section of the control column has the smallest cross-sectional area, and the lowermost section of the control column has the intermediate cross-sectional area. In this manner, the area of the uppermost section can be established such that when the reactor coolant is flowing under normal conditions therethrough, the absorber balls will be lifted and suspended in a fluidized bed manner in the upper section. However, when the reactor coolant flow falls below a predetermined value, the absorber balls will fall through the intermediate section and into the lowermost section, thereby reducing the reactivity of the reactor core and shutting down the reactor.

  4. Fast Breeder Reactor studies

    SciTech Connect (OSTI)

    Till, C.E.; Chang, Y.I.; Kittel, J.H.; Fauske, H.K.; Lineberry, M.J.; Stevenson, M.G.; Amundson, P.I.; Dance, K.D.

    1980-07-01T23:59:59.000Z

    This report is a compilation of Fast Breeder Reactor (FBR) resource documents prepared to provide the technical basis for the US contribution to the International Nuclear Fuel Cycle Evaluation. The eight separate parts deal with the alternative fast breeder reactor fuel cycles in terms of energy demand, resource base, technical potential and current status, safety, proliferation resistance, deployment, and nuclear safeguards. An Annex compares the cost of decommissioning light-water and fast breeder reactors. Separate abstracts are included for each of the parts.

  5. Spherical torus fusion reactor

    DOE Patents [OSTI]

    Martin Peng, Y.K.M.

    1985-10-03T23:59:59.000Z

    The object of this invention is to provide a compact torus fusion reactor with dramatic simplification of plasma confinement design. Another object of this invention is to provide a compact torus fusion reactor with low magnetic field and small aspect ratio stable plasma confinement. In accordance with the principles of this invention there is provided a compact toroidal-type plasma confinement fusion reactor in which only the indispensable components inboard of a tokamak type of plasma confinement region, mainly a current conducting medium which carries electrical current for producing a toroidal magnet confinement field about the toroidal plasma region, are retained.

  6. Nuclear reactor reflector

    DOE Patents [OSTI]

    Hopkins, Ronald J. (Pensacola, FL); Land, John T. (Pensacola, FL); Misvel, Michael C. (Pensacola, FL)

    1994-01-01T23:59:59.000Z

    A nuclear reactor reflector is disclosed that comprises a stack of reflector blocks with vertical water flow passages to cool the reflector. The interface between blocks is opposite support points for reactor fuel rods. Water flows between the reflector and the reactor barrel from passages in a bottom block. The top block contains a flange to limit this flow and the flange has a slot to receive an alignment pin that is welded to the barrel. The pin is held in the slot by two removable shims. Alignment bars extend the length of the stack in slots machined in each block when the stack is assembled.

  7. Nuclear reactor reflector

    DOE Patents [OSTI]

    Hopkins, R.J.; Land, J.T.; Misvel, M.C.

    1994-06-07T23:59:59.000Z

    A nuclear reactor reflector is disclosed that comprises a stack of reflector blocks with vertical water flow passages to cool the reflector. The interface between blocks is opposite support points for reactor fuel rods. Water flows between the reflector and the reactor barrel from passages in a bottom block. The top block contains a flange to limit this flow and the flange has a slot to receive an alignment pin that is welded to the barrel. The pin is held in the slot by two removable shims. Alignment bars extend the length of the stack in slots machined in each block when the stack is assembled. 12 figs.

  8. Microfluidic electrochemical reactors

    DOE Patents [OSTI]

    Nuzzo, Ralph G. (Champaign, IL); Mitrovski, Svetlana M. (Urbana, IL)

    2011-03-22T23:59:59.000Z

    A microfluidic electrochemical reactor includes an electrode and one or more microfluidic channels on the electrode, where the microfluidic channels are covered with a membrane containing a gas permeable polymer. The distance between the electrode and the membrane is less than 500 micrometers. The microfluidic electrochemical reactor can provide for increased reaction rates in electrochemical reactions using a gaseous reactant, as compared to conventional electrochemical cells. Microfluidic electrochemical reactors can be incorporated into devices for applications such as fuel cells, electrochemical analysis, microfluidic actuation, pH gradient formation.

  9. Hypothetical Reactor Accident Study

    E-Print Network [OSTI]

    POPULATIONS; IODINE 131; MELTDOWN; METEOROLOGY; NUCLEAR POWER PLANTS; P CODES; PWR TYPE REACTORS; RADIATION in a Typical BWR and in a typical PWR. Comparison with WASH-1400 by C F . Hřjerup 202 APPENDIX 3. Calculation

  10. P Reactor Grouting

    SciTech Connect (OSTI)

    None

    2010-01-01T23:59:59.000Z

    Filling the P Reactor with grout. This seals the radioactive material and reduces the environmental footprint left from the Cold War. Project sponsored by the Recovery Act at the Savannah River Site.

  11. Nuclear reactor control

    SciTech Connect (OSTI)

    Ingham, R.V.

    1980-01-01T23:59:59.000Z

    A liquid metal cooled fast breeder nuclear reactor has power setback means for use in an emergency. On initiation of a trip-signal a control rod is injected into the core in two stages, firstly, by free fall to effect an immediate power-set back to a safe level and, secondly, by controlled insertion. Total shut-down of the reactor under all emergencies is avoided. 4 claims.

  12. Polymerization reactor control

    SciTech Connect (OSTI)

    Ray, W.H.

    1985-01-01T23:59:59.000Z

    The principal difficulties in achieving good control of polymerization reactors are related to inadequate on-line measurement, a lack of understanding of the dynamics of the process, the highly sensitive and nonlinear behavior of these reactors, and the lack of well-developed techniques for the control of nonlinear processes. Some illustrations of these problems and a discussion of potential techniques for overcoming some of these difficulties is provided.

  13. Molten metal reactors

    DOE Patents [OSTI]

    Bingham, Dennis N; Klingler, Kerry M; Turner, Terry D; Wilding, Bruce M

    2013-11-05T23:59:59.000Z

    A molten metal reactor for converting a carbon material and steam into a gas comprising hydrogen, carbon monoxide, and carbon dioxide is disclosed. The reactor includes an interior crucible having a portion contained within an exterior crucible. The interior crucible includes an inlet and an outlet; the outlet leads to the exterior crucible and may comprise a diffuser. The exterior crucible may contain a molten alkaline metal compound. Contained between the exterior crucible and the interior crucible is at least one baffle.

  14. Reactor- Nuclear Science Center 

    E-Print Network [OSTI]

    Unknown

    2011-08-17T23:59:59.000Z

    A COMPARISON OF NUCLEAR REACTOR CONTROL ROOM DISPLAY PANELS A Thesis by FRANCES RENAE BOWERS Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE May 1988... Major Subject: Industrial Engineering A COMPARISON OF NUCLEAR REACTOR CONTROL ROOM DISPLAY PANELS A Thesis by FRANCES RENAE BOWERS Approved as to style and content by: Rod er . oppa (Cha' of 'ttee) R. Quinn Brackett (Member) rome . Co gleton...

  15. Study of Nuclei and Elementary Particles At Low and Intermediate Energies

    SciTech Connect (OSTI)

    Robert D. McKeown

    2013-02-27T23:59:59.000Z

    The primary activity associated with this DOE grant was the construction, commissioning, operation, and analysis of results of the KamLAND experiment. KamLAND is a large (1kT) liquid scintillator neutrino detector located deep underground in the Kamioka mine in Japan. This effort was a spectacular scientific success, with a major discovery of neutrino oscillations in the â??solarâ?ť sector and the pioneering measurement of geoneutrinos due to radioactive decay within the earth. During the final year of the grant period, effort was devoted to developing the new Daya Bay reactor neutrino experiment in China.

  16. A Precise Calculation of Delayed Coincidence Selection Efficiency and Accidental Coincidence Rate

    E-Print Network [OSTI]

    Jingyi Yu; Zhe Wang; Shaomin Chen

    2014-11-27T23:59:59.000Z

    A model is proposed to address issues on the precise background evaluation due to the complex data structure defined by the delayed coincidence method, which is widely used in reactor electron-antineutrino oscillation experiments. In this model, the effects from the muon veto, uncorrelated random background, coincident signal and background are all studied with the analytical solutions, simplifying the estimation of the systematic uncertainties of signal efficiency and accidental background rate determined by the unstable single rate. The result of calculation is validated numerically with a number of simulation studies and is also applied and validated in the recent Daya Bay hydrogen-capture based oscillation measurement.

  17. Earth Matter Effects in Detection of Supernova Neutrinos

    E-Print Network [OSTI]

    X. -H. Guo; Bing-Lin Young

    2006-05-11T23:59:59.000Z

    We calculated the matter effect, including both the Earth and supernova, on the detection of neutrinos from type II supernovae at the proposed Daya Bay reactor neutrino experiment. It is found that apart from the dependence on the flip probability P_H inside the supernova and the mass hierarchy of neutrinos, the amount of the Earth matter effect depends on the direction of the incoming supernova neutrinos, and reaches the biggest value when the incident angle of neutrinos is around 93^\\circ. In the reaction channel \\bar{\

  18. 42484 secretarys achievement award - 5 x 6 - Building 51

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy China 2015ofDepartment ofCBFO-13-3322(EE)DepartmentVery5Dryers;under9Daya Bay Reactor

  19. 427872_PS3054.indd

    Broader source: Energy.gov (indexed) [DOE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy China 2015ofDepartment ofCBFO-13-3322(EE)DepartmentVery5Dryers;under9Daya Bay Reactor31,

  20. 44

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2UraniumEnergyDepartment ofEnergyDryers;31,000Daya Bay Reactor

  1. 45

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2UraniumEnergyDepartment ofEnergyDryers;31,000Daya Bay Reactor

  2. 46696 Achievement Award BELLA - 5 x 6

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2UraniumEnergyDepartment ofEnergyDryers;31,000Daya Bay Reactor

  3. 46696 Achievement Award EERE - 5 x 6

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2UraniumEnergyDepartment ofEnergyDryers;31,000Daya Bay Reactor

  4. 46696 Achievement Award ISB - 5 x 6

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2UraniumEnergyDepartment ofEnergyDryers;31,000Daya Bay Reactor

  5. 46696 Achievement Award SDU 3&5 - 5 x 6

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2UraniumEnergyDepartment ofEnergyDryers;31,000Daya Bay Reactor

  6. 46696 Achievement Award TDEF - 5 x 6

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2UraniumEnergyDepartment ofEnergyDryers;31,000Daya Bay Reactor

  7. 46696 Excellence award PM- 5 x 6

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2UraniumEnergyDepartment ofEnergyDryers;31,000Daya Bay Reactor

  8. 46696 FPD Award Trollinger- 5 x 6

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2UraniumEnergyDepartment ofEnergyDryers;31,000Daya Bay Reactor

  9. Power Burst Facility (PBF) Reactor Reactor Decommissioning

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's Possible forPortsmouth/Paducah Project Office PressPostdoctoraldecadal7Powder DropperReactor

  10. Reactor Safety Research Programs

    SciTech Connect (OSTI)

    Dotson, CW

    1980-08-01T23:59:59.000Z

    This document summarizes the work performed by Pacific Northwest laboratory from October 1 through December 31, 1979, for the Division of Reactor Safety Research within the Nuclear Regulatory Commission. Evaluation of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibilty of determining structural graphite strength, evaluating the feasibilty of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the remaining integrity of pressurized water reactor steam generator tubes where service-induced degradation has been indicated. Test assemblies and analytical support are being provided for experimental programs at other facilities. These programs include the loss-of-coolant accident simulation tests at the NRU reactor, Chalk River, Canada; the fuel rod deformation and post-accident coolability tests for the ESSOR Test Reactor Program, lspra, Italy; the blowdown and reflood tests in the test facility at Cadarache, France; the instrumented fuel assembly irradiation program at Halden, Norway; and the experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory. These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  11. F Reactor Inspection

    SciTech Connect (OSTI)

    Grindstaff, Keith; Hathaway, Boyd; Wilson, Mike

    2014-10-29T23:59:59.000Z

    Workers from Mission Support Alliance, LLC., removed the welds around the steel door of the F Reactor before stepping inside the reactor to complete its periodic inspection. This is the first time the Department of Energy (DOE) has had the reactor open since 2008. The F Reactor is one of nine reactors along the Columbia River at the Department's Hanford Site in southeastern Washington State, where environmental cleanup has been ongoing since 1989. As part of the Tri-Party Agreement, the Department completes surveillance and maintenance activities of cocooned reactors periodically to evaluate the structural integrity of the safe storage enclosure and to ensure confinement of any remaining hazardous materials. "This entry marks a transition of sorts because the Hanford Long-Term Stewardship Program, for the first time, was responsible for conducting the entry and surveillance and maintenance activities," said Keith Grindstaff, Energy Department Long-Term Stewardship Program Manager. "As the River Corridor cleanup work is completed and transitioned to long-term stewardship, our program will manage any on-going requirements."

  12. F Reactor Inspection

    ScienceCinema (OSTI)

    Grindstaff, Keith; Hathaway, Boyd; Wilson, Mike

    2014-11-24T23:59:59.000Z

    Workers from Mission Support Alliance, LLC., removed the welds around the steel door of the F Reactor before stepping inside the reactor to complete its periodic inspection. This is the first time the Department of Energy (DOE) has had the reactor open since 2008. The F Reactor is one of nine reactors along the Columbia River at the Department's Hanford Site in southeastern Washington State, where environmental cleanup has been ongoing since 1989. As part of the Tri-Party Agreement, the Department completes surveillance and maintenance activities of cocooned reactors periodically to evaluate the structural integrity of the safe storage enclosure and to ensure confinement of any remaining hazardous materials. "This entry marks a transition of sorts because the Hanford Long-Term Stewardship Program, for the first time, was responsible for conducting the entry and surveillance and maintenance activities," said Keith Grindstaff, Energy Department Long-Term Stewardship Program Manager. "As the River Corridor cleanup work is completed and transitioned to long-term stewardship, our program will manage any on-going requirements."

  13. Quantification of sediment bed - water column exchange processes in the South San Francisco Bay estuary

    E-Print Network [OSTI]

    Gladding, Steven Michael

    2011-01-01T23:59:59.000Z

    Hydraulic Mining 1.2.2. Dredging 1.2.3. Contaminants 1.2.4.of the sediment bed of the Bay (see Section Dredging Largescale dredging operations have occurred in the Bay for more

  14. Energy Secretary Steven Chu to Travel to Bay Area to Highlight...

    Energy Savers [EERE]

    Steven Chu to Travel to Bay Area to Highlight State of the Union Address, Commitment to Clean Energy Energy Secretary Steven Chu to Travel to Bay Area to Highlight State of the...

  15. Education Program for Improved Water Quality in Copano Bay Final Report

    E-Print Network [OSTI]

    Berthold, A.; Moench, E.; Wagner, K.; Paschal, J.

    2012-05-17T23:59:59.000Z

    The Copano Bay watershed covers approximately 1.4 million acres encompassing portions of Karnes, Bee, Goliad, Refugio, San Patricio and Aransas counties. Copano Bay and its main tributaries, the Mission and Aransas rivers, were placed on the Texas...

  16. Text classification Naive Bayes NB theory Evaluation of TC Web Search and Text Mining

    E-Print Network [OSTI]

    Gray, Alexander

    Bayes NB theory Evaluation of TC Take-away today Text classification: definition & relevance theory Evaluation of TC Take-away today Text classification: definition & relevance to information: definition & relevance to information retrieval Naive Bayes: simple baseline text classifier Theory

  17. Reactor Safety Planning for Prometheus Project, for Naval Reactors Information

    SciTech Connect (OSTI)

    P. Delmolino

    2005-05-06T23:59:59.000Z

    The purpose of this letter is to submit to Naval Reactors the initial plan for the Prometheus project Reactor Safety work. The Prometheus project is currently developing plans for cold physics experiments and reactor prototype tests. These tests and facilities may require safety analysis and siting support. In addition to the ground facilities, the flight reactor units will require unique analyses to evaluate the risk to the public from normal operations and credible accident conditions. This letter outlines major safety documents that will be submitted with estimated deliverable dates. Included in this planning is the reactor servicing documentation and shipping analysis that will be submitted to Naval Reactors.

  18. Anthropogenic Influence on Recent Bathymetric Change in West-Central San Francisco Bay

    E-Print Network [OSTI]

    Barnard, Patrick; Kvitek, Rikk

    2010-01-01T23:59:59.000Z

    Bay coastal system. Sedimentology, In: Li M, Sherwood C,Publication Book on Shelf Sedimentology. 33 p. Fregoso TA,

  19. Zero Power Reactor simulation | Argonne National Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Zero Power Reactor simulation Share Description Ever wanted to see a nuclear reactor core in action? Here's a detailed simulation of the Zero Power Reactor experiment, run by...

  20. Heavy metal concentration in bay sediments of Japan

    SciTech Connect (OSTI)

    Fukue, Masaharu; Kato, Yoshihisa; Nakamura, Takaaki [Tokai Univ., Shimizu (Japan); Yamasaki, Shoichi [Aoki Marine Ltd., Fukushima, Osaka (Japan)

    1995-12-31T23:59:59.000Z

    Because industry discharge wastes into the sea, marine sediments can be contaminated with various kinds of hazardous and toxic substances. This study discusses how the degree of pollution of heavy metals affects the marine sediments from Osaka Bay and Tokyo Bay. In this study, the concentrations of various metals, such as manganese, iron, aluminum, titanium, vanadium, copper, phosphorus, etc., were measured from sediment samples obtained from different sites in the bays. However, the results had to be corrected because background concentrations for each metal differ with site location and grain size characteristics. The large difference between background and individual concentrations at various soil depths indicates that the surface layers of the seabed are significantly polluted with some species of heavy metal and other elements.

  1. Naval submarine base Kings Bay and Bangor soil evaluations.

    SciTech Connect (OSTI)

    Holcomb, David Joseph; Patteson, Raymond; Wesenberg, Donald L.; Attaway, Stephen W.

    2004-08-01T23:59:59.000Z

    This report provides soil evaluation and characterization testing for the submarine bases at Kings Bay, Georgia, and Bangor, Washington, using triaxial testing at high confining pressures with different moisture contents. In general, the samples from the Bangor and Kings Bay sites appeared to be stronger than a previously used reference soil. Assuming the samples of the material were representative of the material found at the sites, they should be adequate for use in the planned construction. Since soils can vary greatly over even a small site, a soil specification for the construction contractor would be needed to insure that soil variations found at the site would meet or exceed the requirements. A suggested specification for the Bangor and Kings Bay soils was presented based on information gathered from references plus data obtained from this study, which could be used as a basis for design by the construction contractor.

  2. Meta learning of bounds on the Bayes classifier error

    E-Print Network [OSTI]

    Moon, Kevin R; Hero, Alfred O

    2015-01-01T23:59:59.000Z

    Meta learning uses information from base learners (e.g. classifiers or estimators) as well as information about the learning problem to improve upon the performance of a single base learner. For example, the Bayes error rate of a given feature space, if known, can be used to aid in choosing a classifier, as well as in feature selection and model selection for the base classifiers and the meta classifier. Recent work in the field of f-divergence functional estimation has led to the development of simple and rapidly converging estimators that can be used to estimate various bounds on the Bayes error. We estimate multiple bounds on the Bayes error using an estimator that applies meta learning to slowly converging plug-in estimators to obtain the parametric convergence rate. We compare the estimated bounds empirically on simulated data and then estimate the tighter bounds on features extracted from an image patch analysis of sunspot continuum and magnetogram images.

  3. A Transect of Glacier Bay Ocean Currents Measured by Acoustic Doppler Current Profiler (ADCP)

    E-Print Network [OSTI]

    that the tidal flow accelerates over Glacier Bay's shallow entrance sill to speeds of 180 cm/s and then slowsA Transect of Glacier Bay Ocean Currents Measured by Acoustic Doppler Current Profiler (ADCP shipboard acoustic Doppler current profiler (ADCP) transects of ocean current in Glacier Bay and Muir Inlet

  4. REPRODUCTIVE CYCLE OF THE SOFT-SHELL CLAM, MYA ARENARIA, AT SKAGIT BAY, WASHINGTON

    E-Print Network [OSTI]

    'll Skagit Bay in northern Puget Sound. Wash. Spawning occurred from late May to early September in both 1971 the annual reproductive cycle for a soft-shell clam population from Puget Sound, Wash. Skagit Bay-shell clams in Puget Sound. DESCRIPTION OF AREA Skagit Bay, Wash., is located in northern Puget Sound 60 miles

  5. Exploring the Environmental Effects of Shale Gas Development in the Chesapeake Bay Watershed

    E-Print Network [OSTI]

    Exploring the Environmental Effects of Shale Gas Development in the Chesapeake Bay Watershed STAC Committee). 2013. Exploring the environmental effects of shale gas development in the Chesapeake Bay of shale gas development in the Chesapeake Bay Watershed. The purpose of this workshop was to engage

  6. A Baseline Assessment of the Ecological Resources of Jobos Bay, Puerto Rico

    E-Print Network [OSTI]

    A Baseline Assessment of the Ecological Resources of Jobos Bay, Puerto Rico July 2011 Editors David. A Baseline Assessment of the Ecological Resources of Jobos Bay, Puerto Rico. NOAA Technical Memorandum NOS of the Ecological Resources of Jobos Bay, Puerto Rico Prepared by the Coastal and Oceanographic Assessment, Status

  7. Methanation assembly using multiple reactors

    DOE Patents [OSTI]

    Jahnke, Fred C.; Parab, Sanjay C.

    2007-07-24T23:59:59.000Z

    A methanation assembly for use with a water supply and a gas supply containing gas to be methanated in which a reactor assembly has a plurality of methanation reactors each for methanating gas input to the assembly and a gas delivery and cooling assembly adapted to deliver gas from the gas supply to each of said methanation reactors and to combine water from the water supply with the output of each methanation reactor being conveyed to a next methanation reactor and carry the mixture to such next methanation reactor.

  8. A TEN MEGAWATT BOILING HETEROGENEOUS PACKAGE POWER REACTOR. Reactor...

    Office of Scientific and Technical Information (OSTI)

    A reactor and associated power plant designed to produce 1.05 Mwh and 3.535 Mwh of steam for heating purposes are described. The total thermal output of the reactor is 10 Mwh....

  9. CONFIRMATORY SURVEY RESULTS FOR PORTIONS OF THE MATERIALS AND EQUIPMENT FROM UNITS 1 AND 2 AT THE HUMBOLDT BAY POWER PLANT, EUREKA, CALIFORNIA

    SciTech Connect (OSTI)

    W.C. Adams

    2011-04-01T23:59:59.000Z

    The Pacific Gas & Electric Company (PG&E) operated the Humboldt Bay Power Plant (HBPP) Unit 3 nuclear reactor near Eureka, California under Atomic Energy Commission (AEC) provisional license number DPR-7. HBPP Unit 3 achieved initial criticality in February 1963 and began commercial operations in August 1963. Unit 3 was a natural circulation boiling water reactor with a direct-cycle design. This design eliminated the need for heat transfer loops and large containment structures. Also, the pressure suppression containment design permitted below-ground construction. Stainless steel fuel claddings were used from startup until cladding failures resulted in plant system contamination—zircaloy-clad fuel was used exclusively starting in 1965 eliminating cladding-related contamination. A number of spills and gaseous releases were reported during operations resulting in a range of mitigative activities (see ESI 2008 for details).

  10. Reactor for exothermic reactions

    DOE Patents [OSTI]

    Smith, Jr., Lawrence A. (Bellaire, TX); Hearn, Dennis (Houston, TX); Jones, Jr., Edward M. (Friendswood, TX)

    1993-01-01T23:59:59.000Z

    A liquid phase process for oligomerization of C.sub.4 and C.sub.5 isoolefins or the etherification thereof with C.sub.1 to C.sub.6 alcohols wherein the reactants are contacted in a reactor with a fixed bed acid cation exchange resin catalyst at an LHSV of 5 to 20, pressure of 0 to 400 psig and temperature of 120.degree. to 300.degree. F. Wherein the improvement is the operation of the reactor at a pressure to maintain the reaction mixture at its boiling point whereby at least a portion but less than all of the reaction mixture is vaporized. By operating at the boiling point and allowing a portion of the reaction mixture to vaporize, the exothermic heat of reaction is dissipated by the formation of more boil up and the temperature in the reactor is controlled.

  11. Thermionic Reactor Design Studies

    SciTech Connect (OSTI)

    Schock, Alfred

    1994-08-01T23:59:59.000Z

    Paper presented at the 29th IECEC in Monterey, CA in August 1994. The present paper describes some of the author's conceptual designs and their rationale, and the special analytical techniques developed to analyze their (thermionic reactor) performance. The basic designs, first published in 1963, are based on single-cell converters, either double-ended diodes extending over the full height of the reactor core or single-ended diodes extending over half the core height. In that respect they are similar to the thermionic fuel elements employed in the Topaz-2 reactor subsequently developed in the Soviet Union, copies of which were recently imported by the U.S. As in the Topaz-2 case, electrically heated steady-state performance tests of the converters are possible before fueling.

  12. Reactor for exothermic reactions

    DOE Patents [OSTI]

    Smith, L.A. Jr.; Hearn, D.; Jones, E.M. Jr.

    1993-03-02T23:59:59.000Z

    A liquid phase process is described for oligomerization of C[sub 4] and C[sub 5] isoolefins or the etherification thereof with C[sub 1] to C[sub 6] alcohols wherein the reactants are contacted in a reactor with a fixed bed acid cation exchange resin catalyst at an LHSV of 5 to 20, pressure of 0 to 400 psig and temperature of 120 to 300 F. Wherein the improvement is the operation of the reactor at a pressure to maintain the reaction mixture at its boiling point whereby at least a portion but less than all of the reaction mixture is vaporized. By operating at the boiling point and allowing a portion of the reaction mixture to vaporize, the exothermic heat of reaction is dissipated by the formation of more boil up and the temperature in the reactor is controlled.

  13. Nuclear reactor safety device

    DOE Patents [OSTI]

    Hutter, Ernest (Wilmette, IL)

    1986-01-01T23:59:59.000Z

    A safety device is disclosed for use in a nuclear reactor for axially repositioning a control rod with respect to the reactor core in the event of an upward thermal excursion. Such safety device comprises a laminated helical ribbon configured as a tube-like helical coil having contiguous helical turns with slidably abutting edges. The helical coil is disclosed as a portion of a drive member connected axially to the control rod. The laminated ribbon is formed of outer and inner laminae. The material of the outer lamina has a greater thermal coefficient of expansion than the material of the inner lamina. In the event of an upward thermal excursion, the laminated helical coil curls inwardly to a smaller diameter. Such inward curling causes the total length of the helical coil to increase by a substantial increment, so that the control rod is axially repositioned by a corresponding amount to reduce the power output of the reactor.

  14. Fusion reactor control

    SciTech Connect (OSTI)

    Plummer, D.A.

    1995-12-31T23:59:59.000Z

    The plasma kinetic temperature and density changes, each per an injected fuel density rate increment, control the energy supplied by a thermonuclear fusion reactor in a power production cycle. This could include simultaneously coupled control objectives for plasma current, horizontal and vertical position, shape and burn control. The minimum number of measurements required, use of indirect (not plasma parameters) system measurements, and distributed control procedures for burn control are to be verifiable in a time dependent systems code. The International Thermonuclear Experimental Reactor (ITER) has the need to feedback control both the fusion output power and the driven plasma current, while avoiding damage to diverter plates. The system engineering of fusion reactors must be performed to assure their development expeditiously and effectively by considering reliability, availability, maintainability, environmental impact, health and safety, and cost.

  15. Heat dissipating nuclear reactor

    DOE Patents [OSTI]

    Hunsbedt, Anstein (Los Gatos, CA); Lazarus, Jonathan D. (Sunnyvale, CA)

    1987-01-01T23:59:59.000Z

    Disclosed is a nuclear reactor containment adapted to retain and cool core debris in the unlikely event of a core meltdown and subsequent breach in the reactor vessel. The reactor vessel is seated in a cavity which has a thick metal sidewall that is integral with a thick metal basemat at the bottom of the cavity. The basemat extends beyond the perimeter of the cavity sidewall. Underneath the basemat is a porous bed with water pipes and steam pipes running into it. Water is introduced into the bed and converted into steam which is vented to the atmosphere. A plurality of metal pilings in the form of H-beams extends from the metal base plate downwardly and outwardly into the earth.

  16. Heat dissipating nuclear reactor

    DOE Patents [OSTI]

    Hunsbedt, A.; Lazarus, J.D.

    1985-11-21T23:59:59.000Z

    Disclosed is a nuclear reactor containment adapted to retain and cool core debris in the unlikely event of a core meltdown and subsequent breach in the reactor vessel. The reactor vessel is seated in a cavity which has a thick metal sidewall that is integral with a thick metal basemat at the bottom of the cavity. The basemat extends beyond the perimeter of the cavity sidewall. Underneath the basemat is a porous bed with water pipes and steam pipes running into it. Water is introduced into the bed and converted into steam which is vented to the atmosphere. A plurality of metal pilings in the form of H-beams extend from the metal base plate downwardly and outwardly into the earth.

  17. Fast quench reactor method

    DOE Patents [OSTI]

    Detering, Brent A. (Idaho Falls, ID); Donaldson, Alan D. (Idaho Falls, ID); Fincke, James R. (Idaho Falls, ID); Kong, Peter C. (Idaho Falls, ID); Berry, Ray A. (Idaho Falls, ID)

    1999-01-01T23:59:59.000Z

    A fast quench reaction includes a reactor chamber having a high temperature heating means such as a plasma torch at its inlet and a means of rapidly expanding a reactant stream, such as a restrictive convergent-divergent nozzle at its outlet end. Metal halide reactants are injected into the reactor chamber. Reducing gas is added at different stages in the process to form a desired end product and prevent back reactions. The resulting heated gaseous stream is then rapidly cooled by expansion of the gaseous stream.

  18. Fast quench reactor method

    DOE Patents [OSTI]

    Detering, B.A.; Donaldson, A.D.; Fincke, J.R.; Kong, P.C.; Berry, R.A.

    1999-08-10T23:59:59.000Z

    A fast quench reaction includes a reactor chamber having a high temperature heating means such as a plasma torch at its inlet and a means of rapidly expanding a reactant stream, such as a restrictive convergent-divergent nozzle at its outlet end. Metal halide reactants are injected into the reactor chamber. Reducing gas is added at different stages in the process to form a desired end product and prevent back reactions. The resulting heated gaseous stream is then rapidly cooled by expansion of the gaseous stream. 8 figs.

  19. Fusion reactor pumped laser

    DOE Patents [OSTI]

    Jassby, Daniel L. (Princeton, NJ)

    1988-01-01T23:59:59.000Z

    A nuclear pumped laser capable of producing long pulses of very high power laser radiation is provided. A toroidal fusion reactor provides energetic neutrons which are slowed down by a moderator. The moderated neutrons are converted to energetic particles capable of pumping a lasing medium. The lasing medium is housed in an annular cell surrounding the reactor. The cell includes an annular reflecting mirror at the bottom and an annular output window at the top. A neutron reflector is disposed around the cell to reflect escaping neutrons back into the cell. The laser radiation from the annular window is focused onto a beam compactor which generates a single coherent output laser beam.

  20. Perspectives on reactor safety

    SciTech Connect (OSTI)

    Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States)

    1994-03-01T23:59:59.000Z

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor, safety concepts. The course consists of five modules: (1) historical perspective; (2) accident sequences; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

  1. THE MATERIALS OF FAST BREEDER REACTORS

    E-Print Network [OSTI]

    Olander, Donald R.

    2013-01-01T23:59:59.000Z

    times larger in a fast reactor than in a thermal reactor,structural metals in a fast reactor will be subject to farof fuel ele- ments in fast reactors which are roughly one

  2. Innovative design of uranium startup fast reactors

    E-Print Network [OSTI]

    Fei, Tingzhou

    2012-01-01T23:59:59.000Z

    Sodium Fast Reactors are one of the three candidates of GEN-IV fast reactors. Fast reactors play an important role in saving uranium resources and reducing nuclear wastes. Conventional fast reactors rely on transuranic ...

  3. Reactor operation environmental information document

    SciTech Connect (OSTI)

    Haselow, J.S.; Price, V.; Stephenson, D.E.; Bledsoe, H.W.; Looney, B.B.

    1989-12-01T23:59:59.000Z

    The Savannah River Site (SRS) produces nuclear materials, primarily plutonium and tritium, to meet the requirements of the Department of Defense. These products have been formed in nuclear reactors that were built during 1950--1955 at the SRS. K, L, and P reactors are three of five reactors that have been used in the past to produce the nuclear materials. All three of these reactors discontinued operation in 1988. Currently, intense efforts are being extended to prepare these three reactors for restart in a manner that protects human health and the environment. To document that restarting the reactors will have minimal impacts to human health and the environment, a three-volume Reactor Operations Environmental Impact Document has been prepared. The document focuses on the impacts of restarting the K, L, and P reactors on both the SRS and surrounding areas. This volume discusses the geology, seismology, and subsurface hydrology. 195 refs., 101 figs., 16 tabs.

  4. Power calibrations for TRIGA reactors

    SciTech Connect (OSTI)

    Whittemore, W.L.; Razvi, J.; Shoptaugh, J.R. Jr. [General Atomics, San Diego, CA (United States)

    1988-07-01T23:59:59.000Z

    The purpose of this paper is to establish a framework for the calorimetric power calibration of TRIGA reactors so that reliable results can be obtained with a precision better than {+-} 5%. Careful application of the same procedures has produced power calibration results that have been reproducible to {+-} 1.5%. The procedures are equally applicable to the Mark I, Mark II and Mark III reactors as well as to reactors having much larger reactor tanks and to TRIGA reactors capable of forced cooling up to 3 MW in some cases and 15 MW in another case. In the case of forced cooled TRIGA reactors, the calorimetric power calibration is applicable in the natural convection mode for these reactors using exactly the same procedures as are discussed below for the smaller TRIGA reactors (< 2 MW)

  5. Abundance and distribution of the western Gulf stone crab (Menippe adina) in Galveston Bay, Texas

    E-Print Network [OSTI]

    Boslet, Jane Murray

    1989-01-01T23:59:59.000Z

    studies h d t d ~ Md t h h ' d t' t from M. mercenaria (Bert 1986, Williams and Felder 1986) Due to this new systematic status, historical data based on M. mercenaria, most of which come from Florida, may not be applicable to characterize the natural..., and Melager Coves, Mid West Bay, Jones Bay, West Bay east of Anderson Ways, and south of the I ? 45 Causeway. Non-reef/channel sampling sites in West Bay included randomly selected areas representative of the remainder of the bay. Harsh/mudflat areas...

  6. Short-term variability of suspended sediment and phytoplankton in Tampa Bay, Florida: Observations from a coastal oceanographic tower

    E-Print Network [OSTI]

    Meyers, Steven D.

    dynamics in Tampa Bay with data collected between 8 December 2004 and 17 January 2005 from optical of reliable and cost-effective means for high-frequency sampling (e.g., Roegner et al., 2002). As a result, with a dredged channel (>10 m) extending from the mouth of the bay to the upper bay. Tampa Bay is often divided

  7. Sensitivity analysis of three-dimensional salinity simulations in North San Francisco Bay using the unstructured-grid SUNTANS model

    E-Print Network [OSTI]

    Fringer, Oliver B.

    and the confluence of the Sacramento­San Joaquin Rivers and comprises San Pablo Bay, Suisun Bay and Central Bay and San Joaquin rivers, while high inflows result in enhanced salinity stratification and gravitationalSensitivity analysis of three-dimensional salinity simulations in North San Francisco Bay using

  8. Reactor operation safety information document

    SciTech Connect (OSTI)

    Not Available

    1990-01-01T23:59:59.000Z

    The report contains a reactor facility description which includes K, P, and L reactor sites, structures, operating systems, engineered safety systems, support systems, and process and effluent monitoring systems; an accident analysis section which includes cooling system anomalies, radioactive materials releases, and anticipated transients without scram; a summary of onsite doses from design basis accidents; severe accident analysis (reactor core disruption); a description of operating contractor organization and emergency planning; and a summary of reactor safety evolution. (MB)

  9. Reed Reactor Facility Annual Report

    SciTech Connect (OSTI)

    Frantz, Stephen G.

    2000-09-01T23:59:59.000Z

    This is the report of the operations, experiments, modifications, and other aspects of the Reed Reactor Facility for the year.

  10. Covered Product Category: Industrial Luminaires (High/Low Bay)

    Broader source: Energy.gov [DOE]

    The Federal Energy Management Program (FEMP) provides acquisition guidance and Federal efficiency requirements for Industrial Luminaires (High/Low Bay). Federal laws and requirements mandate that agencies meet these efficiency requirements in all procurement and acquisition actions that are not specifically exempted by law.

  11. Bayes Estimation for the Marshall-Olkin Bivariate Weibull Distribution

    E-Print Network [OSTI]

    Kundu, Debasis

    Bayes Estimation for the Marshall-Olkin Bivariate Weibull Distribution Debasis Kundu1 & Arjun K. Gupta2 Abstract In this paper, we consider the Bayesian analysis of the Marshall-Olkin bivariate Weibull. This is a generalization of the Marshall-Olkin bivariate exponential dis- tribution. It is well known that the maximum

  12. UMCESUNIVERSITY OF MARYLAND CENTER for ENVIRONMENTAL SCIENCE CHESAPEAKE BAY

    E-Print Network [OSTI]

    Boynton, Walter R.

    : Utility of ConMon Data for Assessing Shallow Water Habitats 2-1 Community Metabolism: Use of ConMon Data on ConMon data collected along a eutrophication gradient from the Maryland Coastal Bays (A) Bishopville versus daily DO range (max DO ­ min DO) based on ConMon data collected along a eutrophication gradient

  13. EA-1995: Trestle Bay Ecosystem Restoration Project, Clatsop County, Oregon

    Broader source: Energy.gov [DOE]

    The U.S. Army Corps of Engineers is preparing, with DOE’s Bonneville Power Administration (BPA) as a cooperating agency, an EA that evaluates the potential environmental impacts of a proposal to improve estuary habitat in Trestle Bay. BPA’s proposed action is to partially fund the proposal.

  14. Manganese Oxidation In A Natural Marine Environment- San Antonio Bay

    E-Print Network [OSTI]

    Neyin, Rosemary Ogheneochuko

    2013-04-12T23:59:59.000Z

    ................................................................................................................. 24 REFERENCES .................................................................................................................. 25 vii LIST OF FIGURES Page Figure 1 Study Area in ANWR, San Antonio Bay, Texas... by microorganisms, colloidal matter, mineral surfaces, or all three; and (3) is superoxide a significant proximal oxidant? 4 STUDY AREA The area chosen for this study was located in the Aransas National Wildlife Refuge (ANWR) in San Antonio...

  15. AT GUANTANAMO BAY: A HYBRID WIND-DIESEL SYSTEM

    E-Print Network [OSTI]

    Massachusetts at Amherst, University of

    WIND POWER AT GUANTANAMO BAY: A HYBRID WIND-DIESEL SYSTEM FOR THE US NAVY AT GUANTANAMO NAVAL BASE Laboratory and are actively developing what will be the world's largest wind-diesel hybrid electric plant. The pending installation of four 950-kW wind turbines to supplement the 22.8 MW diesel electricity plant

  16. Preliminary Investigation of Tracer Gas Reaeration Method for Shallow Bays

    E-Print Network [OSTI]

    Baker, Sarah H.; Holley, Edward R.

    apparently the first tests to be performed using the tracer gas technique in bays. As a result, the emphasis was on the development of techniques rather than on obtaining data. It appears that workable techniques have been developed, but they now need...

  17. Teaching Bayes' Rule: A Data Oriented Jim Albert 1

    E-Print Network [OSTI]

    Albert, James H.

    Teaching Bayes' Rule: A Data Oriented Approach Jim Albert 1 Bowling Green State University March 1997 1 Address for correspondence: Department of Mathematics and Statistics, Bowling Green State University, Bowling Green, OH 43403, USA. #12; Abstract There is a current emphasis on making

  18. Nitrogen Dynamics in Sandy Freshwater Sediments (Saginaw Bay, Lake Huron)

    E-Print Network [OSTI]

    of added 15NH4 + from lake water passing over dark sediment cores. Sediment-water fluxes of nitrogen at the sediment- water interface is derived from ammonium pro- duced from organic matter mineralization in surface ABSTRACT. Sediment-water nitrogen fluxes and transformations were examined at two sites in Sagi- naw Bay

  19. Nuclear Reactors and Technology

    SciTech Connect (OSTI)

    Cason, D.L.; Hicks, S.C. [eds.

    1992-01-01T23:59:59.000Z

    This publication Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency`s Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on the Energy Science and Technology Database and Nuclear Science Abstracts (NSA) database. Current information, added daily to the Energy Science and Technology Database, is available to DOE and its contractors through the DOE Integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user`s needs.

  20. NETL - Chemical Looping Reactor

    ScienceCinema (OSTI)

    None

    2014-06-26T23:59:59.000Z

    NETL's Chemical Looping Reactor unit is a high-temperature integrated CLC process with extensive instrumentation to improve computational simulations. A non-reacting test unit is also used to study solids flow at ambient temperature. The CLR unit circulates approximately 1,000 pounds per hour at temperatures around 1,800 degrees Fahrenheit.

  1. Thermal Reactor Safety

    SciTech Connect (OSTI)

    Not Available

    1980-06-01T23:59:59.000Z

    Information is presented concerning fire risk and protection; transient thermal-hydraulic analysis and experiments; class 9 accidents and containment; diagnostics and in-service inspection; risk and cost comparison of alternative electric energy sources; fuel behavior and experiments on core cooling in LOCAs; reactor event reporting analysis; equipment qualification; post facts analysis of the TMI-2 accident; and computational methods.

  2. Nuclear reactor building

    DOE Patents [OSTI]

    Gou, Perng-Fei (Saratoga, CA); Townsend, Harold E. (Campbell, CA); Barbanti, Giancarlo (Sirtori, IT)

    1994-01-01T23:59:59.000Z

    A reactor building for enclosing a nuclear reactor includes a containment vessel having a wetwell disposed therein. The wetwell includes inner and outer walls, a floor, and a roof defining a wetwell pool and a suppression chamber disposed thereabove. The wetwell and containment vessel define a drywell surrounding the reactor. A plurality of vents are disposed in the wetwell pool in flow communication with the drywell for channeling into the wetwell pool steam released in the drywell from the reactor during a LOCA for example, for condensing the steam. A shell is disposed inside the wetwell and extends into the wetwell pool to define a dry gap devoid of wetwell water and disposed in flow communication with the suppression chamber. In a preferred embodiment, the wetwell roof is in the form of a slab disposed on spaced apart support beams which define therebetween an auxiliary chamber. The dry gap, and additionally the auxiliary chamber, provide increased volume to the suppression chamber for improving pressure margin.

  3. Nuclear reactor building

    DOE Patents [OSTI]

    Gou, P.F.; Townsend, H.E.; Barbanti, G.

    1994-04-05T23:59:59.000Z

    A reactor building for enclosing a nuclear reactor includes a containment vessel having a wetwell disposed therein. The wetwell includes inner and outer walls, a floor, and a roof defining a wetwell pool and a suppression chamber disposed there above. The wetwell and containment vessel define a drywell surrounding the reactor. A plurality of vents are disposed in the wetwell pool in flow communication with the drywell for channeling into the wetwell pool steam released in the drywell from the reactor during a LOCA for example, for condensing the steam. A shell is disposed inside the wetwell and extends into the wetwell pool to define a dry gap devoid of wetwell water and disposed in flow communication with the suppression chamber. In a preferred embodiment, the wetwell roof is in the form of a slab disposed on spaced apart support beams which define there between an auxiliary chamber. The dry gap, and additionally the auxiliary chamber, provide increased volume to the suppression chamber for improving pressure margin. 4 figures.

  4. Fossil fuel furnace reactor

    DOE Patents [OSTI]

    Parkinson, William J. (Los Alamos, NM)

    1987-01-01T23:59:59.000Z

    A fossil fuel furnace reactor is provided for simulating a continuous processing plant with a batch reactor. An internal reaction vessel contains a batch of shale oil, with the vessel having a relatively thin wall thickness for a heat transfer rate effective to simulate a process temperature history in the selected continuous processing plant. A heater jacket is disposed about the reactor vessel and defines a number of independent controllable temperature zones axially spaced along the reaction vessel. Each temperature zone can be energized to simulate a time-temperature history of process material through the continuous plant. A pressure vessel contains both the heater jacket and the reaction vessel at an operating pressure functionally selected to simulate the continuous processing plant. The process yield from the oil shale may be used as feedback information to software simulating operation of the continuous plant to provide operating parameters, i.e., temperature profiles, ambient atmosphere, operating pressure, material feed rates, etc., for simulation in the batch reactor.

  5. NETL - Chemical Looping Reactor

    SciTech Connect (OSTI)

    None

    2013-07-24T23:59:59.000Z

    NETL's Chemical Looping Reactor unit is a high-temperature integrated CLC process with extensive instrumentation to improve computational simulations. A non-reacting test unit is also used to study solids flow at ambient temperature. The CLR unit circulates approximately 1,000 pounds per hour at temperatures around 1,800 degrees Fahrenheit.

  6. Reactor Monitoring with Neutrinos

    E-Print Network [OSTI]

    M. Cribier

    2007-04-06T23:59:59.000Z

    The fundamental knowledge on neutrinos acquired in the recent years open the possibility of applied neutrino physics. Among it the automatic and non intrusive monitoring of nuclear reactor by its antineutrino signal could be very valuable to IAEA in charge of the control of nuclear power plants. Several efforts worldwide have already started.

  7. The Carolina Bay Restoration Project - Final Report 2000-2006.

    SciTech Connect (OSTI)

    Barton, Christopher

    2007-12-15T23:59:59.000Z

    A Wetlands Mitigation Bank was established at SRS in 1997 as a compensatory alternative for unavoidable wetland losses. Prior to restoration activities, 16 sites included in the project were surveyed for the SRS Site Use system to serve as a protective covenant. Pre-restoration monitoring ended in Fall 2000, and post restoration monitoring began in the Winter/Spring of 2001. The total interior harvest in the 16 bays after harvesting the trees was 19.6 ha. The margins in the opencanopy, pine savanna margin treatments were thinned. Margins containing areas with immature forested stands (bay 5184 and portions of bay 5011) were thinned using a mechanical shredder in November 2001. Over 126 hectares were included in the study areas (interior + margin). Planting of two tree species and the transplanting of wetland grass species was successful. From field surveys, it was estimated that approximately 2700 Nyssa sylvatica and 1900 Taxodium distichum seedlings were planted in the eight forested bays resulting in an average planting density of ? 490 stems ha-1. One hundred seedlings of each species per bay (where available) were marked to evaluate survivability and growth. Wetland grass species were transplanted from donor sites on SRS to plots that ranged in size from 100 – 300 m2, depending on wetland size. On 0.75 and 0.6 meter centers, respectively, 2198 plugs of Panicum hemitomon and 3021 plugs Leersia hexandra were transplanted. New shoots originating from the stumps were treated with a foliar herbicide (Garlon® 4) during the summer of 2001 using backpack sprayers. Preliminary information from 2000-2004 regarding the hydrologic, vegetation and faunal response to restoration is presented in this status report.

  8. Reactor vessel support system. [LMFBR

    DOE Patents [OSTI]

    Golden, M.P.; Holley, J.C.

    1980-05-09T23:59:59.000Z

    A reactor vessel support system includes a support ring at the reactor top supported through a box ring on a ledge of the reactor containment. The box ring includes an annular space in the center of its cross-section to reduce heat flow and is keyed to the support ledge to transmit seismic forces from the reactor vessel to the containment structure. A coolant channel is provided at the outside circumference of the support ring to supply coolant gas through the keyways to channels between the reactor vessel and support ledge into the containment space.

  9. DRAFT RICHMOND BAY CAMPUS LRDP | August 2013 The Richmond Bay Campus is a partnership between the University of Cali-

    E-Print Network [OSTI]

    Lee, Jason R.

    National Laboratory to create a state-of-the-art, inspirational, and sustainable place to produce world, the environment, health, and the global economy. In the near term, research at the Richmond Bay Campus will focus on cleaner methods to produce biofuels; an advanced understanding of the genomics of plants, microbes

  10. DRAFT RICHMOND BAY CAMPUS LRDP | November 2013 The Richmond Bay Campus is a partnership between the University of Cali-

    E-Print Network [OSTI]

    Lee, Jason R.

    is focused on the devel- opment of solutions for 21st century challenges in the areas of energy for innova- tion in the City of Richmond South Shoreline Area, serving as a catalyst for the development -- are directly supportive of the City's goals for the South Shoreline Area. The Richmond Bay Campus will serve

  11. Nuclear reactor construction with bottom supported reactor vessel

    DOE Patents [OSTI]

    Sharbaugh, John E. (Bullskin Township, Fayette County, PA)

    1987-01-01T23:59:59.000Z

    An improved liquid metal nuclear reactor construction has a reactor core and a generally cylindrical reactor vessel for holding a large pool of low pressure liquid metal coolant and housing the core within the pool. The reactor vessel has an open top end, a closed flat bottom end wall and a continuous cylindrical closed side wall interconnecting the top end and bottom end wall. The reactor also has a generally cylindrical concrete containment structure surrounding the reactor vessel and being formed by a cylindrical side wall spaced outwardly from the reactor vessel side wall and a flat base mat spaced below the reactor vessel bottom end wall. A central support pedestal is anchored to the containment structure base mat and extends upwardly therefrom to the reactor vessel and upwardly therefrom to the reactor core so as to support the bottom end wall of the reactor vessel and the lower end of the reactor core in spaced apart relationship above the containment structure base mat. Also, an annular reinforced support structure is disposed in the reactor vessel on the bottom end wall thereof and extends about the lower end of the core so as to support the periphery thereof. In addition, an annular support ring having a plurality of inward radially extending linear members is disposed between the containment structure base mat and the bottom end of the reactor vessel wall and is connected to and supports the reactor vessel at its bottom end on the containment structure base mat so as to allow the reactor vessel to expand radially but substantially prevent any lateral motions that might be imposed by the occurrence of a seismic event. The reactor construction also includes a bed of insulating material in sand-like granular form, preferably being high density magnesium oxide particles, disposed between the containment structure base mat and the bottom end wall of the reactor vessel and uniformly supporting the reactor vessel at its bottom end wall on the containment structure base mat so as to insulate the reactor vessel bottom end wall from the containment structure base mat and allow the reactor vessel bottom end wall to freely expand as it heats up while providing continuous support thereof. Further, a deck is supported upon the side wall of the containment structure above the top open end of the reactor vessel, and a plurality of serially connected extendible and retractable annular bellows extend between the deck and the top open end of the reactor vessel and flexibly and sealably interconnect the reactor vessel at its top end to the deck. An annular guide ring is disposed on the containment structure and extends between its side wall and the top open end of the reactor vessel for providing lateral support of the reactor vessel top open end by limiting imposition of lateral loads on the annular bellows by the occurrence of a lateral seismic event.

  12. SODAR DATA FROM OYSTER BAY AT WINYAH BAY NATIONAL ESTUARINE RESEARCH RESERVE

    SciTech Connect (OSTI)

    Nichols, R.; Kohn, J.; Rigas, N.; Boessneck, E.; Kress, E.; Gayes, P.

    2013-04-29T23:59:59.000Z

    The SecondWind Triton® is a SODAR (SOnic Detection And Ranging) sonic wind profiler (Triton® sodar) system capable of profiling the wind characteristics up to 200m above the instrument. SODAR systems transmit acoustic chirps into the atmosphere and measure the backscattered signal returned to the device. The primary source of acoustic scattering is variations in air temperature, which cause changes in the refractive index of sound. By measuring the Doppler?shifted frequency of these returned signals, the Triton® can calculate the wind’s speed and direction for the volume of air above the instrument, measured at ten fixed heights, known as station heights. The Triton® is specifically designed for the purpose of wind energy resource assessment as it can remotely capture wind data at heights above ground where wind turbine rotors operate. The measurements made include horizontal wind speed and direction, vertical wind speed, and turbulence. Other integrated sensors provide time and location via GPS, barometric pressure, humidity, and the tilt of the instrument. The study area is located east of Georgetown, South Carolina in North Inlet ? Winyah Bay National Estuarine Research Reserve. The monitoring period for data in this report begins 5/14/2009 9:30:00 AM EST and ends 8/2/2010 11:40:00 AM EST.

  13. Nuclear reactor safety device

    DOE Patents [OSTI]

    Hutter, E.

    1983-08-15T23:59:59.000Z

    A safety device is described for use in a nuclear reactor for axially repositioning a control rod with respect to the reactor core in the event of a thermal excursion. It comprises a laminated strip helically configured to form a tube, said tube being in operative relation to said control rod. The laminated strip is formed of at least two materials having different thermal coefficients of expansion, and is helically configured such that the material forming the outer lamina of the tube has a greater thermal coefficient of expansion than the material forming the inner lamina of said tube. In the event of a thermal excursion the laminated strip will tend to curl inwardly so that said tube will increase in length, whereby as said tube increases in length it exerts a force on said control rod to axially reposition said control rod with respect to said core.

  14. Fusion reactor pumped laser

    DOE Patents [OSTI]

    Jassby, D.L.

    1987-09-04T23:59:59.000Z

    A nuclear pumped laser capable of producing long pulses of very high power laser radiation is provided. A toroidal fusion reactor provides energetic neutrons which are slowed down by a moderator. The moderated neutrons are converted to energetic particles capable of pumping a lasing medium. The lasing medium is housed in an annular cell surrounding the reactor. The cell includes an annular reflecting mirror at the bottom and an annular output window at the top. A neutron reflector is disposed around the cell to reflect escaping neutrons back into the cell. The laser radiation from the annular window is focused onto a beam compactor which generates a single coherent output laser beam. 10 figs.

  15. Spherical torus fusion reactor

    DOE Patents [OSTI]

    Peng, Yueng-Kay M. (Oak Ridge, TN)

    1989-01-01T23:59:59.000Z

    A fusion reactor is provided having a near spherical-shaped plasma with a modest central opening through which straight segments of toroidal field coils extend that carry electrical current for generating a toroidal magnet plasma confinement fields. By retaining only the indispensable components inboard of the plasma torus, principally the cooled toroidal field conductors and in some cases a vacuum containment vessel wall, the fusion reactor features an exceptionally small aspect ratio (typically about 1.5), a naturally elongated plasma cross section without extensive field shaping, requires low strength magnetic containment fields, small size and high beta. These features combine to produce a spherical torus plasma in a unique physics regime which permits compact fusion at low field and modest cost.

  16. Nuclear reactor sealing system

    DOE Patents [OSTI]

    McEdwards, James A. (Calabasas, CA)

    1983-01-01T23:59:59.000Z

    A liquid metal-cooled nuclear reactor sealing system. The nuclear reactor includes a vessel sealed at its upper end by a closure head. The closure head comprises at least two components, one of which is rotatable; and the two components define an annulus therebetween. The sealing system includes at least a first and second inflatable seal disposed in series in an upper portion of the annulus. The system further includes a dip seal extending into a body of insulation located adjacent a bottom portion of the closure head. The dip seal comprises a trough formed by a lower portion of one of the components, and a seal blade pendently supported from the other component and extending downwardly into the trough. A body of liquid metal is contained in the trough which submerges a portion of the seal blade. The seal blade is provided with at least one aperture located above the body of liquid metal for providing fluid communication between the annulus intermediate the dip seal and the inflatable seals, and a body of cover gas located inside the vessel. There also is provided means for introducing a purge gas into the annulus intermediate the inflatable seals and the seal blade. The purge gas is introduced in an amount sufficient to substantially reduce diffusion of radioactive cover gas or sodium vapor up to the inflatable seals. The purge gas mixes with the cover gas in the reactor vessel where it can be withdrawn from the vessel for treatment and recycle to the vessel.

  17. Nuclear reactor engineering: Reactor systems engineering. Fourth edition, Volume Two

    SciTech Connect (OSTI)

    Glasstone, S.; Sesonske, A.

    1994-12-31T23:59:59.000Z

    This new edition of this classic reference combines broad yet in-depth coverage of nuclear engineering principles with practical descriptions of their application in the design and operation of nuclear power plants. Extensively updated, the fourth edition includes new materials on reactor safety and risk analysis, regulation, fuel management, waste management and operational aspects of nuclear power. This volume contains the following: the systems concept, design decisions, and information tools; energy transport; reactor fuel management and energy cost considerations; environmental effects of nuclear power and waste management; nuclear reactor safety and regulation; power reactor systems; plant operations; and advanced plants and the future.

  18. Modular Pebble Bed Reactor High Temperature Gas Reactor

    E-Print Network [OSTI]

    Built · Site Assembled · On--line Refueling · Modules added to meet demand. · No Reprocessing · High Experiments · Non-Proliferation · Safeguards · Waste Disposal · Reactor Research/ Demonstration Facility

  19. Thermionic Reactor Design Studies

    SciTech Connect (OSTI)

    Schock, Alfred

    1994-06-01T23:59:59.000Z

    During the 1960's and early 70's the author performed extensive design studies, analyses, and tests aimed at thermionic reactor concepts that differed significantly from those pursued by other investigators. Those studies, like most others under Atomic Energy Commission (AEC and DOE) and the National Aeronautics and Space Administration (NASA) sponsorship, were terminated in the early 1970's. Some of this work was previously published, but much of it was never made available in the open literature. U.S. interest in thermionic reactors resumed in the early 80's, and was greatly intensified by reports about Soviet ground and flight tests in the late 80's. This recent interest resulted in renewed U.S. thermionic reactor development programs, primarily under Department of Defense (DOD) and Department of Energy (DOE) sponsorship. Since most current investigators have not had an opportunity to study all of the author's previous work, a review of the highlights of that work may be of value to them. The present paper describes some of the author's conceptual designs and their rationale, and the special analytical techniques developed to analyze their performance. The basic designs, first published in 1963, are based on single-cell converters, either double-ended diodes extending over the full height of the reactor core or single-ended diodes extending over half the core height. In that respect they are similar to the thermionic fuel elements employed in the Topaz-2 reactor subsequently developed in the Soviet Union, copies of which were recently imported by the U.S. As in the Topaz-2 case, electrically heated steady-state performance tests of the converters are possible before fueling. Where the author's concepts differed from the later Topaz-2 design was in the relative location of the emitter and the collector. Placing the fueled emitter on the outside of the cylindrical diodes permits much higher axial conductances to reduce ohmic losses in the electrodes of full-core-height diodes. Moreover, placing the fuel on the outside of the diode makes possible reactors with much higher fuel volume fractions, which enable power-flattened fast reactors scalable to very low power levels without the need for life-limiting hydride moderators or the use of efficiency-limiting driver fuel. In addition, with the fuel on the outside its swelling does not increase the emitter diameter or reduce the interelectrode gap. This should permit long lifetimes even with closer spacings, which can significantly improve the system efficiences. This was confirmed by coupled neutronic, thermal, thermionic, and electrical system analyses - some of which are presented in this paper - and by subsequent experiments. A companion paper presented next describes the fabrication and testing of full-scale converter elements, both fueled and unfueled, and summarizes the test results obtained. There is a duplicate copy in the file.

  20. Realistic Earth matter effects and a method to acquire information about small ?_{13} in the detection of supernova neutrinos

    E-Print Network [OSTI]

    Xin-Heng Guo; Ming-Yang Huang; Bing-Lin Young

    2009-04-14T23:59:59.000Z

    In this paper, we first calculate the realistic Earth matter effects in the detection of type II supernova neutrinos at the Daya Bay reactor neutrino experiment which is currently under construction. It is found that the Earth matter effects depend on the neutrino incident angle $\\theta$, the neutrino mass hierarchy $\\Delta m_{31}^{2}$, the crossing probability at the high resonance region inside the supernova, $P_{H}$, the neutrino temperature, $T_{\\alpha}$, and the pinching parameter in the neutrino spectrum, $\\eta_{\\alpha}$. We also take into account the collective effects due to neutrino-neutrino interactions inside the supernova. With the expression for the dependence of $P_H$ on the neutrino mixing angle $\\theta_{13}$, we obtain the relations between $\\theta_{13}$ and the event numbers for various reaction channels of supernova neutrinos. Using these relations, we propose a possible method to acquire information about $\\theta_{13}$ smaller than $1.5^\\circ$. Such a sensitivity cannot yet be achieved by the Daya Bay reactor neutrino experiment which has a sensitivity of the order of $\\theta_{13}\\sim 3^\\circ$. Furthermore, we apply this method to other neutrino experiments, i.e. Super-K, SNO, KamLAND, LVD, MinBooNE, Borexino, and Double-Chooz. We also study the energy spectra of the differential event numbers, ${\\rm d}N/{\\rm d}E$.

  1. Ambient dissolved oxygen concentrations in Delaware's Inland Bays. Final report, June 6, 1984

    SciTech Connect (OSTI)

    Biggs, R.B.

    1984-01-01T23:59:59.000Z

    Ambient dissolved oxygen concentrations were measured at dawn during August, 1983, in Rehoboth and Indian River Bays. In Indian River Bay, 59% of the D.O. measurements were below the State minimum water quality standard of 5 mg L/sup -1/, while in Rehoboth Bay 17% of the values fail to meet the State standards. Diurnal dissolved oxygen curves measured at 5 stations in the Bays and tributary creeks, provide evidence that, although the Bays are in reasonable balance with respect to apparent net daytime photosynthesis (Pa) and nighttime respiration (Rn), the absolute values of Pa and Rn are very high, compared with other coastal ecosystems, except for central Rehoboth Bay. These conclusions are consistent with the annual nutrient loads to the systems, which are about double for Indian River when contrasted with Rehoboth. 11 references, 1 figure, 7 tables.

  2. Designing Reactors to Facilitate Decommissioning

    SciTech Connect (OSTI)

    Richard H. Meservey

    2006-06-01T23:59:59.000Z

    Critics of nuclear power often cite issues with tail-end-of-the-fuel-cycle activities as reasons to oppose the building of new reactors. In fact, waste disposal and the decommissioning of large nuclear reactors have proven more challenging than anticipated. In the early days of the nuclear power industry the design and operation of various reactor systems was given a great deal of attention. Little effort, however, was expended on end-of-the-cycle activities, such as decommissioning and disposal of wastes. As early power and test reactors have been decommissioned difficulties with end-of-the-fuel-cycle activities have become evident. Even the small test reactors common at the INEEL were not designed to facilitate their eventual decontamination, decommissioning, and dismantlement. The results are that decommissioning of these facilities is expensive, time consuming, relatively hazardous, and generates large volumes of waste. This situation clearly supports critics concerns about building a new generation of power reactors.

  3. Investigation of tidal power, Cobscook Bay, Maine. Environmental Appendix

    SciTech Connect (OSTI)

    Not Available

    1980-08-01T23:59:59.000Z

    This report presents information regarding existing terrestrial and marine resources and water quality conditions in the Cobscook Bay area. A preliminary assessment of impacts from a tidal power project is also presented and data gaps are identified. Reports contained in the appendix were prepared by the U.S. Fish and Wildlife Service, the National Marine Fisheries Service, the University of Maine at Orino, School of Forestry Resources and the U.S. Army Corps of Engineers.

  4. Submarine geomorphology of Eastern Ross Sea and Sulzberger Bay, Antarctica

    E-Print Network [OSTI]

    Lepley, Larry Kent

    1964-01-01T23:59:59.000Z

    SUBMARINE GEOMORPHOLOGY OF EASTERN ROSS SEA AND SULZBERGER BAY, ANTARCTICA A Thocis By Submitted to the Graduate College of the Texas A 6 H Universicy in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE lanum...- ': Bsfhpeotrg l. Outer Snelf ?. ? Q ? ~elf =Bepr eeoione 3. inner Shelf 4~ B id gee S ed haunts l. Antaratic Uorine Sedhaento B seclhnents of Eastern Rom ssa - suleborgsr Boy Dissuasion Outer Shelf a. Ihwtstio, Xsostatio, snd Qlaoia1 Sister@ b. ?h igin...

  5. Fast quench reactor and method

    DOE Patents [OSTI]

    Detering, B.A.; Donaldson, A.D.; Fincke, J.R.; Kong, P.C.

    1998-05-12T23:59:59.000Z

    A fast quench reactor includes a reactor chamber having a high temperature heating means such as a plasma torch at its inlet and a restrictive convergent-divergent nozzle at its outlet end. Reactants are injected into the reactor chamber. The resulting heated gaseous stream is then rapidly cooled by passage through the nozzle. This ``freezes`` the desired end product(s) in the heated equilibrium reaction stage. 7 figs.

  6. Weighting and Bayes Nets for Rollup of Surveillance Metrics

    SciTech Connect (OSTI)

    Henson, Kriste [Los Alamos National Laboratory; Sentz, Kari [Los Alamos National Laboratory; Hamada, Michael [Los Alamos National Laboratory

    2012-04-30T23:59:59.000Z

    The LANL IKE team proposes that the surveillance metrics for several data stream that are used to detect the same failure mode be weighted. Similarly, the failure mode metrics are weighted to obtain a subsystem metric. E.g., if there n data streams (nodes 1-n), the failure mode (node 0) metric is obtained as M{sub 0} = w{sub 1}M{sub 1} + {hor_ellipsis} + w{sub n}M{sub n}, where {Sigma}{sub i=1}{sup n} w{sub i} = 1. This proposal has been implemented with Bayes Nets using the Netica/IKE software by specifying an appropriate conditional probability table (CPT). This CPT is calculated using the same form as (1), where the data stream metrics for the true (T) and false (F) states are replaced by 1 and 0, respectively. Then using this CPT, the failure mode metric calculated by Netica/IKE equals (1). This result has two nice features. First, the rollup Bayes nets is doing can be easily explained. Second, because Bayes Nets can implement this rollup using Netica/IKE, then data marshalling (allocating next year's budget) can be studied. A proof that the claim 'failure mode metric calculated by Netica/IKE equals (1)' for n = 2 and n = 3 follows as well as the sketch of a proof by induction for general n.

  7. State of the Chesapeake Bay: second annual monitoring report, compendium. Report for January 1984-September 1985

    SciTech Connect (OSTI)

    Lynch, M.P.; Krome, E.C.

    1987-04-01T23:59:59.000Z

    The report is a summary of information collected at stations around the Chesapeake Bay. It is designed to be a more detailed/technical companion to the State Of The Bay Summary Report. It reports the results of the monitoring of the Chesapeake Bay in terms of its physical and chemical makeup (sediments, the distribution of toxics), the living resources, (plankton, benthos, submerged aquatic vegetation, birds), and the Patuxent River, as a case history.

  8. Neutrino Oscillation Studies with Reactors

    E-Print Network [OSTI]

    Petr Vogel; Liangjian Wen; Chao Zhang

    2015-03-03T23:59:59.000Z

    Nuclear reactors are one of the most intense, pure, controllable, cost-effective, and well-understood sources of neutrinos. Reactors have played a major role in the study of neutrino oscillations, a phenomenon that indicates that neutrinos have mass and that neutrino flavors are quantum mechanical mixtures. Over the past several decades reactors were used in the discovery of neutrinos, were crucial in solving the solar neutrino puzzle, and allowed the determination of the smallest mixing angle $\\theta_{13}$. In the near future, reactors will help to determine the neutrino mass hierarchy and to solve the puzzling issue of sterile neutrinos.

  9. Neutrino Oscillation Studies with Reactors

    E-Print Network [OSTI]

    Petr Vogel; Liangjian Wen; Chao Zhang

    2015-04-27T23:59:59.000Z

    Nuclear reactors are one of the most intense, pure, controllable, cost-effective, and well-understood sources of neutrinos. Reactors have played a major role in the study of neutrino oscillations, a phenomenon that indicates that neutrinos have mass and that neutrino flavors are quantum mechanical mixtures. Over the past several decades reactors were used in the discovery of neutrinos, were crucial in solving the solar neutrino puzzle, and allowed the determination of the smallest mixing angle $\\theta_{13}$. In the near future, reactors will help to determine the neutrino mass hierarchy and to solve the puzzling issue of sterile neutrinos.

  10. Neutrino Oscillation Studies with Reactors

    E-Print Network [OSTI]

    Vogel, Petr; Zhang, Chao

    2015-01-01T23:59:59.000Z

    Nuclear reactors are one of the most intense, pure, controllable, cost-effective, and well-understood sources of neutrinos. Reactors have played a major role in the study of neutrino oscillations, a phenomenon that indicates that neutrinos have mass and that neutrino flavors are quantum mechanical mixtures. Over the past several decades reactors were used in the discovery of neutrinos, were crucial in solving the solar neutrino puzzle, and allowed the determination of the smallest mixing angle $\\theta_{13}$. In the near future, reactors will help to determine the neutrino mass hierarchy and to solve the puzzling issue of sterile neutrinos.

  11. Progress Update: Reactor Disassembly Grouting

    ScienceCinema (OSTI)

    Cody, Tom

    2012-06-14T23:59:59.000Z

    Grouting the P&R reactors in order to remove these basins as an environmental threat. This will end the Cold War legacy and end the environmental footprint.

  12. Progress Update: Reactor Disassembly Grouting

    SciTech Connect (OSTI)

    Cody, Tom

    2010-01-01T23:59:59.000Z

    Grouting the P&R reactors in order to remove these basins as an environmental threat. This will end the Cold War legacy and end the environmental footprint.

  13. Neutrino oscillation studies with reactors

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Vogel, P. [California Inst. of Technology (CalTech), Pasadena, CA (United States). Kellog Radiation Lab.; Wen, L.J. [Chinese Academy of Sciences (CAS), Beijing (China). Inst. of High Energy Physics (IHEP); Zhang, C. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2015-04-27T23:59:59.000Z

    Nuclear reactors are one of the most intense, pure, controllable, cost-effective and well-understood sources of neutrinos. Reactors have played a major role in the study of neutrino oscillations, a phenomenon that indicates that neutrinos have mass and that neutrino flavours are quantum mechanical mixtures. Over the past several decades, reactors were used in the discovery of neutrinos, were crucial in solving the solar neutrino puzzle, and allowed the determination of the smallest mixing angle ?13. In the near future, reactors will help to determine the neutrino mass hierarchy and to solve the puzzling issue of sterile neutrinos.

  14. Thermonuclear Reflect AB-Reactor

    E-Print Network [OSTI]

    Alexander Bolonkin

    2008-03-26T23:59:59.000Z

    The author offers a new kind of thermonuclear reflect reactor. The remarkable feature of this new reactor is a three net AB reflector, which confines the high temperature plasma. The plasma loses part of its energy when it contacts with the net but this loss can be compensated by an additional permanent plasma heating. When the plasma is rarefied (has a small density), the heat flow to the AB reflector is not large and the temperature in the triple reflector net is lower than 2000 - 3000 K. This offered AB-reactor has significantly less power then the currently contemplated power reactors with magnetic or inertial confinement (hundreds-thousands of kW, not millions of kW). But it is enough for many vehicles and ships and particularly valuable for tunnelers, subs and space apparatus, where air to burn chemical fuel is at a premium or simply not available. The author has made a number of innovations in this reactor, researched its theory, developed methods of computation, made a sample computation of typical project. The main point of preference for the offered reactor is its likely cheapness as a power source. Key words: Micro-thermonuclear reactor, Multi-reflex AB-thermonuclear reactor, Self-magnetic AB-thermonuclear reactor, aerospace thermonuclear engine.

  15. Waste Stream Generated and Waste Disposal Plans for Molten Salt Reactor Experiment at Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Haghighi, M. H.; Szozda, R. M.; Jugan, M. R.

    2002-02-26T23:59:59.000Z

    The Molten Salt Reactor Experiment (MSRE) site is located in Tennessee, on the U.S. Department of Energy (DOE) Oak Ridge Reservation (ORR), south of the Oak Ridge National Laboratory (ORNL) main plant across Haw Ridge in Melton Valley. The MSRE was run by ORNL to demonstrate the desirable features of the molten-salt concept in a practical reactor that could be operated safely and reliably. It introduced the idea of a homogeneous reactor using fuel salt media and graphite moderation for power and breeder reactors. The MSRE reactor and associated components are located in cells beneath the floor in the high-bay area of Building 7503 (Figure 1). The reactor was operated from June 1965 to December 1969. When the reactor was shut down, fuel salt was drained from the reactor circuit to two drain tanks. A ''clean'' salt was then circulated through the reactor as a decontamination measure and drained to a third drain tank. When operations ceased, the fuel and flush salts were allowed t o cool and solidify in the drain tanks. At shutdown, the MSRE facility complex was placed in a surveillance and maintenance program. As a result of the S&M program, it was discovered in 1994 that gaseous uranium (233U/232U) hexafluoride (UF6) had moved throughout the MSRE process systems. The UF6 was generated when radiolysis of the fluorine salts caused the individual constituents to dissociate to their component atoms, including free fluorine.Some of the free fluorine combined with uranium fluorides (UF4) in the salt to form UF6. UF6 is gaseous at slightly above ambient temperatures; thus, periodic heating of the fuel salts (which was intended to remedy the radiolysis problems) and simple diffusion had allowed the UF6 to move out of the salt and into the process systems of MSRE.

  16. Building America Whole-House Solutions for Existing HomesBay...

    Broader source: Energy.gov (indexed) [DOE]

    non-invasive retrofit measures. Bay Ridge Gardens-Mixed Humid Affordable Multifamily Housing Deep Energy Retrofit More Documents & Publications Building America Whole-House...

  17. Current Perspectives on the Physical and Biological Processes of Humboldt Bay

    E-Print Network [OSTI]

    Schlosser, S. C.; Rasmussen, R.

    2007-01-01T23:59:59.000Z

    1893 and began ditching and dredging the marshland from thetions and Maintenance Dredging. Draft Program- matic 5-Yearwharf was abandoned. Early Dredging Humboldt Bay has been

  18. Current Perspectives on the Physical and Biological Processes of Humboldt Bay

    E-Print Network [OSTI]

    Schlosser, S. C.; Rasmussen, R.

    2007-01-01T23:59:59.000Z

    Humboldt Bay. Fab r icia sabella (Ehrenberg 1937) SABELLIDAEin estuarine mud. Banse (1979) reports Fab r icia sabellasabella from Newcastle Island, British Columbia; and

  19. Presentations

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Craig Tull: Present and Future Computing Requirements for Daya Bay November 27, 2012 | Author(s): Craig Tull (LBNL) | Download File: CraigTull20121127Dayabay.pdf | pdf | 11 MB...

  20. March 27

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    27 March 27 Attending: Eric Larry Iwona Barbara JeffP Mike Utilization: Cluster has been full with Daya Bay running quite a bit. Outages: 2 interactive reboots for SL6 upgrade and...

  1. Presentations

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Future Computing Requirements for Daya Bay November 27, 2012 | Author(s): Craig Tull (LBNL) | Download File: CraigTull20121127Dayabay.pdf | pdf | 11 MB Present and Future...

  2. NERSC Global Filesystem Played a Key Role in Discovery of the...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Physics (HEP), NERSC Global Filesystems (NGF), Science Gateways John Hules, JAHules@lbl.gov, +1 510 486 6008 XBD201107-00790-183.jpg Daya Bay Neutrino Facility in China. Photo by...

  3. anna nuclear power: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Chapter 11 Effects of the Operating Nuclear Power Plant on Marine Ecology and Environment - A Case Study of Daya Bay in China 255 You-Shao Wang Chapter 12 Microbial Leaching...

  4. Reactor coolant pump flywheel

    DOE Patents [OSTI]

    Finegan, John Raymond; Kreke, Francis Joseph; Casamassa, John Joseph

    2013-11-26T23:59:59.000Z

    A flywheel for a pump, and in particular a flywheel having a number of high density segments for use in a nuclear reactor coolant pump. The flywheel includes an inner member and an outer member. A number of high density segments are provided between the inner and outer members. The high density segments may be formed from a tungsten based alloy. A preselected gap is provided between each of the number of high density segments. The gap accommodates thermal expansion of each of the number of segments and resists the hoop stress effect/keystoning of the segments.

  5. Reactor refueling containment system

    DOE Patents [OSTI]

    Gillett, J.E.; Meuschke, R.E.

    1995-05-02T23:59:59.000Z

    A method of refueling a nuclear reactor is disclosed whereby the drive mechanism is disengaged and removed by activating a jacking mechanism that raises the closure head. The area between the barrier plate and closure head is exhausted through the closure head penetrations. The closure head, upper drive mechanism, and bellows seal are lifted away and transported to a safe area. The barrier plate acts as the primary boundary and each drive and control rod penetration has an elastomer seal preventing excessive tritium gases from escaping. The individual instrumentation plugs are disengaged allowing the corresponding fuel assembly to be sealed and replaced. 2 figs.

  6. Nuclear reactor control assembly

    SciTech Connect (OSTI)

    Negron, S.B.

    1991-06-11T23:59:59.000Z

    This patent describes an assembly for providing global power control in a nuclear reactor having the core split into two halves. It comprises a disk assembly formed from at least two disks each machined with an identical surface hole pattern such that rotation of one disk relative to the other causes the hole pattern to open or close, the disk assembly being positioned substantially at the longitudinal center of and coaxial with the core halves; and means for rotating at least one of the disks relative to the other.

  7. Nuclear reactor control apparatus

    SciTech Connect (OSTI)

    Sridhar, B.N.

    1981-08-28T23:59:59.000Z

    Nuclear reactor core safety rod release apparatus comprises a control rod having a detent notch in the form of an annular peripheral recess at its upper end, a control rod support tube for raising and lowering the control rod under normal conditions, latches pivotally mounted on the control support tube with free ends thereof normally disposed in the recess in the control rod, and cam means for pivoting the latches out of the recess in the control rod when a scram condition occurs. One embodiment of the invention comprises an additonal magnetically-operated latch for releasing the control rod under two different conditions, one involving seismic shock.

  8. Biparticle fluidized bed reactor

    DOE Patents [OSTI]

    Scott, C.D.; Marasco, J.A.

    1996-02-27T23:59:59.000Z

    A fluidized bed reactor system is described which utilizes a fluid phase, a retained fluidized primary particulate phase, and a migratory second particulate phase. The primary particulate phase is a particle such as a gel bead containing an immobilized biocatalyst. The secondary and tertiary particulate phases, continuously introduced and removed simultaneously in the cocurrent and countercurrent mode, act in a role such as a sorbent to continuously remove a product or by-product constituent from the fluid phase. Means for introducing and removing the sorbent phases include feed screw mechanisms and multivane slurry valves. 3 figs.

  9. Biparticle fluidized bed reactor

    DOE Patents [OSTI]

    Scott, Charles D. (Oak Ridge, TN)

    1993-01-01T23:59:59.000Z

    A fluidized bed reactor system which utilizes a fluid phase, a retained fluidized primary particulate phase, and a migratory second particulate phase. The primary particulate phase is a particle such as a gel bead containing an immobilized biocatalyst. The secondary particulate phase, continuously introduced and removed in either cocurrent or countercurrent mode, acts in a secondary role such as a sorbent to continuously remove a product or by-product constituent from the fluid phase. Introduction and removal of the sorbent phase is accomplished through the use of feed screw mechanisms and multivane slurry valves.

  10. Biparticle fluidized bed reactor

    DOE Patents [OSTI]

    Scott, Charles D. (Oak Ridge, TN); Marasco, Joseph A. (Kingston, TN)

    1995-01-01T23:59:59.000Z

    A fluidized bed reactor system utilizes a fluid phase, a retained fluidized primary particulate phase, and a migratory second particulate phase. The primary particulate phase is a particle such as a gel bead containing an immobilized biocatalyst. The secondary particulate phase, continuously introduced and removed in either cocurrent or countercurrent mode, acts in a secondary role such as a sorbent to continuously remove a product or by-product constituent from the fluid phase. Introduction and removal of the sorbent phase is accomplished through the use of feed screw mechanisms and multivane slurry valves.

  11. Biparticle fluidized bed reactor

    DOE Patents [OSTI]

    Scott, Charles D. (Oak Ridge, TN); Marasco, Joseph A. (Kingston, TN)

    1996-01-01T23:59:59.000Z

    A fluidized bed reactor system which utilizes a fluid phase, a retained fluidized primary particulate phase, and a migratory second particulate phase. The primary particulate phase is a particle such as a gel bead containing an immobilized biocatalyst. The secondary and tertiary particulate phases, continuously introduced and removed simultaneously in the cocurrent and countercurrent mode, act in a role such as a sorbent to continuously remove a product or by-product constituent from the fluid phase. Means for introducing and removing the sorbent phases include feed screw mechanisms and multivane slurry valves.

  12. Biparticle fluidized bed reactor

    DOE Patents [OSTI]

    Scott, C.D.

    1993-12-14T23:59:59.000Z

    A fluidized bed reactor system which utilizes a fluid phase, a retained fluidized primary particulate phase, and a migratory second particulate phase is described. The primary particulate phase is a particle such as a gel bead containing an immobilized biocatalyst. The secondary particulate phase, continuously introduced and removed in either cocurrent or countercurrent mode, acts in a secondary role such as a sorbent to continuously remove a product or by-product constituent from the fluid phase. Introduction and removal of the sorbent phase is accomplished through the use of feed screw mechanisms and multivane slurry valves. 3 figures.

  13. Reactor refueling containment system

    DOE Patents [OSTI]

    Gillett, James E. (Greensburg, PA); Meuschke, Robert E. (Pittsburgh, PA)

    1995-01-01T23:59:59.000Z

    A method of refueling a nuclear reactor whereby the drive mechanism is disengaged and removed by activating a jacking mechanism that raises the closure head. The area between the barrier plate and closure head is exhausted through the closure head penetrations. The closure head, upper drive mechanism, and bellows seal are lifted away and transported to a safe area. The barrier plate acts as the primary boundary and each drive and control rod penetration has an elastomer seal preventing excessive tritium gases from escaping. The individual instrumentation plugs are disengaged allowing the corresponding fuel assembly to be sealed and replaced.

  14. Biparticle fluidized bed reactor

    DOE Patents [OSTI]

    Scott, C.D.; Marasco, J.A.

    1995-04-25T23:59:59.000Z

    A fluidized bed reactor system utilizes a fluid phase, a retained fluidized primary particulate phase, and a migratory second particulate phase. The primary particulate phase is a particle such as a gel bead containing an immobilized biocatalyst. The secondary particulate phase, continuously introduced and removed in either cocurrent or countercurrent mode, acts in a secondary role such as a sorbent to continuously remove a product or by-product constituent from the fluid phase. Introduction and removal of the sorbent phase is accomplished through the use of feed screw mechanisms and multivane slurry valves. 3 figs.

  15. Nuclear reactor control apparatus

    DOE Patents [OSTI]

    Sridhar, Bettadapur N. (Cupertino, CA)

    1983-11-01T23:59:59.000Z

    Nuclear reactor core safety rod release apparatus comprises a control rod having a detent notch in the form of an annular peripheral recess at its upper end, a control rod support tube for raising and lowering the control rod under normal conditions, latches pivotally mounted on the control support tube with free ends thereof normally disposed in the recess in the control rod, and cam means for pivoting the latches out of the recess in the control rod when a scram condition occurs. One embodiment of the invention comprises an additional magnetically-operated latch for releasing the control rod under two different conditions, one involving seismic shock.

  16. N Reactor - Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes |IsLove Your1 SECTIONES2008-54174MoreMuseum Day atMyNERSCVanN Reactor

  17. Fast Reactor Fuel Type and Reactor Safety Performance

    SciTech Connect (OSTI)

    R. Wigeland; J. Cahalan

    2009-09-01T23:59:59.000Z

    Fast Reactor Fuel Type and Reactor Safety Performance R. Wigeland , Idaho National Laboratory J. Cahalan, Argonne National Laboratory The sodium-cooled fast neutron reactor is currently being evaluated for the efficient transmutation of the highly-hazardous, long-lived, transuranic elements that are present in spent nuclear fuel. One of the fundamental choices that will be made is the selection of the fuel type for the fast reactor, whether oxide, metal, carbide, nitride, etc. It is likely that a decision on the fuel type will need to be made before many of the related technologies and facilities can be selected, from fuel fabrication to spent fuel reprocessing. A decision on fuel type should consider all impacts on the fast reactor system, including safety. Past work has demonstrated that the choice of fuel type may have a significant impact on the severity of consequences arising from accidents, especially for severe accidents of low probability. In this paper, the response of sodium-cooled fast reactors is discussed for both oxide and metal fuel types, highlighting the similarities and differences in reactor response and accident consequences. Any fast reactor facility must be designed to be able to successfully prevent, mitigate, or accommodate all consequences of potential events, including accidents. This is typically accomplished by using multiple barriers to the release of radiation, including the cladding on the fuel, the intact primary cooling system, and most visibly the reactor containment building. More recently, this has also included the use of ‘inherent safety’ concepts to reduce or eliminate the potential for serious damage in some cases. Past experience with oxide and metal fuel has demonstrated that both fuel types are suitable for use as fuel in a sodium-cooled fast reactor. However, safety analyses for these two fuel types have also shown that there can be substantial differences in accident consequences due to the neutronic and thermophysical properties of the fuel and their compatibility with the reactor coolant, with corresponding differences in the challenges presented to the reactor developers. Accident phenomena are discussed for the sodium-cooled fast reactor based on the mechanistic progression of conditions from accident initiation to accident termination, whether a benign state is achieved or more severe consequences are expected. General principles connecting accident phenomena and fuel properties are developed from the oxide and metal fuel safety analyses, providing guidelines that can be used as part of the evaluation for selection of fuel type for the sodium-cooled fast reactor.

  18. Granular Dynamics in Pebble Bed Reactor Cores

    E-Print Network [OSTI]

    Laufer, Michael Robert

    2013-01-01T23:59:59.000Z

    in a pebble-bed nuclear reactor,” Phys. Rev. E, vol. 74, no.cycles of the pebble bed reactor,” Nuclear Engineering andoptimization of pebble-bed reactors,” Annals of Nuclear

  19. Gaseous reactor control system

    SciTech Connect (OSTI)

    Abdel-Khalik, S.

    1991-09-03T23:59:59.000Z

    This paper describes a nuclear reactor control system for controlling the reactivity of the core of a nuclear reactor. It includes a control gas having a high neutron cross-section; a first tank containing a first supply of the control gas; a first conduit providing a first fluid passage extending into the core, the first conduit being operatively connected to communicate with the first tank; a first valve operatively connected to regulate the flow of the control gas between the first tank and the first conduit; a second conduit concentrically disposed around the first conduit such that a second fluid passage is defined between the outer surface of the first conduit and the inner surface of the second conduit; a second tank containing a second supply of the control gas, the second tank being operatively connected to communicate with the second fluid passage; a second supply valve operatively connected to regulate the flow of the control gas between the second tank and the second fluid passage.

  20. Solvent refined coal reactor quench system

    DOE Patents [OSTI]

    Thorogood, R.M.

    1983-11-08T23:59:59.000Z

    There is described an improved SRC reactor quench system using a condensed product which is recycled to the reactor and provides cooling by evaporation. In the process, the second and subsequent reactors of a series of reactors are cooled by the addition of a light oil fraction which provides cooling by evaporation in the reactor. The vaporized quench liquid is recondensed from the reactor outlet vapor stream. 1 fig.

  1. Reactor Neutrino Physics -- An Update

    E-Print Network [OSTI]

    Felix Boehm

    1999-06-18T23:59:59.000Z

    We review the status and the results of reactor neutrino experiments. Long baseline oscillation experiments at Palo Verde and Chooz have provided limits for the oscillation parameters while the recently proposed Kamland experiment at a baseline of more than 100km is now in the planning stage. We also describe the status of neutrino magnetic moment experiments at reactors.

  2. Radiation Shielding for Fusion Reactors

    SciTech Connect (OSTI)

    Santoro, R.T.

    1999-10-01T23:59:59.000Z

    Radiation shielding requirements for fusion reactors present different problems than those for fission reactors and accelerators. Fusion devices, particularly tokamak reactors, are complicated by geometry constraints that complicate disposition of fully effective shielding. This paper reviews some of these shielding issues and suggested solutions for optimizing the machine and biological shielding. Radiation transport calculations are essential for predicting and confirming the nuclear performance of the reactor and, as such, must be an essential part of the reactor design process. Development and optimization of reactor components from the first wall and primary shielding to the penetrations and containment shielding must be carried out in a sensible progression. Initial results from one-dimensional transport calculations are used for scoping studies and are followed by detailed two- and three-dimensional analyses to effectively characterize the overall radiation environment. These detail model calculations are essential for accounting for the radiation leakage through ports and other penetrations in the bulk shield. Careful analysis of component activation and radiation damage is cardinal for defining remote handling requirements, in-situ replacement of components, and personnel access at specific locations inside the reactor containment vessel. Radiation shielding requirements for fusion reactors present different problems than those for fission reactors and accelerators. Fusion devices, particularly tokamak reactors, are complicated by geometry constraints that complicate disposition of fully effective shielding. This paper reviews some of these shielding issues and suggested solutions for optimizing the machine and biological shielding. Radiation transport calculations are essential for predicting and confirming the nuclear performance of the reactor and, as such, must be an essential part of the reactor design process. Development and optimization of reactor components from the first wall and primary shielding to the penetrations and containment shielding must be carried out in a sensible progression. Initial results from one-dimensional transport calculations are used for scoping studies and are followed by detailed two- and three-dimensional analyses to effectively characterize the overall radiation environment. These detail model calculations are essential for accounting for the radiation leakage through ports and other penetrations in the bulk shield. Careful analysis of component activation and radiation damage is cardinal for defining remote handling requirements, in-situ replacement of components, and personnel access at specific locations inside the reactor containment vessel.

  3. Granular Dynamics in Pebble Bed Reactor Cores

    E-Print Network [OSTI]

    Laufer, Michael Robert

    2013-01-01T23:59:59.000Z

    gas reactors with the effective heat transfer of a molten salt coolant and the passive natural circulation safety systems of sodium fast reactors.

  4. MOOSE simulating nuclear reactor CRUD buildup

    ScienceCinema (OSTI)

    None

    2014-07-21T23:59:59.000Z

    This simulation uses multiple physical models to show how the buildup of boron deposits on reactor fuel can affect performance and the reactor's power profile.

  5. MOOSE simulating nuclear reactor CRUD buildup

    SciTech Connect (OSTI)

    None

    2014-02-06T23:59:59.000Z

    This simulation uses multiple physical models to show how the buildup of boron deposits on reactor fuel can affect performance and the reactor's power profile.

  6. The Endurance Bioenergy Reactor | Argonne National Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    The Endurance Bioenergy Reactor Share Description Argonne biophysicist Dr. Philip Laible and Air Force Major Matt Michaud talks about he endurance bioenergy reactor-a device that...

  7. Fast reactors and nuclear nonproliferation

    SciTech Connect (OSTI)

    Avrorin, E.N. [Russian Federal Nuclear Center - Zababakhin Institute of Applied Physics, Snezhinsk (Russian Federation); Rachkov, V.I.; Chebeskov, A.N. [State Scientific Center of the Russian Federation - Institute for Physics and Power Engineering, Bondarenko Square, 1, Obninsk, Kaluga region, 249033 (Russian Federation)

    2013-07-01T23:59:59.000Z

    Problems are discussed with regard to nuclear fuel cycle resistance in fast reactors to nuclear proliferation risk due to the potential for use in military programs of the knowledge, technologies and materials gained from peaceful nuclear power applications. Advantages are addressed for fast reactors in the creation of a more reliable mode of nonproliferation in the closed nuclear fuel cycle in comparison with the existing fully open and partially closed fuel cycles of thermal reactors. Advantages and shortcomings are also discussed from the point of view of nonproliferation from the start with fast reactors using plutonium of thermal reactor spent fuel and enriched uranium fuel to the gradual transition using their own plutonium as fuel. (authors)

  8. Physics and Physical Oceanography Data Report 2000-2 Tow-Yo and Temperature Data from Trinity Bay,

    E-Print Network [OSTI]

    deYoung, Brad

    Physics and Physical Oceanography Data Report 2000-2 Tow-Yo and Temperature Data from Trinity Bay Oeanography Memorial University of Newfoundland St. John's, Newfoundland A1B 3X7 #12;ii Abstract Trinity Bay

  9. Automatic reactor power control for a pressurized water reactor

    SciTech Connect (OSTI)

    Jungin Choi (Kyungwon Univ. (Korea, Republic of)); Yungjoon Hah (Korea Atomic Energy Research Inst., Daejeon (Korea, Republic of)); Unchul Lee (Seoul National Univ. (Korea, Republic of))

    1993-05-01T23:59:59.000Z

    An automatic reactor power control system is presented for a pressurized water reactor (PWR). The associated reactor control strategy is called mode K.' The new system implements a heavy-worth bank dedicated to axial shape control, independent of the existing regulating banks. The heavy bank provides a monotonic relationship between its motion and the axial shape change, which allows automatic control of the axial power distribution. Thus, the mode K enables precise regulation of both the reactivity and the power distribution, by using double closed-loop control of the reactor coolant temperature and the axial power difference. Automatic reactor power control permits the nuclear power plant to accommodate the load-follow operations, including frequency control, to respond to the grid requirements. The mode K reactor control concepts were tested using simulation responses of a Korean standardized 1,000-MW (electric) PWR. The simulation results illustrate that the mode K would be a practical reactor power control strategy for the increased automation of nuclear plants.

  10. Enhanced Land Subsidence and Seidment Dynamics in Galveston Bay- Implications for Geochemical Processes and Fate and Transport of Contaminants

    E-Print Network [OSTI]

    Almukaimi, Mohammad E

    2013-07-05T23:59:59.000Z

    ENHANCED LAND SUBSIDENCE AND SEDIMENT DYNAMICS IN GALVESTON BAY- IMPLICATIONS FOR GEOCHEMICAL PROCESSES AND FATE AND TRANSPORT OF CONTAMINANTS A Thesis by MOHAMMAD ALMUKAIMI Submitted to the Office of Graduate Studies of Texas A... August 2013 Major Subject: Oceanography Copyright 2013 Mohammad Almukaimi ii ABSTRACT Galveston Bay is the second largest estuary in the Gulf of Mexico. The bay?s watershed and shoreline contains one of the largest concentrations...

  11. Nuclear reactor engineering: Reactor design basics. Fourth edition, Volume One

    SciTech Connect (OSTI)

    Glasstone, S.; Sesonske, A.

    1994-12-31T23:59:59.000Z

    This new edition of this classic reference combines broad yet in-depth coverage of nuclear engineering principles with practical descriptions of their application in design and operation of nuclear power plants. Extensively updated, the fourth edition includes new material on reactor safety and risk analysis, regulation, fuel management, waste management, and operational aspects of nuclear power. This volume contains the following: energy from nuclear fission; nuclear reactions and radiations; neutron transport; nuclear design basics; nuclear reactor kinetics and control; radiation protection and shielding; and reactor materials.

  12. University Reactor Conversion Lessons Learned Workshop for Purdue University Reactor

    SciTech Connect (OSTI)

    Eric C. Woolstenhulme; Dana M. Hewit

    2008-09-01T23:59:59.000Z

    The Department of Energy’s Idaho National Laboratory, under its programmatic responsibility for managing the University Research Reactor Conversions, has completed the conversion of the reactor at Purdue University Reactor. With this work completed and in anticipation of other impending conversion projects, the INL convened and engaged the project participants in a structured discussion to capture the lessons learned. The lessons learned process has allowed us to capture gaps, opportunities, and good practices, drawing from the project team’s experiences. These lessons will be used to raise the standard of excellence, effectiveness, and efficiency in all future conversion projects.

  13. SOME EFFECTS OF HYDRAULIC DREDGING AND COASTAL DEVELOPMENT IN BOCA CIEGA BAY, FLORIDA 1

    E-Print Network [OSTI]

    SOME EFFECTS OF HYDRAULIC DREDGING AND COASTAL DEVELOPMENT IN BOCA CIEGA BAY, FLORIDA 1 BY JOHN L. PETERSBURG BEACH, FLA. 33706 ABSTRACT Filling of 1,400 hectares (3,500 acres) of bay by hy- draulic dredging in dredged ItreltS wit.h those in relatively undisturbed ttreas. Hydl'ltulic dredging becmue. ltll ltccepted

  14. Mercury speciation in Galveston Bay, Texas: the importance of complexation by natural organic ligands

    E-Print Network [OSTI]

    Han, Seunghee

    2005-02-17T23:59:59.000Z

    of the requirements for the degree of DOCTOR OF PHILOSOPHY December 2004 Major Subject: Oceanography MERCURY SPECIATION IN GALVESTON BAY, TEXAS: THE IMPORTANCE OF COMPLEXATION BY NATURAL ORGANIC LIGANDS A Dissertation by SEUNGHEE HAN.... Cifuentes (Member) Paul A. Lindahl (Member) Wilford D. Gardner (Head of Department) December 2004 Major Subject: Oceanography iii ABSTRACT Mercury Speciation in Galveston Bay, Texas: The Importance of Complexation...

  15. Feeding habits of the Guiana dolphin, Sotalia guianensis (Cetacea: Delphinidae), in Norte Bay,

    E-Print Network [OSTI]

    Simőes-Lopes, Paulo César

    Feeding habits of the Guiana dolphin, Sotalia guianensis (Cetacea: Delphinidae), in Norte Bay contents of 18 Guiana dolphins stranded or accidentally caught by fishing around Norte Bay of Santa del delfín costero, Sotalia guianenSiS (Cetacea: Delphinidae), en la bahía Norte al sur de Brasil

  16. REPRODUCTIVE LONGEVITY OF DRIFTING KELP MACROCYSTIS PYRIFERA (PHAEOPHYCEAE) IN MONTEREY BAY, USA1

    E-Print Network [OSTI]

    California at Santa Cruz, University of

    REPRODUCTIVE LONGEVITY OF DRIFTING KELP MACROCYSTIS PYRIFERA (PHAEOPHYCEAE) IN MONTEREY BAY, USA1 index words: dispersal; drifting; germination; kelp; longevity; Macrocystis; Monterey Bay; rafts, especially for seaweeds (Norton 1992, Eckman 1996, Kinlan and Gaines 2003, Reed et al. 2006). The giant kelp

  17. Nitrogen sources and cycling in the San Francisco Bay Estuary: A nitrate dual isotopic composition approach

    E-Print Network [OSTI]

    Paytan, Adina

    as 25.0%) at the Sacramento­San Joaquin River delta region give rise to a wide range of d18ONO3 valuesNitrogen sources and cycling in the San Francisco Bay Estuary: A nitrate dual isotopic composition18O) within the estuarine system of San Francisco (SF) Bay, California, to explore the utility

  18. Optimal Pollution Mitigation in Monterey Bay Based on Coastal Radar Data and Nonlinear

    E-Print Network [OSTI]

    Marsden, Jerrold

    Optimal Pollution Mitigation in Monterey Bay Based on Coastal Radar Data and Nonlinear Dynamics run-off which is a typical source of pollution in the bay. We show that a HF radar-based pollution release scheme using this flow structure reduces the impact of pollution on the coastal envi- ronment

  19. MODELING PHYTOPLANKTON ABUNDANCE IN SAGINAW BAY, LAKE HURON: USING ARTIFICIAL NEURAL NETWORKS TO DISCERN FUNCTIONAL INFLUENCE

    E-Print Network [OSTI]

    MODELING PHYTOPLANKTON ABUNDANCE IN SAGINAW BAY, LAKE HURON: USING ARTIFICIAL NEURAL NETWORKS; phytoplankton Abbreviations: ANN, artificial neural network; ClŔ , chloride; DOC, dissolved organic carbon; Kd Phytoplankton abundance, as chl a, in Saginaw Bay, Lake Huron was modeled using arti- ficial neural networks

  20. The Catalytic Chemistry of HCN+NO over Na- and Ba-Y, FAU: An...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    The Catalytic Chemistry of HCN+NO over Na- and Ba-Y, FAU: An In Situ FTIR and TPDTPR Study. The Catalytic Chemistry of HCN+NO over Na- and Ba-Y, FAU: An In Situ FTIR and TPDTPR...

  1. Time Series Measurements of Temperature, Current Velocity, and Sediment Resuspension in Saginaw Bay

    E-Print Network [OSTI]

    Time Series Measurements of Temperature, Current Velocity, and Sediment Resuspension in Saginaw Bay and verification. These measurements will be made as part of this project. Measurements of sediment resuspension sediment resuspension in the bay during the spring. Measurements of sediment resuspension are important

  2. The influence of oceanic swell on flows over an estuarine intertidal mudflat in San Francisco Bay

    E-Print Network [OSTI]

    Talke, Stefan

    The influence of oceanic swell on flows over an estuarine intertidal mudflat in San Francisco Bay S mudflat. The observations indicate that long-period (10­20 s) ocean waves are a potentially important, we deployed an autonomous SonTek Hydra system on a mudflat in Central San Francisco Bay, and measured

  3. Final Report for Sea-level Rise Response Modeling for San Francisco Bay Estuary Tidal

    E-Print Network [OSTI]

    Fleskes, Joe

    i Final Report for Sea-level Rise Response Modeling for San Francisco Bay Estuary Tidal Marshes Refuge in northern San Francisco Bay, California. #12;iii Final Report for Sea-level Rise Response)................................................................... 7 Sea-level rise scenario model inputs

  4. Hydrodynamic models for San Francisco Bay: An overview of what we can model, when

    E-Print Network [OSTI]

    S SS Chla x/X2 z/h(x) #12;Models can influence policy: Mixing in the LSZ (1993) Dispersion via tidal shear in Suisun Bay (2D calculations by Jon Burau) #12;Current models: South Bay Salt Pond sediment average Thermal front near Dumbarton Bridge #12;More complicated models: Sediment transport in South SF

  5. Wastewater Discharge, Nutrient Loading, and Dissolved Oxygen Dynamics in a Shallow Texas Bay

    E-Print Network [OSTI]

    Schroer, Lee Allen

    2014-05-07T23:59:59.000Z

    In Oso Bay, a wastewater treatment plant acts as a source of eutrophication and may have measureable impact on the health of the bay. The objectives of this study were to create a model for modeling dissolved oxygen concentrations over time...

  6. Nuclear reactor control

    DOE Patents [OSTI]

    Cawley, William E. (Phoenix, AZ); Warnick, Robert F. (Pasco, WA)

    1982-01-01T23:59:59.000Z

    1. In a nuclear reactor incorporating a plurality of columns of tubular fuel elements disposed in horizontal tubes in a mass of graphite wherein water flows through the tubes to cool the fuel elements, the improvement comprising at least one control column disposed in a horizontal tube including fewer fuel elements than in a normal column of fuel elements and tubular control elements disposed at both ends of said control column, and means for varying the horizontal displacement of the control column comprising a winch at the upstream end of the control column and a cable extending through the fuel and control elements and attached to the element at the downstream end of the column.

  7. Nuclear reactor control apparatus

    DOE Patents [OSTI]

    Sridhar, Bettadapur N. (Cupertino, CA)

    1983-10-25T23:59:59.000Z

    Nuclear reactor safety rod release apparatus comprises a ring which carries detents normally positioned in an annular recess in outer side of the rod, the ring being held against the lower end of a drive shaft by magnetic force exerted by a solenoid carried by the drive shaft. When the solenoid is de-energized, the detent-carrying ring drops until the detents contact a cam surface associated with the lower end of the drive shaft, at which point the detents are cammed out of the recess in the safety rod to release the rod from the drive shaft. In preferred embodiments of the invention, an additional latch is provided to release a lower portion of a safety rod under conditions that may interfere with movement of the entire rod.

  8. Nuclear reactor control

    SciTech Connect (OSTI)

    Cawley, W.E.; Warnick, R.F.

    1982-03-30T23:59:59.000Z

    In a nuclear reactor incorporating a plurality of columns of tubular fuel elements disposed in horizontal tubes in a mass of graphite wherein water flows through the tubes to cool the fuel elements, the improvement comprising at least one control column disposed in a horizontal tube including fewer fuel elements than in a normal column of fuel elements and tubular control elements disposed at both ends of said control column, and means for varying the horizontal displacement of the control column comprising a winch at the upstream end of the control column and a cable extending through the fuel and control elements and attached to the element at the downstream end of the column.

  9. Please cite as: Boynton, W.R. 1998. Chesapeake Bay eutrophication Current status, historical trends, nutrient limitation

    E-Print Network [OSTI]

    Boynton, Walter R.

    Please cite as: Boynton, W.R. 1998. Chesapeake Bay eutrophication Current status, historical trends NUTRIENTS WORKSHOP CHESAPEAKE BAY EUTROPHICATION: CURRENT STATUS, HISTORICAL TRENDS, NUTRIENT LIMITATION summarizes a portion of the eutrophication history of Chesapeake Bay, a large coastal plain estuary

  10. Environmental links to interannual variability in shellfish toxicity in Cobscook Bay and eastern Maine, a strongly tidally mixed coastal region

    E-Print Network [OSTI]

    Townsend, David W.

    Environmental links to interannual variability in shellfish toxicity in Cobscook Bay and eastern e i n f o Keywords: Harmful algal blooms Gulf of Maine Cobscook Bay Shellfish toxicity a b s t r a c of Cobscook Bay, where strong tidal mixing tends to reduce seasonal variability in oceanographic properties

  11. On the circulation and tidal flushing of Mobile Bay, Alabama 

    E-Print Network [OSTI]

    Austin, George Belden

    1953-01-01T23:59:59.000Z

    is not filling with sediment to any apparent degree. The U. S. Corps of Engineers maintains ths Mobile Ship Channel to a depth of thirty-two feet. Dredging operations proceed during most of the year since this depth is some twenty-two f'eet below the mean bay... ~ ~ ~ ~ ix ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 ~ 4 6 9 10 E. Meteorological III. TIDAL FLUSHING THEORY 15 A. Ketchum's Tidal Prism Theory B. Stommel's and Arons' Ydxing Length Theory. of Tidal Flushing IV. THE HYDROGRAPHIC SURVEY 22 27 A. Planning B...

  12. Observations of remote and local forcing in Galveston Bay, Texas

    E-Print Network [OSTI]

    Guannel, Gregory

    2001-01-01T23:59:59.000Z

    OIISERVATIONS OF REMOTE AND LOCAL FORCINC IN CALVESTON BAY, TEXAS A Thesis by GREGORY GUANNEL Submitted to the Office ot Graduate Studies of Texas ARM University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE... conditions, and who supported me and helped me in the theoret&cal aspect of my research, as well as in thc professional aspect of my studies at Texas A&M University. I also would like to thank Dr. Edge for his help and support, and Dr. Nev, ton liar its...

  13. Geological oceanography of the Atchafalaya Bay area, Louisiana

    E-Print Network [OSTI]

    Thompson, Warren Charles

    1953-01-01T23:59:59.000Z

    off the river mouth, and 2. Mud-flat sediments on the coast west of Atchafalaya Bay to form the 7-mile-wide stretch of marshland which extends for 60 miles (Figure 3, p. 14). B. The contemporary rapid increase in discharge of the Atchafalaya River... area of the recently formed Atchafalaya River, and the site at which a great new river delta will eventually form. Engineering operations undertaken near the head of the Atchafalaya River in central Louisiana in the mid-19th century to open a...

  14. On the circulation and tidal flushing of Mobile Bay, Alabama

    E-Print Network [OSTI]

    Austin, George Belden

    1953-01-01T23:59:59.000Z

    . For each of the twenty-eight station positions, curves vere then drawn for temperature-depth and salinity&epth for the different ob- served tidal stages. From these curves temperature-depth sections (Figure V) and salinity-depth sections (Figures VI, VII...) vere oon- structed 1' or six cross-sections of Mobile Bay and for the ship channel length, for the different tidal stages. Current velocity vectors were plotted by station for surface and bottom at ebb and flood tidal stages. From these data surface...

  15. Bristol Bay Borough, Alaska: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnualProperty EditCalifornia:Power LP Biomass Facility Jump to: navigation, searchEnergyBristol Bay

  16. Clean Cities: East Bay Clean Cities coalition (Oakland)

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office511041clothAdvanced Materials Advanced. C o w l i t z CPlasma0 12Denver Metro Clean Cities CoalitionBay

  17. Kawela Bay, Hawaii: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are8COaBulkTransmissionSitingProcess.pdfGetecGtelInteriasIowa: EnergyKanabec County,Kaolin ADKaw ValleyKawela Bay,

  18. Palmetto Bay, Florida: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere I Geothermal Pwer PlantMunhall,Missouri:EnergyOssian, NewPalisades Park, New Jersey:Florida: EnergyPalmer,Bay,

  19. City of Bay City, Michigan (Utility Company) | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnual Siteof EnergyInnovationin Urban Transport |City of Ames,Barnesville, GeorgiaCity of Bay

  20. Half Moon Bay, California: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are8COaBulkTransmissionSitingProcess.pdfGetec AG| Open EnergyGuntersville ElectricControlon|Half Moon Bay, California:

  1. Morro Bay, California: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand Jump to: navigation, searchOfRose BendMiasole IncMinutemanVistaZephyr) JumpMorro Bay, California:

  2. Pedro Bay Village Council (Utility Company) | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnual SiteofEvaluatingGroup |JilinLuOpenNorthOlympiaAnalysis)Pearl River Valley El Pwr AssnPedro Bay

  3. South Bay, Florida: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghuraji Agro Industries Pvt LtdShawangunk, NewSingaporeSonix Japan Inc JumpBarrington ElectricBay, Florida:

  4. McKay Bay Facility Biomass Facility | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere I Geothermal Pwer Plant JumpMarysville, Ohio: Energy ResourcesMaviMcCullochMcGregor,McKay Bay Facility Biomass

  5. Mission Bay, Florida: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere I Geothermal Pwer Plant JumpMarysville, Ohio:Menomonee|MililaniMindanaoMinuanoIV Jump to:1980)Bay, Florida:

  6. Cutler Bay, Florida: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand JumpConceptual Model, clickInformationNew|CoreCpWingCushing, Maine: EnergySouthCutler Bay,

  7. Cold Bay Hot Spring Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnualProperty EditCalifornia:PowerCER.png El CER esDatasetCityFundCo-benefitsCoalogixfield |Cold Bay

  8. Nassau Bay, Texas: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere I Geothermal Pwer PlantMunhall, Pennsylvania: Energy ResourcesOceanNanostellar IncNaranja,Nashua,Bay, Texas:

  9. Bay County, Florida: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand Jump to:EzfeedflagBiomass Conversions IncBay County, Florida: Energy Resources Jump to: navigation,

  10. Bay County, Michigan: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand Jump to:EzfeedflagBiomass Conversions IncBay County, Florida: Energy Resources Jump to:Michigan:

  11. Bay Harbor Islands, Florida: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand Jump to:EzfeedflagBiomass Conversions IncBay County, Florida: Energy Resources Jump to:Michigan:Harbor

  12. Bay Head, New Jersey: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand Jump to:EzfeedflagBiomass Conversions IncBay County, Florida: Energy Resources Jump

  13. Bay Hill, Florida: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand Jump to:EzfeedflagBiomass Conversions IncBay County, Florida: Energy Resources JumpHill, Florida:

  14. Bay Lake, Florida: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand Jump to:EzfeedflagBiomass Conversions IncBay County, Florida: Energy Resources JumpHill, Florida:Lake,

  15. Bay Point, California: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

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  16. Bay Shore, New York: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

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  17. Bay View, Ohio: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

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  18. Bay Village, Ohio: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

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  19. Runaway Bay, Texas: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

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  20. Galveston Bay Biodiesel LP GBB | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are8COaBulkTransmissionSitingProcess.pdf Jump1946865°,Park, Texas: Energy Resources Jump to:GallantGalliaGalveston Bay

  1. United States Domestic Research Reactor Infrastrucutre TRIGA Reactor Fuel Support

    SciTech Connect (OSTI)

    Douglas Morrell

    2011-03-01T23:59:59.000Z

    The United State Domestic Research Reactor Infrastructure Program at the Idaho National Laboratory manages and provides project management, technical, quality engineering, quality inspection and nuclear material support for the United States Department of Energy sponsored University Reactor Fuels Program. This program provides fresh, unirradiated nuclear fuel to Domestic University Research Reactor Facilities and is responsible for the return of the DOE-owned, irradiated nuclear fuel over the life of the program. This presentation will introduce the program management team, the universities supported by the program, the status of the program and focus on the return process of irradiated nuclear fuel for long term storage at DOE managed receipt facilities. It will include lessons learned from research reactor facilities that have successfully shipped spent fuel elements to DOE receipt facilities.

  2. Reactor protection system design alternatives for sodium fast reactors

    E-Print Network [OSTI]

    DeWitte, Jacob D. (Jacob Dominic)

    2011-01-01T23:59:59.000Z

    Historically, unprotected transients have been viewed as design basis events that can significantly challenge sodium-cooled fast reactors. The perceived potential consequences of a severe unprotected transient in a ...

  3. Reactor physics design of supercritical CO?-cooled fast reactors

    E-Print Network [OSTI]

    Pope, Michael A. (Michael Alexander)

    2004-01-01T23:59:59.000Z

    Gas-Cooled Fast Reactors (GFRs) are among the GEN-IV designs proposed for future deployment. Driven by anticipated plant cost reduction, the use of supercritical CO? (S-CO?) as a Brayton cycle working fluid in a direct ...

  4. Nuclear reactor downcomer flow deflector

    DOE Patents [OSTI]

    Gilmore, Charles B. (Greensburg, PA); Altman, David A. (Pittsburgh, PA); Singleton, Norman R. (Murrysville, PA)

    2011-02-15T23:59:59.000Z

    A nuclear reactor having a coolant flow deflector secured to a reactor core barrel in line with a coolant inlet nozzle. The flow deflector redirects incoming coolant down an annulus between the core barrel and the reactor vessel. The deflector has a main body with a front side facing the fluid inlet nozzle and a rear side facing the core barrel. The rear side of the main body has at least one protrusion secured to the core barrel so that a gap exists between the rear side of the main body adjacent the protrusion and the core barrel. Preferably, the protrusion is a relief that circumscribes the rear side of the main body.

  5. 2012 Annual Report Research Reactor Infrastructure Program

    SciTech Connect (OSTI)

    Douglas Morrell

    2012-11-01T23:59:59.000Z

    The content of this report is the 2012 Annual Report for the Research Reactor Infrastructure Program.

  6. How far is a Fusion Power Reactor from an Experimental Reactor?

    E-Print Network [OSTI]

    1 How far is a Fusion Power Reactor from an Experimental Reactor? R. Toschi(1) , P. Barabaschi(2 September 2000 Madrid, Spain #12;2 How far is a fusion power reactor from an experimental reactor? R. Toschi To support a request of very substantial resources to build and operate an experimental reactor such as ITER

  7. Evaluation of older bay mud sediment from Richmond Harbor, California

    SciTech Connect (OSTI)

    Pinza, M.R.; Mayhew, H.L.; Word, J.Q.

    1996-09-01T23:59:59.000Z

    The older, bay mud (OBM) unit predates modem man and could act as a barrier to the downward transport of contaminants from the younger bay mud (YBM) because of its hard-packed consistency. However, its chemical and biological nature have not been well characterized. Battelle/Marine Sciences Laboratory (MSL) conducted three independent studies of OBM sediment in January 1993, January 1994, and October 1994. These studies evaluated potential chemical contamination and biological effects of OBM that could occur as a result of dredging and disposal activities. These evaluations were performed by conducting chemical analysis, solid-phase toxicity tests, suspended- particulate-phase (SPP) toxicity tests, and bioaccumulation tests on the OBM sediment. If the sediment chemistry and toxicity results showed no or minimal contamination and toxicological responses, then either the OBM could be left exposed in Richmond Harbor after dredging the YBM without leaving a source of contamination, or if the project depths necessitate, the OBM would be acceptable for disposal at an appropriate disposal site.

  8. Distribution ICategory: General Reactor Technology

    E-Print Network [OSTI]

    Shlyakhter, Ilya

    --- Distribution ICategory: General Reactor Technology (UC-520) ANl-92/23 AR(;ONNE NATIONAL, progressively by Huygens, Maxwell and Roentgen, mankind has learned to observe it, measure it, control it

  9. Spectral shift reactor control method

    SciTech Connect (OSTI)

    Impink, A.J. Jr.

    1987-08-18T23:59:59.000Z

    The method is described of closely controlling the reactor water coolant temperature of an operating spectral-shift nuclear reactor, the reactor comprising a core formed of fuel assemblies through which the reactor water coolant flows; different types of elongated elements operable to be controllably moved into and out of the core; one type of the elongated elements comprising control rods formed of neutron absorbing material and operable to decrease reactivity through neutron absorption when inserted into the core; another of the types of elongated elements comprising displacer rods formed of material which has a low absorption for neutrons and which have overall neutron-absorbing and moderating characteristics essentially not exceeding those of hollow tubular Zircaloy members with a filling zirconium oxide or aluminum oxide, the displacer rods operating to displace an equivalent volume of water coolant fluid from the core when inserted therein to decrease reactivity and to increase reactivity when moved from the core.

  10. University Reactor Matching Grants Program

    SciTech Connect (OSTI)

    John Valentine; Farzad Rahnema; Said Abdel-Khalik

    2003-02-14T23:59:59.000Z

    During the 2002 Fiscal year, funds from the DOE matching grant program, along with matching funds from the industrial sponsors, have been used to support research in the area of thermal-hydraulics. Both experimental and numerical research projects have been performed. Experimental research focused on two areas: (1) Identification of the root cause mechanism for axial offset anomaly in pressurized water reactors under prototypical reactor conditions, and (2) Fluid dynamic aspects of thin liquid film protection schemes for inertial fusion reactor chambers. Numerical research focused on two areas: (1) Multi-fluid modeling of both two-phase and two-component flows for steam conditioning and mist cooling applications, and (2) Modeling of bounded Rayleigh-Taylor instability with interfacial mass transfer and fluid injection through a porous wall simulating the ''wetted wall'' protection scheme in inertial fusion reactor chambers. Details of activities in these areas are given.

  11. Reactor physics project final report

    E-Print Network [OSTI]

    Driscoll, Michael J.

    1970-01-01T23:59:59.000Z

    This is the final report in an experimental and theoretical program to develop and apply single- and few-element methods for the determination of reactor lattice parameters. The period covered by the report is January 1, ...

  12. Combustion synthesis continuous flow reactor

    DOE Patents [OSTI]

    Maupin, G.D.; Chick, L.A.; Kurosky, R.P.

    1998-01-06T23:59:59.000Z

    The present invention is a reactor for combustion synthesis of inorganic powders. The reactor includes a reaction vessel having a length and a first end and a second end. The reaction vessel further has a solution inlet and a carrier gas inlet. The reactor further has a heater for heating both the solution and the carrier gas. In a preferred embodiment, the reaction vessel is heated and the solution is in contact with the heated reaction vessel. It is further preferred that the reaction vessel be cylindrical and that the carrier gas is introduced tangentially into the reaction vessel so that the solution flows helically along the interior wall of the reaction vessel. As the solution evaporates and combustion produces inorganic material powder, the carrier gas entrains the powder and carries it out of the reactor. 10 figs.

  13. Advanced Catalytic Hydrogenation Retrofit Reactor

    SciTech Connect (OSTI)

    Reinaldo M. Machado

    2002-08-15T23:59:59.000Z

    Industrial hydrogenation is often performed using a slurry catalyst in large stirred-tank reactors. These systems are inherently problematic in a number of areas, including industrial hygiene, process safety, environmental contamination, waste production, process operability and productivity. This program proposed the development of a practical replacement for the slurry catalysts using a novel fixed-bed monolith catalyst reactor, which could be retrofitted onto an existing stirred-tank reactor and would mitigate many of the minitations and problems associated with slurry catalysts. The full retrofit monolith system, consisting of a recirculation pump, gas/liquid ejector and monolith catalyst, is described as a monolith loop reactor or MLR. The MLR technology can reduce waste and increase raw material efficiency, which reduces the overall energy required to produce specialty and fine chemicals.

  14. Teaching About Nature's Nuclear Reactors

    E-Print Network [OSTI]

    Herndon, J M

    2005-01-01T23:59:59.000Z

    Naturally occurring nuclear reactors existed in uranium deposits on Earth long before Enrico Fermi built the first man-made nuclear reactor beneath Staggs Field in 1942. In the story of their discovery, there are important lessons to be learned about scientific inquiry and scientific discovery. Now, there is evidence to suggest that the Earth's magnetic field and Jupiter's atmospheric turbulence are driven by planetary-scale nuclear reactors. The subject of planetocentric nuclear fission reactors can be a jumping off point for stimulating classroom discussions about the nature and implications of planetary energy sources and about the geomagnetic field. But more importantly, the subject can help to bring into focus the importance of discussing, debating, and challenging current thinking in a variety of areas.

  15. Nuclear Reactors and Technology; (USA)

    SciTech Connect (OSTI)

    Cason, D.L.; Hicks, S.C. (eds.)

    1991-01-01T23:59:59.000Z

    Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database (EDB) during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency's Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on EDB and Nuclear Science Abstracts (NSA) database. Current information, added daily to EDB, is available to DOE and its contractors through the DOE integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user's needs.

  16. Reactor core isolation cooling system

    DOE Patents [OSTI]

    Cooke, Franklin E. (San Jose, CA)

    1992-01-01T23:59:59.000Z

    A reactor core isolation cooling system includes a reactor pressure vessel containing a reactor core, a drywell vessel, a containment vessel, and an isolation pool containing an isolation condenser. A turbine is operatively joined to the pressure vessel outlet steamline and powers a pump operatively joined to the pressure vessel feedwater line. In operation, steam from the pressure vessel powers the turbine which in turn powers the pump to pump makeup water from a pool to the feedwater line into the pressure vessel for maintaining water level over the reactor core. Steam discharged from the turbine is channeled to the isolation condenser and is condensed therein. The resulting heat is discharged into the isolation pool and vented to the atmosphere outside the containment vessel for removing heat therefrom.

  17. Reactor core isolation cooling system

    DOE Patents [OSTI]

    Cooke, F.E.

    1992-12-08T23:59:59.000Z

    A reactor core isolation cooling system includes a reactor pressure vessel containing a reactor core, a drywell vessel, a containment vessel, and an isolation pool containing an isolation condenser. A turbine is operatively joined to the pressure vessel outlet steamline and powers a pump operatively joined to the pressure vessel feedwater line. In operation, steam from the pressure vessel powers the turbine which in turn powers the pump to pump makeup water from a pool to the feedwater line into the pressure vessel for maintaining water level over the reactor core. Steam discharged from the turbine is channeled to the isolation condenser and is condensed therein. The resulting heat is discharged into the isolation pool and vented to the atmosphere outside the containment vessel for removing heat therefrom. 1 figure.

  18. Interfacial effects in fast reactors

    E-Print Network [OSTI]

    Saidi, Mohammad Said

    1979-01-01T23:59:59.000Z

    The problem of increased resonance capture rates near zone interfaces in fast reactor media has been examined both theoretically and experimentally. An interface traversing assembly was designed, constructed and employed ...

  19. User's guide for BAYES: a general-purpose computer code for fitting a functional form to experimental data

    SciTech Connect (OSTI)

    Larson, N M

    1982-08-01T23:59:59.000Z

    This report is intended as a user's manual for a general-purpose computer program BAYES to solve Bayes equations for updating parameter values, uncertainties, and correlations. Bayes equations are derived from Bayes theorem, using linearity and normality assumptions. The method of solution is described, and details are given for adapting the code for a specific purpose. Numerous examples are given, including problem description and solution method, FORTRAN coding, and sample input and output. A companion code LEAST, which solves the usual least-squares equations rather than Bayes equations but which encourages nondiagonal data weighting, is also described.

  20. Solid State Reactor Final Report

    SciTech Connect (OSTI)

    Mays, G.T.

    2004-03-10T23:59:59.000Z

    The Solid State Reactor (SSR) is an advanced reactor concept designed to take advantage of Oak Ridge National Laboratory's (ORNL's) recently developed graphite foam that has enhanced heat transfer characteristics and excellent high-temperature mechanical properties, to provide an inherently safe, self-regulated, source of heat for power and other potential applications. This work was funded by the U.S. Department of Energy's Nuclear Energy Research Initiative (NERI) program (Project No. 99-064) from August 1999 through September 30, 2002. The initial concept of utilizing the graphite foam as a basis for developing an advanced reactor concept envisioned that a suite of reactor configurations and power levels could be developed for several different applications. The initial focus was looking at the reactor as a heat source that was scalable, independent of any heat removal/power conversion process. These applications might include conventional power generation, isotope production and destruction (actinides), and hydrogen production. Having conducted the initial research on the graphite foam and having performed the scoping parametric analyses from neutronics and thermal-hydraulic perspectives, it was necessary to focus on a particular application that would (1) demonstrate the viability of the overall concept and (2) require a reasonably structured design analysis process that would synthesize those important parameters that influence the concept the most as part of a feasible, working reactor system. Thus, the application targeted for this concept was supplying power for remote/harsh environments and a design that was easily deployable, simplistic from an operational standpoint, and utilized the new graphite foam. Specifically, a 500-kW(t) reactor concept was pursued that is naturally load following, inherently safe, optimized via neutronic studies to achieve near-zero reactivity change with burnup, and proliferation resistant. These four major areas of research were undertaken: (1) establishing the design and safety-related basis via neutronic and reactor control assessments with the graphite foam as heat transfer medium; (2) evaluating the thermal performance of the graphite foam for heat removal, reactor stability, reactor operations, and overall core thermal characteristics; (3) characterizing the physical properties of the graphite foam under normal and irradiated conditions to determine any effects on structure, dimensional stability, thermal conductivity, and thermal expansion; and (4) developing a power conversion system design to match the reactor operating parameters.

  1. Alternate-fuel reactor studies

    SciTech Connect (OSTI)

    Evans, K. Jr.; Ehst, D.A.; Gohar, Y.; Jung, J.; Mattas, R.F.; Turner, L.R.

    1983-02-01T23:59:59.000Z

    A number of studies related to improvements and/or greater understanding of alternate-fueled reactors is presented. These studies cover the areas of non-Maxwellian distributions, materials and lifetime analysis, a /sup 3/He-breeding blanket, tritium-rich startup effects, high field magnet support, and reactor operation spanning the range from full D-T operation to operation with no tritium breeding.

  2. Automatic safety rod for reactors

    DOE Patents [OSTI]

    Germer, John H. (San Jose, CA)

    1988-01-01T23:59:59.000Z

    An automatic safety rod for a nuclear reactor containing neutron absorbing material and designed to be inserted into a reactor core after a loss-of-core flow. Actuation is based upon either a sudden decrease in core pressure drop or the pressure drop decreases below a predetermined minimum value. The automatic control rod includes a pressure regulating device whereby a controlled decrease in operating pressure due to reduced coolant flow does not cause the rod to drop into the core.

  3. Fast quench reactor and method

    DOE Patents [OSTI]

    Detering, Brent A. (Idaho Falls, ID); Donaldson, Alan D. (Idaho Falls, ID); Fincke, James R. (Idaho Falls, ID); Kong, Peter C. (Idaho Falls, ID)

    1998-01-01T23:59:59.000Z

    A fast quench reaction includes a reactor chamber having a high temperature heating means such as a plasma torch at its inlet and a restrictive convergent-divergent nozzle at its outlet end. Reactants are injected into the reactor chamber. The resulting heated gaseous stream is then rapidly cooled by passage through the nozzle. This "freezes" the desired end product(s) in the heated equilibrium reaction stage.

  4. Propellant actuated nuclear reactor steam depressurization valve

    DOE Patents [OSTI]

    Ehrke, Alan C. (San Jose, CA); Knepp, John B. (San Jose, CA); Skoda, George I. (Santa Clara, CA)

    1992-01-01T23:59:59.000Z

    A nuclear fission reactor combined with a propellant actuated depressurization and/or water injection valve is disclosed. The depressurization valve releases pressure from a water cooled, steam producing nuclear reactor when required to insure the safety of the reactor. Depressurization of the reactor pressure vessel enables gravity feeding of supplementary coolant water through the water injection valve to the reactor pressure vessel to prevent damage to the fuel core.

  5. When Do Commercial Reactors Permanently Shut Down?

    Reports and Publications (EIA)

    2011-01-01T23:59:59.000Z

    For those wishing to obtain current data, the following resources are available: U.S. reactors, go to the Energy Information Administration's nuclear reactor shutdown list. (Note: As of April 30, 2010, the last U.S. reactor to permanently shut down was Big Rock Point in 1997.) Foreign Reactors, go to the Power Reactor Information System (PRIS) on the International Atomic Energy Agency's website.

  6. Nuclear reactor control rod

    SciTech Connect (OSTI)

    Cearley, J.E.; Izzo, K.R.

    1987-06-30T23:59:59.000Z

    This patent describes a vertically oriented bottom entry control rod from a nuclear reactor: a frame including an elongated central spine of cruciform cross section connected between an upper support member and a lower support member both of cruciform shape having four laterally extending arms. The arms are in alignment with the arms of the lower support member and each aligned upper and lower support members has a sheath extending between; absorber plates of neutron absorber material, different from the material of the frame, one of the absorber plates is positioned within a sheath beneath each of the arms; attachment means suspends the absorber plates from the arms of the upper support member within a sheath; elongated absorber members positioned within a sheath between each of the suspended absorber plates and an arm of the lower support member; and joint means between the upper ends of the absorber members and the lower ends of the suspended absorber plates for minimizing gaps; the sheath means encloses the suspended absorber plates and the absorber members extending between aligned arms of the upper and lower support members and secured.

  7. Reactor pressure vessel nozzle

    DOE Patents [OSTI]

    Challberg, R.C.; Upton, H.A.

    1994-10-04T23:59:59.000Z

    A nozzle for joining a pool of water to a nuclear reactor pressure vessel includes a tubular body having a proximal end joinable to the pressure vessel and a distal end joinable in flow communication with the pool. The body includes a flow passage therethrough having in serial flow communication a first port at the distal end, a throat spaced axially from the first port, a conical channel extending axially from the throat, and a second port at the proximal end which is joinable in flow communication with the pressure vessel. The inner diameter of the flow passage decreases from the first port to the throat and then increases along the conical channel to the second port. In this way, the conical channel acts as a diverging channel or diffuser in the forward flow direction from the first port to the second port for recovering pressure due to the flow restriction provided by the throat. In the backflow direction from the second port to the first port, the conical channel is a converging channel and with the abrupt increase in flow area from the throat to the first port collectively increase resistance to flow therethrough. 2 figs.

  8. Reactor shroud joint

    DOE Patents [OSTI]

    Ballas, G.J.; Fife, A.B.; Ganz, I.

    1998-04-07T23:59:59.000Z

    A shroud for a nuclear reactor is described. In one embodiment, the shroud includes first and second shroud sections, and each shroud section includes a substantially cylindrical main body having a first end and a second end. With respect to each shroud section, a flange is located at the main body first end, and the flange has a plurality of bolt openings therein and a plurality of scalloped regions. The first shroud section is welded to the second shroud section, and at least some of the bolt openings in the first shroud section flange align with respective bolt openings in the second shroud section flange. In the event that the onset of inter-granular stress corrosion cracking is ever detected in the weld between the shroud section, bolts are inserted through bolt openings in the first shroud section flange and through aligned bolt openings the second shroud section flange. Each bolt, in one embodiment, has a shank section and first and second threaded end sections. Nuts are threadedly engaged to the threaded end sections and tightened against the respective flanges. 4 figs.

  9. Solar solids reactor

    DOE Patents [OSTI]

    Yudow, B.D.

    1986-02-24T23:59:59.000Z

    A solar powered kiln is provided, that is of relatively simple design and which efficiently uses solar energy. The kiln or solids reactor includes a stationary chamber with a rearward end which receives solid material to be reacted and a forward end through which reacted material is disposed of, and a screw conveyor extending along the bottom of the chamber for slowly advancing the material between the chamber ends. Concentrated solar energy is directed to an aperture at the forward end of the chamber to heat the solid material moving along the bottom of the chamber. The solar energy can be reflected from a mirror facing at an upward incline, through the aperture and against a heat-absorbing material near the top of the chamber, which moves towards the rear of the chamber to distribute heat throughout the chamber. Pumps at the forward and rearward ends of the chamber pump heated sweep gas through the length of the chamber, while minimizing the flow of gas through an open aperture through which concentrated sunlight is received.

  10. Solar solids reactor

    DOE Patents [OSTI]

    Yudow, Bernard D. (Chicago, IL)

    1987-01-01T23:59:59.000Z

    A solar powered kiln is provided, that is of relatively simple design and which efficiently uses solar energy. The kiln or solids reactor includes a stationary chamber with a rearward end which receives solid material to be reacted and a forward end through which reacted material is disposed of, and a screw conveyor extending along the bottom of the chamber for slowly advancing the material between the chamber ends. Concentrated solar energy is directed to an aperture at the forward end of the chamber to heat the solid material moving along the bottom of the chamber. The solar energy can be reflected from a mirror facing at an upward incline, through the aperture and against a heat-absorbing material near the top of the chamber, which moves towards the rear of the chamber to distribute heat throughout the chamber. Pumps at the forward and rearward ends of the chamber pump heated sweep gas through the length of the chamber, while minimizing the flow of gas through an open aperture through which concentrated sunlight is received.

  11. Novel Catalytic Membrane Reactors

    SciTech Connect (OSTI)

    Stuart Nemser, PhD

    2010-10-01T23:59:59.000Z

    There are many industrial catalytic organic reversible reactions with amines or alcohols that have water as one of the products. Many of these reactions are homogeneously catalyzed. In all cases removal of water facilitates the reaction and produces more of the desired chemical product. By shifting the reaction to right we produce more chemical product with little or no additional capital investment. Many of these reactions can also relate to bioprocesses. Given the large number of water-organic compound separations achievable and the ability of the Compact Membrane Systems, Inc. (CMS) perfluoro membranes to withstand these harsh operating conditions, this is an ideal demonstration system for the water-of-reaction removal using a membrane reactor. Enhanced reaction synthesis is consistent with the DOE objective to lower the energy intensity of U.S. industry 25% by 2017 in accord with the Energy Policy Act of 2005 and to improve the United States manufacturing competitiveness. The objective of this program is to develop the platform technology for enhancing homogeneous catalytic chemical syntheses.

  12. Commencement Bay cumulative impact study: Historic review of special aquatic sites

    SciTech Connect (OSTI)

    Not Available

    1991-05-04T23:59:59.000Z

    The Commencement Bay Nearshore/Tideflats area, of which Commencement Bay is a part, has been designated by the Environmental Protection Agency as a Superfund site. Development in and around Commencement Bay have resulted in significant shoreline alterations, loss of substantial aquatic, mudflat and delta wetland habitat, and degradation of water quality. Dredging of nearshore areas to support port and harbor facilities for the Port of Tacoma has been carried out since the turn of the century by public and private industry. Areas south of the waterways have been diked, filled, and channelized for construction of storage buildings, shipping facilities, and various commercial and industrial purposes. Continued development pressures, maintenance dredging, and other activities necessitate an evaluation of the cumulative impacts of such activities on the remaining aquatic sites of Commencement Bay. Various resource agency and tribal recommendations resulted in the Commencement Bay Cumulative Impact Study, which was designed to produce the most complete historic record documenting loss of special aquatic sites. The baseline information will be used to quantify the cumulative impacts beginning in the mid-1800's through 1941 as a management tool. Commencement Bay is generally defined as a geographic region of south Puget Sound in Washington State extending from Brown's Point to Point Defiance. It provides a natural harbor for ships because there are no bars or other obstructions at the entrance to the bay.

  13. Neutrino oscillations refitted

    E-Print Network [OSTI]

    Forero, D V; Valle, J W F

    2014-01-01T23:59:59.000Z

    Here we update our previous global fit of neutrino oscillations by including the recent results which have appeared since the Neutrino-2012 conference. These include the measurements of reactor anti-neutrino disappearance reported by Daya Bay and RENO, together with latest T2K and MINOS data including both disappearance and appearance channels. We also include the revised results from the third solar phase of Super-Kamiokande, SK-III, as well as new solar results from the fourth phase of Super-Kamiokande, SK-IV. We find that the preferred global determination of the atmospheric angle $\\theta_{23}$ is consistent with maximal mixing. We also determine the impact of the new data upon all the other neutrino oscillation parameters with emphasis on the increasing sensitivity to the CP phase, thanks to the interplay between accelerator and reactor data.

  14. Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation

    E-Print Network [OSTI]

    Heidet, Florent

    2010-01-01T23:59:59.000Z

    selected as part of the Generation IV reactors .. - 4 -The development of Generation IV fast reactors can make aconcepts selected for the Generation IV reactors, three,

  15. Uncertainties in the Anti-neutrino Production at Nuclear Reactors

    E-Print Network [OSTI]

    Djurcic, Zelimir

    2009-01-01T23:59:59.000Z

    neutrino Production at Nuclear Reactors Z. Djurcic 1 , ?emission rates from nuclear reactors are determined fromlarge commercial nuclear reactors are playing an important

  16. Incorporation of Hydride Nuclear Fuels in Commercial Light Water Reactors

    E-Print Network [OSTI]

    Terrani, Kurt Amir

    2010-01-01T23:59:59.000Z

    Fundamental aspects of nuclear reactor fuel elements.Unlike permanent nuclear reactor core components, nuclearof the first nuclear reactors, commercial nuclear fuel still

  17. PIA - Advanced Test Reactor National Scientific User Facility...

    Energy Savers [EERE]

    Advanced Test Reactor National Scientific User Facility Users Week 2009 PIA - Advanced Test Reactor National Scientific User Facility Users Week 2009 PIA - Advanced Test Reactor...

  18. acid immunoaffinity reactor: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    sludge blanket reactors (more) Ning, Zuojun. 2009-01-01 8 Inexpensive Mini Thermonuclear Reactor CiteSeer Summary: This proposed design for a mini thermonuclear reactor...

  19. MULTIPHASE REACTOR MODELING FOR ZINC CHLORIDE CATALYZED COAL LIQUEFACTION

    E-Print Network [OSTI]

    Joyce, Peter James

    2011-01-01T23:59:59.000Z

    II. c. High Yield Batch Reactor Results. . . • .Objectives •. Slurry Reactors . . . . . . .A. StudiesSystems. D. Slurry Reactor Theory. General. . Application to

  20. Development of a Hydrodynamic and Transport model of Bellingham Bay in Support of Nearshore Habitat Restoration

    SciTech Connect (OSTI)

    Wang, Taiping; Yang, Zhaoqing; Khangaonkar, Tarang

    2010-04-22T23:59:59.000Z

    In this study, a hydrodynamic model based on the unstructured-grid finite volume coastal ocean model (FVCOM) was developed for Bellingham Bay, Washington. The model simulates water surface elevation, velocity, temperature, and salinity in a three-dimensional domain that covers the entire Bellingham Bay and adjacent water bodies, including Lummi Bay, Samish Bay, Padilla Bay, and Rosario Strait. The model was developed using Pacific Northwest National Laboratory’s high-resolution Puget Sound and Northwest Straits circulation and transport model. A sub-model grid for Bellingham Bay and adjacent coastal waters was extracted from the Puget Sound model and refined in Bellingham Bay using bathymetric light detection and ranging (LIDAR) and river channel cross-section data. The model uses tides, river inflows, and meteorological inputs to predict water surface elevations, currents, salinity, and temperature. A tidal open boundary condition was specified using standard National Oceanic and Atmospheric Administration (NOAA) predictions. Temperature and salinity open boundary conditions were specified based on observed data. Meteorological forcing (wind, solar radiation, and net surface heat flux) was obtained from NOAA real observations and National Center for Environmental Prediction North American Regional Analysis outputs. The model was run in parallel with 48 cores using a time step of 2.5 seconds. It took 18 hours of cpu time to complete 26 days of simulation. The model was calibrated with oceanographic field data for the period of 6/1/2009 to 6/26/2009. These data were collected specifically for the purpose of model development and calibration. They include time series of water-surface elevation, currents, temperature, and salinity as well as temperature and salinity profiles during instrument deployment and retrieval. Comparisons between model predictions and field observations show an overall reasonable agreement in both temporal and spatial scales. Comparisons of root mean square error values for surface elevation, velocity, temperature, and salinity time series are 0.11 m, 0.10 m/s, 1.28oC, and 1.91 ppt, respectively. The model was able to reproduce the salinity and temperature stratifications inside Bellingham Bay. Wetting and drying processes in tidal flats in Bellingham Bay, Samish Bay, and Padilla Bay were also successfully simulated. Both model results and observed data indicated that water surface elevations inside Bellingham Bay are highly correlated to tides. Circulation inside the bay is weak and complex and is affected by various forcing mechanisms, including tides, winds, freshwater inflows, and other local forcing factors. The Bellingham Bay model solution was successfully linked to the NOAA oil spill trajectory simulation model “General NOAA Operational Modeling Environment (GNOME).” Overall, the Bellingham Bay model has been calibrated reasonably well and can be used to provide detailed hydrodynamic information in the bay and adjacent water bodies. While there is room for further improvement with more available data, the calibrated hydrodynamic model provides useful hydrodynamic information in Bellingham Bay and can be used to support sediment transport and water quality modeling as well as assist in the design of nearshore restoration scenarios.

  1. Mercury-contaminated sludge treatment by dredging in Minamata Bay

    SciTech Connect (OSTI)

    Yoshinaga, Kiyoto [Ministry of Transport, Niigata (Japan)

    1995-12-31T23:59:59.000Z

    To eradicate Minamata Disease, caused by the discharge of sewage containing methyl mercury and its accumulation in fish and shellfish through the food cycle, a large-scale sediment disposal project was conducted with special care taken to prevent new pollution resulting from the project itself. The basic approach to sediment disposal was to construct a highly watertight revetment to reclaim the inner area of the bay and then confine sediment dredged from the remaining contaminated area in the reclamation area through surface treatment. Before sediment disposal, boundary nets were installed to enclose the work area to prevent the mixing of contaminated and noncontaminated fish. Dredging work was successfully carried out by using four cutterless suction dredgers, newly developed in advance for minimizing resuspension of sediments. Dredged material was discharged into the reclamation area, filled up to sea level, and covered with a sandproof membrane, lightweight volcanic ash earth, and mountain soil.

  2. International Research Reactor Decommissioning Project

    SciTech Connect (OSTI)

    Leopando, Leonardo [Philippine Nuclear Research Institute, Quezon City (Philippines); Warnecke, Ernst [International Atomic Energy Agency, Vienna (Austria)

    2008-01-15T23:59:59.000Z

    Many research reactors have been or will be shut down and are candidates for decommissioning. Most of the respective countries neither have a decommissioning policy nor the required expertise and funds to effectively implement a decommissioning project. The IAEA established the Research Reactor Decommissioning Demonstration Project (R{sup 2}D{sup 2}P) to help answer this need. It was agreed to involve the Philippine Research Reactor (PRR-1) as model reactor to demonstrate 'hands-on' experience as it is just starting the decommissioning process. Other facilities may be included in the project as they fit into the scope of R{sup 2}D{sup 2}P and complement to the PRR-1 decommissioning activities. The key outcome of the R{sup 2}D{sup 2}P will be the decommissioning of the PRR-1 reactor. On the way to this final goal the preparation of safety related documents (i.e., decommissioning plan, environmental impact assessment, safety analysis report, health and safety plan, cost estimate, etc.) and the licensing process as well as the actual dismantling activities could provide a model to other countries involved in the project. It is expected that the R{sup 2}D{sup 2}P would initiate activities related to planning and funding of decommissioning activities in the participating countries if that has not yet been done.

  3. Rapid starting methanol reactor system

    DOE Patents [OSTI]

    Chludzinski, Paul J. (38 Berkshire St., Swampscott, MA 01907); Dantowitz, Philip (39 Nancy Ave., Peabody, MA 01960); McElroy, James F. (12 Old Cart Rd., Hamilton, MA 01936)

    1984-01-01T23:59:59.000Z

    The invention relates to a methanol-to-hydrogen cracking reactor for use with a fuel cell vehicular power plant. The system is particularly designed for rapid start-up of the catalytic methanol cracking reactor after an extended shut-down period, i.e., after the vehicular fuel cell power plant has been inoperative overnight. Rapid system start-up is accomplished by a combination of direct and indirect heating of the cracking catalyst. Initially, liquid methanol is burned with a stoichiometric or slightly lean air mixture in the combustion chamber of the reactor assembly. The hot combustion gas travels down a flue gas chamber in heat exchange relationship with the catalytic cracking chamber transferring heat across the catalyst chamber wall to heat the catalyst indirectly. The combustion gas is then diverted back through the catalyst bed to heat the catalyst pellets directly. When the cracking reactor temperature reaches operating temperature, methanol combustion is stopped and a hot gas valve is switched to route the flue gas overboard, with methanol being fed directly to the catalytic cracking reactor. Thereafter, the burner operates on excess hydrogen from the fuel cells.

  4. Imaging Fukushima Daiichi reactors with muons

    SciTech Connect (OSTI)

    Miyadera, Haruo; Borozdin, Konstantin N.; Greene, Steve J.; Milner, Edward C.; Morris, Christopher L. [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Lukic, Zarija [Computational Cosmology Center, Lawrence Berkeley National Laboratory, Berkeley, CA 94720 (United States); Masuda, Koji [University of New Mexico, Albuquerque, NM 87131 (United States); Perry, John O. [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); University of New Mexico, Albuquerque, NM 87131 (United States)

    2013-05-15T23:59:59.000Z

    A study of imaging the Fukushima Daiichi reactors with cosmic-ray muons to assess the damage to the reactors is presented. Muon scattering imaging has high sensitivity for detecting uranium fuel and debris even through thick concrete walls and a reactor pressure vessel. Technical demonstrations using a reactor mockup, detector radiation test at Fukushima Daiichi, and simulation studies have been carried out. These studies establish feasibility for the reactor imaging. A few months of measurement will reveal the spatial distribution of the reactor fuel. The muon scattering technique would be the best and probably the only way for Fukushima Daiichi to make this determination in the near future.

  5. Surface Currents and Winds at the Delaware Bay Mouth

    SciTech Connect (OSTI)

    Muscarella, P A; Barton, N P; Lipphardt, B L; Veron, D E; Wong, K C; Kirwan, A D

    2011-04-06T23:59:59.000Z

    Knowledge of the circulation of estuaries and adjacent shelf waters has relied on hydrographic measurements, moorings, and local wind observations usually removed from the region of interest. Although these observations are certainly sufficient to identify major characteristics, they lack both spatial resolution and temporal coverage. High resolution synoptic observations are required to identify important coastal processes at smaller scales. Long observation periods are needed to properly sample low-frequency processes that may also be important. The introduction of high-frequency (HF) radar measurements and regional wind models for coastal studies is changing this situation. Here we analyze synoptic, high-resolution surface winds and currents in the Delaware Bay mouth over an eight-month period (October 2007 through May 2008). The surface currents were measured by two high-frequency radars while the surface winds were extracted from a data-assimilating regional wind model. To illustrate the utility of these monitoring tools we focus on two 45-day periods which previously were shown to present contrasting pictures of the circulation. One, the low-outflow period is from 1 October through 14 November 2007; the other is the high-outflow period from 3 March through 16 April 2008. The large-scale characteristics noted by previous workers are clearly corroborated. Specifically the M2 tide dominates the surface currents, and the Delaware Bay outflow plume is clearly evident in the low frequency currents. Several new aspects of the surface circulation were also identified. These include a map of the spatial variability of the M2 tide (validating an earlier model study), persistent low-frequency cross-mouth flow, and a rapid response of the surface currents to a changing wind field. However, strong wind episodes did not persist long enough to set up a sustained Ekman response.

  6. Current Perspectives on the Physical and Biological Processes of Humboldt Bay

    E-Print Network [OSTI]

    Schlosser, S. C.; Rasmussen, R.

    2007-01-01T23:59:59.000Z

    Spit, which had absorbed much of the wave energy. Once theseharbor entrance deepened, wave energy came into the bay andand refocusing wave energy that, in turn, increases risk to

  7. Targeting Net Zero Energy at Marine Corps Base Kaneohe Bay, Hawaii...

    Broader source: Energy.gov (indexed) [DOE]

    Targeting Net Zero Energy at Marine Corps Base Kaneohe Bay, Hawaii: Assessment and Recommendations K. Burman, A. Kandt, L. Lisell, S. Booth, A. Walker, J. Roberts and J. Falcey...

  8. Vegetation and sediment characteristics of created and natural Spartina alterniflora marshes in Lower Galveston Bay, Texas

    E-Print Network [OSTI]

    Albertson, Andrea Kai

    1998-01-01T23:59:59.000Z

    Five natural and ten created Spartina altemiflora marshes in the Lower Galveston Bay System, Texas, were compared to determine if there were significantly different vegetative and sediment characteristics associated with each marsh type. Vegetative...

  9. Effects Of Sea Otter Colonization On Soft-Sediment Intertidal Prey Assemblages In Glacier Bay, Alaska

    E-Print Network [OSTI]

    Weitzman, Benjamin Phillip

    2013-01-01T23:59:59.000Z

    structuring in soft-sediment systems over a multi-decadalcaloric demands. In soft-substrate systems, recolonizing seainfluences of otters on soft-sediment systems in Glacier Bay

  10. An Urban Estuary in a Changing World: Diversity, Invasions, and Climate Change in San Francisco Bay

    E-Print Network [OSTI]

    Chang, Andrew L.

    2009-01-01T23:59:59.000Z

    33: 1–67. ????. 2006. Water Quality of San Francisco Bay.within and among shallow- water Ciona species (Ascidiacea).induced changes in estuarine water quality. Marine Ecology

  11. A Rapid Assessment Method Examining the Ecological Health of Tidal Marine Wetlands in Galveston Bay, Texas

    E-Print Network [OSTI]

    Staszak, Lindsey Ann

    2011-10-21T23:59:59.000Z

    Galveston Bay, and then grouped those measurements into four functional groups: landscape/site characteristics, hydrology, wildlife habitat, and soil characteristics. I then developed a scoring system (minimum 0, maximum 100) to summarize the overall health...

  12. Increase in the Intensity of Postmonsoon Bay of Bengal Tropical Cyclones

    SciTech Connect (OSTI)

    Balaguru, Karthik; Taraphdar, Sourav; Leung, Lai-Yung R.; Foltz, Gregory R.

    2014-05-28T23:59:59.000Z

    The post-monsoon (October-November) tropical cyclone (TC) season in the Bay of Bengal has spawned many of the deadliest storms in recorded history. Here it is shown that the intensity of post-monsoon Bay of Bengal TCs, and the contribution of major TCs to total TC power, increased during 1981-2010. It is found that changes in environmental parameters are responsible for the observed increases in TC intensity. Increases in sea surface temperature and upper ocean heat content made the ocean more conducive to TC development, while enhanced convective instability made the atmosphere more favorable for the growth of TCs. The largest changes in the atmosphere and ocean occurred in the eastern Bay of Bengal, where nearly all major TCs form. These changes are part of positive linear trends, suggesting that the intensity of post-monsoon Bay of Bengal TCs may continue to increase in the future.

  13. Tidal response of a bay with a constricted opening to the sea

    E-Print Network [OSTI]

    Love, Robert Wesley

    1959-01-01T23:59:59.000Z

    Fundamental response of bay for a'L = . 01, H/ho & 1 Fundamental response of bay for o'L = . 1, H/h & . 1 . Fundamental response of bay for crL =, 5, H/h & . 1 . 31 33 I Response factor of a /H for ctL =, 01, H/h as 0 indicated, 10 Response factor of a... -& . 06 . 04 3. H/h = . 1 H/h = . 05 H/ho = . 01 . 02 0 . 1 . 5 1 2 10 20 Bay Parameter, N 50 100 200 Pig. 10: Respoase Factor of a2/H for cL = 0. 1, H/h as isdicatetl. . 08 x . Oe H [ . 04 cd H/h H/ho = . 05 H/h = . 01 0 . 02 . 5 1 2...

  14. Chesapeake Bay Eutrophication: Scientific Understanding, Ecosystem Restoration, and Challenges for Agriculture

    E-Print Network [OSTI]

    Chesapeake Bay Eutrophication: Scientific Understanding, Ecosystem Restoration, and Challenges'scultural eutrophication and extensive efforts to reduce nutrient inputs. In 1987 a commitment was made to reduce of eutrophication were incompletely known. research, policies, and concerted management action Subsequent research

  15. Guidelines for left-turn bays at unsignalized access locations on arterial roadways

    E-Print Network [OSTI]

    Hawley, Patrick Emmett

    1994-01-01T23:59:59.000Z

    It has long been recognized that effective access management along arterial streets can alleviate traffic congestion. A major goal within access management is to limit the speed differential between turning and through vehicles. Left-turn bays...

  16. Targeting Net Zero Energy at Marine Corps Base Kaneohe Bay, Hawaii: Assessment and Recommendations

    Office of Energy Efficiency and Renewable Energy (EERE)

    NREL performed a comprehensive assessment to appraise the potential of MCBH Kaneohe Bay to achieve net zero energy status through energy efficiency, renewable energy, and electric vehicle integration. This report summarizes the results of the assessment and provides energy recommendations.

  17. Age and growth of southern flounder (Paralichthys lethostigma) from Matagorda Bay, Texas

    E-Print Network [OSTI]

    Stunz, Gregory Wayne

    1995-01-01T23:59:59.000Z

    Estimates of age and growth of southern flounder (Paralichthys lethostigma) from Matagorda Bay, Texas were made by analyzing thin sections of otoliths (sagittae) from 892 specimens collected along the Texas coast from May 1992 to January 1995...

  18. Effect of variation in freshwater inflow on phytoplankton productivity and community composition in galveston bay, texas

    E-Print Network [OSTI]

    Thronson, Amanda Mae

    2009-05-15T23:59:59.000Z

    2050, water regulators and managers are faced with the challenge of meeting human needs, while maintaining essential freshwater inflows into estuarine ecosystems. Galveston Bay is of particular concern because 10 million people currently living within...

  19. Political Ecology and Coastal Conservation: A Case Study of Menai Bay Conservation Area, Tanzania

    E-Print Network [OSTI]

    Shinn, Jamie Elizabeth

    2010-06-04T23:59:59.000Z

    . This thesis begins to fill that gap by using a political ecology-based approach to understand the complex historical, political, and environmental factors that affect issues of degradation and conservation in the Menai Bay Conservation Area of Zanzibar...

  20. Hydro-Ecologic Responses to Land Use in Small Urbanizing Watersheds Within the Chesapeake Bay

    E-Print Network [OSTI]

    Palmer, Margaret A.

    Hydro-Ecologic Responses to Land Use in Small Urbanizing Watersheds Within the Chesapeake Bay. The consequences for both the hydrology and 41 #12;42 HYDRO-ECOLOGIC RESPONSES TO LAND USE IN SMALL URBANIZING

  1. DEVELOPING A METHOD TO MONITOR SEDIMENTATION PROCESSES IN MAYAGEZ BAY USING MODIS DATA

    E-Print Network [OSTI]

    Gilbes, Fernando

    b d 1 & 2) October 26, 2005 Close up of the Bay (c) (MODIS band 1 & 2) y = 452.41x + 2.9603 R 2 = 0.7232

  2. Current Perspectives on the Physical and Biological Processes of Humboldt Bay

    E-Print Network [OSTI]

    Schlosser, S. C.; Rasmussen, R.

    2007-01-01T23:59:59.000Z

    food on Humboldt Bay mudflat. M.S. thesis, Humboldt Statecould be applied to mudflat or high marsh communities. TheSlough. Note the higher mudflat bars on the north side of

  3. Ground penetrating radar characterization of wood piles and the water table in Back Bay, Boston

    E-Print Network [OSTI]

    LeFrançois, Suzanne O'Neil, 1980-

    2003-01-01T23:59:59.000Z

    Ground penetrating radar (GPR) surveys are performed to determine the depth to the water table and the tops of wood piles beneath a residential structure at 122 Beacon Street in Back Bay, Boston. The area of Boston known ...

  4. Successful Application of Heat Pumps to a DHC System in the Tokyo Bay Area

    E-Print Network [OSTI]

    Yanagihara, R.; Okagaki, A.

    2006-01-01T23:59:59.000Z

    The Harumi-Island District Heating & Cooling (DHC), which is located in the Tokyo Bay area, introduced the heat pump and thermal storage system with the aim of achieving minimum energy consumption, minimum environmental load, and maximum economical...

  5. Empirical Bayes in the presence of exceptional cases, with application to microarray data

    E-Print Network [OSTI]

    Smyth, Gordon K.

    Research, 1G Royal Parade, Parkville, Victoria 3052, Australia. (3) Department of Mathematics, Australia. (5) Corresponding author. Abstract Empirical Bayes is a statistical approach for estimating procedure improves statistical power for most genes in many microarray data sets. Simulations show

  6. The Association of Virulent Vibrio Spp. Bacteria on Gafftopsail and Hardhead Catfish in Galveston Bay 

    E-Print Network [OSTI]

    Gilbert, Leslie Deanne

    2011-10-21T23:59:59.000Z

    Vibrio vulnificus (Vv) and V. parahaemolyticus (Vp) are gram negative, halophilic bacteria that occur naturally in estuarine waters of Galveston Bay. Both bacteria have the potential to cause infections in humans either via consumption or direct...

  7. The distribution and diurnal variation of phosphorus in some Texas bays

    E-Print Network [OSTI]

    Bruce, Herbert Ernest

    1959-01-01T23:59:59.000Z

    of these compounds is probably negligible since these compounds are obtained by extraction from nucleo- protein with chloroform (Harvey, 1938). SECTION III DETERMINATION OF THE DISTRIBUTION OF IONIC PHOSPHATE IN BAFFIN BAY AS TRACED HITH P In an effort...

  8. Successful Application of Heat Pumps to a DHC System in the Tokyo Bay Area 

    E-Print Network [OSTI]

    Yanagihara, R.; Okagaki, A.

    2006-01-01T23:59:59.000Z

    The Harumi-Island District Heating & Cooling (DHC), which is located in the Tokyo Bay area, introduced the heat pump and thermal storage system with the aim of achieving minimum energy consumption, minimum environmental load, and maximum economical...

  9. Reactor control rod timing system

    DOE Patents [OSTI]

    Wu, Peter T. K. (Clifton Park, NY)

    1982-01-01T23:59:59.000Z

    A fluid driven jet-edge whistle timing system for control rods of a nuclear reactor for producing real-time detection of the timing of each control rod in its scram operation. An important parameter in reactor safety, particularly for liquid metal fast breeder reactors (LMFBR), is the time deviation between the time the control rod is released and the time the rod actually reaches the down position. The whistle has a nearly pure tone signal with center frequency (above 100 kHz) far above the frequency band in which the energy of the background noise is concentrated. Each control rod can be fitted with a whistle with a different frequency so that there is no ambiguity in differentiating the signal from each control rod.

  10. Reactor control rod timing system

    SciTech Connect (OSTI)

    Wu, P.T.

    1982-02-09T23:59:59.000Z

    A fluid driven jet-edge whistle timing system for control rods of a nuclear reactor for producing real-time detection of the timing of each control rod in its scram operation. An important parameter in reactor safety, particularly for liquid metal fast breeder reactors (LMFBR), is the time deviation between the time the control rod is released and the time the rod actually reaches the down position. The whistle has a nearly pure tone signal with center frequency (Above 100 kHz) far above the frequency band in which the energy of the background noise is concentrated. Each control rod can be fitted with a whistle with a different frequency so that there is no ambiguity in differentiating the signal from each control rod.

  11. Integral fast reactor safety features

    SciTech Connect (OSTI)

    Cahalan, J.E.; Kramer, J.M.; Marchaterre, J.F.; Mueller, C.J.; Pedersen, D.R.; Sevy, R.H.; Wade, D.C.; Wei, T.Y.C.

    1988-01-01T23:59:59.000Z

    The Integral Fast Reactor (IFR) is an advanced liquid-metal-cooled reactor concept being developed at Argonne National Laboratory. The two major goals of the IFR development effort are improved economics and enhanced safety. In addition to liquid metal cooling, the principal design features that distinguish the IFR are: (1) a pool-type primary system, (2) an advanced ternary alloy metallic fuel, and (3) an integral fuel cycle with on-site fuel reprocessing and fabrication. This paper focuses on the technical aspects of the improved safety margins available in the IFR concept. This increased level of safety is made possible by (1) the liquid metal (sodium) coolant and pool-type primary system layout, which together facilitate passive decay heat removal, and (2) a sodium-bonded metallic fuel pin design with thermal and neutronic properties that provide passive core responses which control and mitigate the consequences of reactor accidents.

  12. Assessment of bycatch associated with the inshore shrimp fishery in Matagorda Bay, Texas

    E-Print Network [OSTI]

    Sparks, Debbie Laura

    2000-01-01T23:59:59.000Z

    ASSESSMENT OF BYCATCH ASSOCIATED WITH THE INSHORE SHRIMP FISHERY IN MATAGORDA BAY, TEXAS A Thesis by DEBBIE LAURA SPARKS Submitted to the Office of Graduate Studies of Texas ARM University in partial fulfillment of the requirements... for the degree of MASTER OF SCIENCE August 2000 Major Subject: Wildlife and Fisheries Sciences ASSESSMENT OF BYCATCH ASSOCIATED WITH THE INSHORE SHRIMP FISHERY IN MATAGORDA BAY, TEXAS A Thesis by DEBBIE LAURA SPARKS Submitted to Texas ARM University...

  13. DRAFT RICHMOND BAY CAMPUS LRDP | August 2013 Appendix 1: Existing Richmond Field Station Building Inventory (2012)

    E-Print Network [OSTI]

    Lee, Jason R.

    2012-01-01T23:59:59.000Z

    in the fore- ground and the San Francisco Bay and Marina Bay residen- tial community beyond. #12;A.2 DRAFT Research Ofc 1960-1969 16,949 12 Poor 113 Storage 1980-1989 1,800 14 Good 114 Storage pre 1940 4,523 12 Good 120 Storage unknown 269 12 Good 121 Storage unknown 728 15 Good 125 Storage pre 1940 1,024 12 Good

  14. Antecedent Geologic Controls on the Distribution of Oyster Reefs in Copano Bay, Texas

    E-Print Network [OSTI]

    Piper, Erin Alynn

    2011-08-08T23:59:59.000Z

    ANTECEDENT GEOLOGIC CONTROLS ON THE DISTRIBUTION OF OYSTER REEFS IN COPANO BAY, TEXAS A Thesis by ERIN ALYNN PIPER Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements... for the degree of MASTER OF SCIENCE May 2010 Major Subject: Oceanography ANTECEDENT GEOLOGIC CONTROLS ON THE DISTRIBUTION OF OYSTER REEFS IN COPANO BAY, TEXAS A Thesis by ERIN ALYNN PIPER Submitted to the Office of Graduate...

  15. Sedimentary environments and processes in a shallow, Gulf Coast Estuary-Lavaca Bay, Texas.

    E-Print Network [OSTI]

    Bronikowski, Jason Lee

    2004-11-15T23:59:59.000Z

    point, the bedload cannot migrate seaward pass the null point. As a result, coarser sediment deposits form upstream of the null point. During flooding, the null point and bedload deposits migrate down into the bay. A turbidity maximum exists... correlation between low and high backscatter to muddy and sandy substrates. Low backscatter correlated to fine grain sediment and the high backscatter to coarser sediment deposits at grab locations, and these were extrapolated to the entire bay floor...

  16. Influence of soil physicochemical properties on hydrology and restoration response in Carolina Bay wetlands.

    SciTech Connect (OSTI)

    Barton, C. D.; Andrews, D.M.; Kolka, R.K.

    2006-04-01T23:59:59.000Z

    Carolina Bays are shallow depression wetlands found in the southeast US that have been severely altered by human activity. The need to restore these complex and diverse systems is well established, but our understanding of basic wetland hydrological processes is limited, hence our ability to predict the need for and/or assess the effectiveness of bay restorations is hindered. Differing physicochemical properties of soils within bay interiors may control bay hydrology. However, previous efforts to establish relationships between soil characteristics and bay hydrology have been inconclusive and the question still remains as to why some bays are ponded throughout the year while others, within a similar landscape unit, are predominantly dry. An assessment of soil and hydrologic characteristics was initiated in restored and unrestored control bays to determine if a relationship exists. Soil morphology was described and permanent monitoring wells were installed at each site. Soil samples were collected by horizon to a depth of 2 meters at the topographic center of each site, and then analyzed. After three years, multiple regression analysis (stepwise backward and forward) was used to establish relationships between the soil physicochemical characteristics and bay hydroperiod in the undisturbed sites. Results from surface soils indicated that exchangeable acidity (EA) was the best single predictor of hydrology. The best double predictor was EA and total N and EA, total N and total C as the best triple predictor. A significant relationship (r2 = 0.96) between hydroperiod and clay content in the argillic horizon (Bt) was also observed. Subsequently, this relationship was utilized to predict hydrologic response using pre-restoration hydroperiod data. The model accurately identified sites that did not need hydrologic restoration (too wet), and effectively showed sites that responded well to restoration activities.

  17. 13 OctOber 2013 Mission Bay Conference Center, San Francisco, USA

    E-Print Network [OSTI]

    Kaski, Samuel

    1­3 OctOber 2013 Mission Bay Conference Center, San Francisco, USA www.beyond-the-genome.com Beyond the Genome 2013 #12;2 1­3 OctOber 2013 Mission Bay Conference Center, San Francisco, USA www.beyond-the-genome.com Beyond the Genome 2013 Exhibition and sponsorship Nick Moss BioMed Central T: +44 (0)20 3192 2723 E: nick

  18. DOE's way-out reactors

    SciTech Connect (OSTI)

    Marshall, E.

    1986-03-21T23:59:59.000Z

    The SP-100 reactor, envisioned long before Star Wars, was to power civilian structures such as the space station and orbiting commercial labs. According to the SDI Organization, it will be the cornerstone for SDI, used as a no-maintenance, general source of energy for the military's infrastructure - weapons scale power will come later. DOE wants to spend $72 in FY 1977 to design and build these reactors. Funding problems with Congress, as well as some of the technology and timetables are discussed here.

  19. Nuclear reactor safety heat transfer

    SciTech Connect (OSTI)

    Jones, O.C.

    1982-07-01T23:59:59.000Z

    Reviewed is a book which has 5 parts: Overview, Fundamental Concepts, Design Basis Accident-Light Water Reactors (LWRs), Design Basis Accident-Liquid-Metal Fast Breeder Reactors (LMFBRs), and Special Topics. It combines a historical overview, textbook material, handbook information, and the editor's personal philosophy on safety of nuclear power plants. Topics include thermal-hydraulic considerations; transient response of LWRs and LMFBRs following initiating events; various accident scenarios; single- and two-phase flow; single- and two-phase heat transfer; nuclear systems safety modeling; startup and shutdown; transient response during normal and upset conditions; vapor explosions, natural convection cooling; blockages in LMFBR subassemblies; sodium boiling; and Three Mile Island.

  20. Uncertainties in the Anti-neutrino Production at Nuclear Reactors

    E-Print Network [OSTI]

    Djurcic, Zelimir

    2009-01-01T23:59:59.000Z

    reactors are determined from thermal power measure- ments and ?ssion rate calculations.of a reactor’s ther- mal power is given by a calculation ofCALCULATIONS During the power cycle of a nuclear reactor,

  1. Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation

    E-Print Network [OSTI]

    Heidet, Florent

    2010-01-01T23:59:59.000Z

    Gas Expansion Module Gas-cooled Fast Reactor High Enrichedfast reactors: gas-cooled fast reactor (GFR), sodium-cooledderived from the Gas cooled Fast Reactor (GFR). This core

  2. Computational Analysis of Fluid Flow in Pebble Bed Modular Reactor

    E-Print Network [OSTI]

    Gandhir, Akshay

    2012-10-19T23:59:59.000Z

    High Temperature Gas-cooled Reactor (HTGR) is a Generation IV reactor under consideration by Department of Energy and in the nuclear industry. There are two categories of HTGRs, namely, Pebble Bed Modular Reactor (PBMR) and Prismatic reactor. Pebble...

  3. Reactor Operations informal monthly report September 1994

    SciTech Connect (OSTI)

    Junker, L.

    1994-09-01T23:59:59.000Z

    This paper presents operations at the MRR and HFBR reactors at Brookhaven National Laboratory for September 1994. Reactor run-times, instrumentation, mechanical maintenance, occurrence reports and safety information are listed. Irradiation summaries are included.

  4. Reactivity control assembly for nuclear reactor

    DOE Patents [OSTI]

    Bollinger, Lawrence R. (Schenectady, NY)

    1984-01-01T23:59:59.000Z

    Reactivity control assembly for nuclear reactor comprises supports stacked above reactor core for holding control rods. Couplers associated with the supports and a vertically movable drive shaft have lugs at their lower ends for engagement with the supports.

  5. Microfluidic reactors for the synthesis of nanocrystals

    E-Print Network [OSTI]

    Yen, Brian K. H

    2007-01-01T23:59:59.000Z

    Several microfluidic reactors were designed and applied to the synthesis of colloidal semiconductor nanocrystals (NCs). Initially, a simple single-phase capillary reactor was used for the synthesis of CdSe NCs. Precursors ...

  6. Stability analysis of supercritical water cooled reactors

    E-Print Network [OSTI]

    Zhao, Jiyun, Ph. D. Massachusetts Institute of Technology

    2005-01-01T23:59:59.000Z

    The Supercritical Water-Cooled Reactor (SCWR) is a concept for an advanced reactor that will operate at high pressure (25MPa) and high temperature (500°C average core exit). The high coolant temperature as it leaves the ...

  7. Auxiliary reactor for a hydrocarbon reforming system

    DOE Patents [OSTI]

    Clawson, Lawrence G.; Dorson, Matthew H.; Mitchell, William L.; Nowicki, Brian J.; Bentley, Jeffrey M.; Davis, Robert; Rumsey, Jennifer W.

    2006-01-17T23:59:59.000Z

    An auxiliary reactor for use with a reformer reactor having at least one reaction zone, and including a burner for burning fuel and creating a heated auxiliary reactor gas stream, and heat exchanger for transferring heat from auxiliary reactor gas stream and heat transfer medium, preferably two-phase water, to reformer reaction zone. Auxiliary reactor may include first cylindrical wall defining a chamber for burning fuel and creating a heated auxiliary reactor gas stream, the chamber having an inlet end, an outlet end, a second cylindrical wall surrounding first wall and a second annular chamber there between. The reactor being configured so heated auxiliary reactor gas flows out the outlet end and into and through second annular chamber and conduit which is disposed in second annular chamber, the conduit adapted to carry heat transfer medium and being connectable to reformer reaction zone for additional heat exchange.

  8. Challenges in the Development of Advanced Reactors

    SciTech Connect (OSTI)

    P. Sabharwall; M.C. Teague; S.M. Bragg-Sitton; M.W. Patterson

    2012-08-01T23:59:59.000Z

    Past generations of nuclear reactors have been successively developed and the next generation is currently being developed, demonstrating the constant progress and technical and industrial vitality of nuclear energy. In 2000 US Department of Energy launched Generation IV International Forum (GIF) which is one of the main international frameworks for the development of future nuclear systems. The six systems that were selected were: sodium cooled fast reactor, lead cooled fast reactor, supercritical water cooled reactor, very high temperature gas cooled reactor (VHTR), gas cooled fast reactor and molten salt reactor. This paper discusses some of the proposed advanced reactor concepts that are currently being researched to varying degrees in the United States, and highlights some of the major challenges these concepts must overcome to establish their feasibility and to satisfy licensing requirements.

  9. MULTIPHASE REACTOR MODELING FOR ZINC CHLORIDE CATALYZED COAL LIQUEFACTION

    E-Print Network [OSTI]

    Joyce, Peter James

    2011-01-01T23:59:59.000Z

    for the Coal Slurry Reactor Calculations are shown here for= Total reactor pressure, psi. The calculation is iterative,

  10. Incorporation of Hydride Nuclear Fuels in Commercial Light Water Reactors

    E-Print Network [OSTI]

    Terrani, Kurt Amir

    2010-01-01T23:59:59.000Z

    target subassemblies in a fast reactor core for effectiveof minor actinides in fast reactors [79]. In order to

  11. Granular Dynamics in Pebble Bed Reactor Cores

    E-Print Network [OSTI]

    Laufer, Michael Robert

    2013-01-01T23:59:59.000Z

    a simulant fluid to match the dynamics of fuel pebbles andfuel pebbles through reactor cores with and without coupled fluid

  12. Digital computer operation of a nuclear reactor

    DOE Patents [OSTI]

    Colley, Robert W. (Richland, WA)

    1984-01-01T23:59:59.000Z

    A method is described for the safe operation of a complex system such as a nuclear reactor using a digital computer. The computer is supplied with a data base containing a list of the safe state of the reactor and a list of operating instructions for achieving a safe state when the actual state of the reactor does not correspond to a listed safe state, the computer selects operating instructions to return the reactor to a safe state.

  13. Digital computer operation of a nuclear reactor

    DOE Patents [OSTI]

    Colley, R.W.

    1982-06-29T23:59:59.000Z

    A method is described for the safe operation of a complex system such as a nuclear reactor using a digital computer. The computer is supplied with a data base containing a list of the safe state of the reactor and a list of operating instructions for achieving a safe state when the actual state of the reactor does not correspond to a listed safe state, the computer selects operating instructions to return the reactor to a safe state.

  14. Liquid metal cooled nuclear reactor plant system

    DOE Patents [OSTI]

    Hunsbedt, Anstein (Los Gatos, CA); Boardman, Charles E. (Saratoga, CA)

    1993-01-01T23:59:59.000Z

    A liquid metal cooled nuclear reactor having a passive cooling system for removing residual heat resulting for fuel decay during reactor shutdown, or heat produced during a mishap. The reactor system is enhanced with sealing means for excluding external air from contact with the liquid metal coolant leaking from the reactor vessel during an accident. The invention also includes a silo structure which resists attack by leaking liquid metal coolant, and an added unique cooling means.

  15. Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories

    Office of Legacy Management (LM)

    Radiological Condition of the Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories Cheswick, Pennsylvania -. -, -- AGENCY: Office of Operational Safety, Department...

  16. Interdisciplinary Institute for Innovation Nuclear reactors' construction

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Interdisciplinary Institute for Innovation Nuclear reactors' construction costs: The role of lead@mines-paristech.fr hal-00956292,version1-6Mar2014 #12;hal-00956292,version1-6Mar2014 #12;Nuclear reactors' construction reactor construction costs in France and the United States. Studying the cost of nuclear power has often

  17. Laminar Entrained Flow Reactor (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2014-02-01T23:59:59.000Z

    The Laminar Entrained Flow Reactor (LEFR) is a modular, lab scale, single-user reactor for the study of catalytic fast pyrolysis (CFP). This system can be employed to study a variety of reactor conditions for both in situ and ex situ CFP.

  18. BROOKHAVEN NATIONAL LABORATORY'S HIGH FLUX BEAM REACTOR

    E-Print Network [OSTI]

    Ohta, Shigemi

    1 BROOKHAVEN NATIONAL LABORATORY'S HIGH FLUX BEAM REACTOR Compiled by S. M. Shapiro I. PICTORIAL with fiberglass insulation and a protective aluminum skin. The reactor vessel is shaped somewhat like a very large at the spherical end. It is located at the center of the reactor building and is surrounded by a lead and steel

  19. The Reactor An ObjectOriented Framework

    E-Print Network [OSTI]

    Schmidt, Douglas C.

    The Reactor An Object­Oriented Framework for Event Demultiplexing and Event Handler Dispatching Douglas C. Schmidt 1 Overview ffl The Reactor is an object­oriented frame­ work that encapsulates OS event demul­ tiplexing mechanisms -- e.g., the Reactor API runs transparently atop both Wait

  20. REACTOR SAFETY KEYWORDS: best estimate plus

    E-Print Network [OSTI]

    Hoppe, Fred M.

    REACTOR SAFETY KEYWORDS: best estimate plus uncertainty analysis, epistemic error and aleatory phe- nomena that underlie the safety analyses. The use of BE codes within the reactor technology in advance and that result from a variety of operating conditions or states. These arise because the reactor

  1. Chemical Reactor Analysis and Optimal Digestion

    E-Print Network [OSTI]

    Jumars, Pete

    J 310 Chemical Reactor Analysis and Optimal Digestion An optimal digestion theory can be readily derived from basic principles o f chemical reactor analysis and design Deborah L. Penry and Peter a reactor and an operating strategy that maximize the yield or yield rate of desired reaction products

  2. BioElectrochemically Assisted Microbial Reactor

    E-Print Network [OSTI]

    Lee, Dongwon

    BioElectrochemically Assisted Microbial Reactor (BEAMR) The BEAMR reactor uses only >0.2 V needed of combustion) >85% based on energy in electricity + acetate, at a rate of 1 m3 -H2 /m3 -reactor volume/d (100 A

  3. Nuclear reactor safeguards and monitoring with antineutrino detectors A. Bernsteina)

    E-Print Network [OSTI]

    Gratta, Giorgio

    Nuclear reactor safeguards and monitoring with antineutrino detectors A. Bernsteina) Sandia of nuclear reactor types, including power reactors, research reactors, and plutonium production reactors-understood principles that govern the core's evolution in time, can be used to determine whether the reactor is being

  4. Integrated reformer and shift reactor

    DOE Patents [OSTI]

    Bentley, Jeffrey M.; Clawson, Lawrence G.; Mitchell, William L.; Dorson, Matthew H.

    2006-06-27T23:59:59.000Z

    A hydrocarbon fuel reformer for producing diatomic hydrogen gas is disclosed. The reformer includes a first reaction vessel, a shift reactor vessel annularly disposed about the first reaction vessel, including a first shift reactor zone, and a first helical tube disposed within the first shift reactor zone having an inlet end communicating with a water supply source. The water supply source is preferably adapted to supply liquid-phase water to the first helical tube at flow conditions sufficient to ensure discharge of liquid-phase and steam-phase water from an outlet end of the first helical tube. The reformer may further include a first catalyst bed disposed in the first shift reactor zone, having a low-temperature shift catalyst in contact with the first helical tube. The catalyst bed includes a plurality of coil sections disposed in coaxial relation to other coil sections and to the central longitudinal axis of the reformer, each coil section extending between the first and second ends, and each coil section being in direct fluid communication with at least one other coil section.

  5. Starfire - a commercial tokamak reactor

    SciTech Connect (OSTI)

    Baker, C.C.; Abdou, M.A.; DeFreece, D.A.; Trachsel, C.A.; Kokoszenski, J.; Graumann, D.

    1981-01-01T23:59:59.000Z

    The basic objective of the STARFIRE Project is to develop a design concept for a commercial tokamak fusion electric power plant based on the deuterium/tritium/lithium fuel cycle. The key technical objective is to develop the best embodiment of the tokamak as a power reactor consistent with credible engineering solutions to design problems. 10 refs.

  6. Nozzle for electric dispersion reactor

    DOE Patents [OSTI]

    Sisson, W.G.; Harris, M.T.; Scott, T.C.; Basaran, O.A.

    1996-04-02T23:59:59.000Z

    A nozzle for an electric dispersion reactor includes two coaxial cylindrical bodies, the inner one of the two delivering disperse phase fluid into a continuous phase fluid. A potential difference generated by a voltage source creates a dispersing electric field at the end of the inner electrode. 5 figs.

  7. Nozzle for electric dispersion reactor

    DOE Patents [OSTI]

    Sisson, Warren G. (Oak Ridge, TN); Basaran, Osman A. (Oak Ridge, TN); Harris, Michael T. (Knoxville, TN)

    1995-01-01T23:59:59.000Z

    A nozzle for an electric dispersion reactor includes two concentric electrodes, the inner one of the two delivering disperse phase fluid into a continuous phase fluid. A potential difference generated by a voltage source creates a dispersing electric field at the end of the inner electrode.

  8. Nozzle for electric dispersion reactor

    DOE Patents [OSTI]

    Sisson, Warren G. (Oak Ridge, TN); Harris, Michael T. (Knoxville, TN); Scott, Timothy C. (Knoxville, TN); Basaran, Osman A. (Oak Ridge, TN)

    1998-01-01T23:59:59.000Z

    A nozzle for an electric dispersion reactor includes two coaxial cylindrical bodies, the inner one of the two delivering disperse phase fluid into a continuous phase fluid. A potential difference generated by a voltage source creates a dispersing electric field at the end of the inner electrode.

  9. Nozzle for electric dispersion reactor

    DOE Patents [OSTI]

    Sisson, Warren G. (Oak Ridge, TN); Basaran, Osman A. (Oak Ridge, TN); Harris, Michael T. (Knoxville, TN)

    1998-01-01T23:59:59.000Z

    A nozzle for an electric dispersion reactor includes two concentric electrodes, the inner one of the two delivering disperse phase fluid into a continuous phase fluid. A potential difference generated by a voltage source creates a dispersing electric field at the end of the inner electrode.

  10. Nozzle for electric dispersion reactor

    DOE Patents [OSTI]

    Sisson, Warren G. (Oak Ridge, TN); Harris, Michael T. (Knoxville, TN); Scott, Timothy C. (Knoxville, TN); Basaran, Osman A. (Oak Ridge, TN)

    1996-01-01T23:59:59.000Z

    A nozzle for an electric dispersion reactor includes two coaxial cylindrical bodies, the inner one of the two delivering disperse phase fluid into a continuous phase fluid. A potential difference generated by a voltage source creates a dispersing electric field at the end of the inner electrode.

  11. Nuclear Reactions and Reactor Safety

    E-Print Network [OSTI]

    Onuchic, José

    Nuclear Reactions and Reactor Safety DO NOT LICK We haven't entirely nailed down what element nuclear chain reaction, 1938 #12;Nuclear Chain Reactions Do nuclear chain reactions lead to runaway explosions? or ? -Controlled nuclear chain reactions possible: control energy release/sec -> More

  12. MCZ 050411 1 Stellarator Reactors

    E-Print Network [OSTI]

    designs => Motivated development of more compact designs · SPPS projected cost of electricity similar Average Major Radius (m) ASRA-6C 20 m HSR-G 18 m SPPS 14 m FFHR-J 10 m ARIES-ST Spherical Torus 3.2 m to tokamaks, but higher initial capital cost · Stellarator reactors expected to operate in true ignition

  13. Nuclear Reactor Safety Design Criteria

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1993-01-19T23:59:59.000Z

    The order establishes nuclear safety criteria applicable to the design, fabrication, construction, testing, and performance requirements of nuclear reactor facilities and safety class structures, systems, and components (SSCs) within these facilities. Cancels paragraphs 8a and 8b of DOE 5480.6. Cancels DOE O 5480.6 in part. Certified 11-18-10.

  14. Nozzle for electric dispersion reactor

    DOE Patents [OSTI]

    Sisson, W.G.; Harris, M.T.; Scott, T.C.; Basaran, O.A.

    1998-06-02T23:59:59.000Z

    A nozzle for an electric dispersion reactor includes two coaxial cylindrical bodies, the inner one of the two delivering disperse phase fluid into a continuous phase fluid. A potential difference generated by a voltage source creates a dispersing electric field at the end of the inner electrode. 5 figs.

  15. Nozzle for electric dispersion reactor

    DOE Patents [OSTI]

    Sisson, W.G.; Basaran, O.A.; Harris, M.T.

    1998-04-14T23:59:59.000Z

    A nozzle for an electric dispersion reactor includes two concentric electrodes, the inner one of the two delivering disperse phase fluid into a continuous phase fluid. A potential difference generated by a voltage source creates a dispersing electric field at the end of the inner electrode. 4 figs.

  16. Control of reactor coolant flow path during reactor decay heat removal

    DOE Patents [OSTI]

    Hunsbedt, Anstein N. (Los Gatos, CA)

    1988-01-01T23:59:59.000Z

    An improved reactor vessel auxiliary cooling system for a sodium cooled nuclear reactor is disclosed. The sodium cooled nuclear reactor is of the type having a reactor vessel liner separating the reactor hot pool on the upstream side of an intermediate heat exchanger and the reactor cold pool on the downstream side of the intermediate heat exchanger. The improvement includes a flow path across the reactor vessel liner flow gap which dissipates core heat across the reactor vessel and containment vessel responsive to a casualty including the loss of normal heat removal paths and associated shutdown of the main coolant liquid sodium pumps. In normal operation, the reactor vessel cold pool is inlet to the suction side of coolant liquid sodium pumps, these pumps being of the electromagnetic variety. The pumps discharge through the core into the reactor hot pool and then through an intermediate heat exchanger where the heat generated in the reactor core is discharged. Upon outlet from the heat exchanger, the sodium is returned to the reactor cold pool. The improvement includes placing a jet pump across the reactor vessel liner flow gap, pumping a small flow of liquid sodium from the lower pressure cold pool into the hot pool. The jet pump has a small high pressure driving stream diverted from the high pressure side of the reactor pumps. During normal operation, the jet pumps supplement the normal reactor pressure differential from the lower pressure cold pool to the hot pool. Upon the occurrence of a casualty involving loss of coolant pump pressure, and immediate cooling circuit is established by the back flow of sodium through the jet pumps from the reactor vessel hot pool to the reactor vessel cold pool. The cooling circuit includes flow into the reactor vessel liner flow gap immediate the reactor vessel wall and containment vessel where optimum and immediate discharge of residual reactor heat occurs.

  17. Sources and sinks of [sup 210]Pb in Concepcion Bay, Chile

    SciTech Connect (OSTI)

    Salamanca, Orrego, M.A.

    1993-01-01T23:59:59.000Z

    The sources and sinks of [sup 210]Pb to Concepcion Bay waters were evaluated to discern the relative importance of the main removal and supply mechanisms of this radionuclide to the waters of Concepcion Bay. The main inputs of [sup 210]Pb are the atmospheric supply and the advection of offshore upwelling waters. The atmospheric input was measured in precipitation using a collector and inventories of excess [sup 210]Pb in Rocuant and Raqui marsh sediments. The average atmospheric supply of [sup 210]Pb for Concepcion area is about 0.3 dpm cm[sup [minus]2] yr[sup [minus]1]. The advective input from upwelling varies from 0.6 [+-] 1.3 to 2.1 [+-] 2.0 dpm cm[sup [minus]2] yr[sup [minus]1]. [sup 210]Pb is removed efficiently from the water column as shelf water with high [sup 210]Pb content crosses the continental shelf off Concepcion Bay, with [sup 210]Pb/[sup 226]Ra activity ratios decreasing by a factor of 3 to 4 before reaching the interior of the bay. This is coincident with an increase of suspended matter concentration towards inside the bay. The main removal of [sup 210]Pb from Concepcion Bay waters is deposition in sediments. There is an increase of the [sup 210]Pb inventories toward the bay entrance excess (by a factor of 2) and outside the bay sediments (by a factor of 7). This pattern can be explained by an increase of mixing of sediments by the benthic infauna and enhanced removal of [sup 210]Pb from the water column by particles near the bay mouth. Mass balance calculations are included. The residence time of [sup 210]Pb with respect to removal from water column is estimated to be 17 to 43 days. The results of this research indicate that [sup 210]Pb and probably other similar particle-reactive contaminants (such as heavy metals) are retained and redistributed inside the bay by circulation, resuspension and biological mixing.

  18. Spectral shift reactor control method

    SciTech Connect (OSTI)

    Impink, A.J. Jr.

    1987-12-29T23:59:59.000Z

    This patent describes the method of operating a pressurized-water fissile-material-fueled spectral-shift nuclear reactor in such manner that short-term reactivity requirement variations can be satisfied without making control rod or chemical shim changes. The reactor includes a pressure vessel enclosing a reactor core and having an inlet and an outlet for circulating a water coolant moderator in heat transfer relationship with the core. The core comprises fuel assemblies disposed therein for generating heat by nuclear fission. The reactor provided with neutron-absorbing control rods which are vertically movable into and out of the core so that movement of the control rods into the core will substantially decrease reactivity and withdrawal of the control rods from the core will substantially increase reactivity. The control rods when inserted into the core displace an equivalent volume of the water coolant moderator. The reactor also provides neutron-spectral-shift rods which have a lower absorptivity for neutrons than the control rods, the neutron-spectral shift rods when inserted into the core displacing an equaivalent volume of the water coolant moderator. The neutron-spectral-shift rods comprises two different types of rods, a first of the different types of the neutron-spectral-shift rods comprising displacer rods which have a low absorptivity for neutrons, the remainder of the neutron-spectral-shift rods comprising gray rods which have an absorption for neutrons which is intermediate the neutron absorption of the control rods and the low neutron absorption of the displacer rods. Each neutron-spectral-shift displacer rod comprises a hollow thin-walled Zircaloy member containing a filling of solid or annular zirconium- or aluminum-containing material for providing internal support and mass for the thin-walled tubular member.

  19. Heterogeneous Recycling in Fast Reactors

    SciTech Connect (OSTI)

    Forget, Benoit; Pope, Michael; Piet, Steven J.; Driscoll, Michael

    2012-07-30T23:59:59.000Z

    Current sodium fast reactor (SFR) designs have avoided the use of depleted uranium blankets over concerns of creating weapons grade plutonium. While reducing proliferation risks, this restrains the reactor design space considerably. This project will analyze various blanket and transmutation target configurations that could broaden the design space while still addressing the non-proliferation issues. The blanket designs will be assessed based on the transmutation efficiency of key minor actinide (MA) isotopes and also on mitigation of associated proliferation risks. This study will also evaluate SFR core performance under different scenarios in which depleted uranium blankets are modified to include minor actinides with or without moderators (e.g. BeO, MgO, B4C, and hydrides). This will be done in an effort to increase the sustainability of the reactor and increase its power density while still offering a proliferation resistant design with the capability of burning MA waste produced from light water reactors (LWRs). Researchers will also analyze the use of recycled (as opposed to depleted) uranium in the blankets. The various designs will compare MA transmutation efficiency, plutonium breeding characteristics, proliferation risk, shutdown margins and reactivity coefficients with a current reference sodium fast reactor design employing homogeneous recycling. The team will also evaluate the out-of-core accumulation and/or burn-down rates of MAs and plutonium isotopes on a cycle-by-cycle basis. This cycle-by-cycle information will be produced in a format readily usable by the fuel cycle systems analysis code, VISION, for assessment of the sustainability of the deployment scenarios.

  20. Proceedings of the Symposium: Current Perspectives on the Physical and Biological Processes of Humboldt Bay, March 2004

    E-Print Network [OSTI]

    Schlosser, S. C.

    2007-01-01T23:59:59.000Z

    1893 and began ditching and dredging the marshland from thetions and Maintenance Dredging. Draft Program- matic 5-Yearwharf was abandoned. Early Dredging Humboldt Bay has been

  1. Monitoring and Modeling Non-Point Source Contributions of Host-Specific Fecal Contamination in San Pablo Bay

    E-Print Network [OSTI]

    Wuertz, Stefan; Bombardelli, Fabian A; Sirikanchana, Kwanrawee; Wang, Dan

    2009-01-01T23:59:59.000Z

    Host-Specific Fecal Contamination in San Pablo Bay Principlelivestock sources of fecal contamination in Kenya with host-Huang. Abstract Fecal contamination from non-point sources

  2. Ecosystem-scale Selenium Model for the San Francisco Bay-Delta Regional Ecosystem Restoration Implementation Plan

    E-Print Network [OSTI]

    Presser, Theresa S.; Luoma, Samuel N.

    2013-01-01T23:59:59.000Z

    both agricultural and oil refinery sources of Se (SFBRWQCBSe • hydrodynamics • oil refinery effluent • North Bay •1) internal inputs of oil refinery wastewaters from pro-

  3. Fast-acting nuclear reactor control device

    DOE Patents [OSTI]

    Kotlyar, Oleg M. (Idaho Falls, ID); West, Phillip B. (Idaho Falls, ID)

    1993-01-01T23:59:59.000Z

    A fast-acting nuclear reactor control device for moving and positioning a fety control rod to desired positions within the core of the reactor between a run position in which the safety control rod is outside the reactor core, and a shutdown position in which the rod is fully inserted in the reactor core. The device employs a hydraulic pump/motor, an electric gear motor, and solenoid valve to drive the safety control rod into the reactor core through the entire stroke of the safety control rod. An overrunning clutch allows the safety control rod to freely travel toward a safe position in the event of a partial drive system failure.

  4. Shutdown system for a nuclear reactor

    DOE Patents [OSTI]

    Groh, E.F.; Olson, A.P.; Wade, D.C.; Robinson, B.W.

    1984-06-05T23:59:59.000Z

    An ultimate shutdown system is provided for termination of neutronic activity in a nuclear reactor. The shutdown system includes bead chains comprising spherical containers suspended on a flexible cable. The containers are comprised of mating hemispherical shells which provide a ruggedized enclosure for reactor poison material. The bead chains, normally suspended above the reactor core on storage spools, are released for downward travel upon command from an external reactor monitor. The chains are capable of horizontal movement, so as to flow around obstructions in the reactor during their downward motion. 8 figs.

  5. Shutdown system for a nuclear reactor

    DOE Patents [OSTI]

    Groh, Edward F. (Naperville, IL); Olson, Arne P. (Western Springs, IL); Wade, David C. (Naperville, IL); Robinson, Bryan W. (Oak Lawn, IL)

    1984-01-01T23:59:59.000Z

    An ultimate shutdown system is provided for termination of neutronic activity in a nuclear reactor. The shutdown system includes bead chains comprising spherical containers suspended on a flexible cable. The containers are comprised of mating hemispherical shells which provide a ruggedized enclosure for reactor poison material. The bead chains, normally suspended above the reactor core on storage spools, are released for downward travel upon command from an external reactor monitor. The chains are capable of horizontal movement, so as to flow around obstructions in the reactor during their downward motion.

  6. Reactor monitoring and safeguards using antineutrino detectors

    E-Print Network [OSTI]

    N. S. Bowden

    2008-09-15T23:59:59.000Z

    Nuclear reactors have served as the antineutrino source for many fundamental physics experiments. The techniques developed by these experiments make it possible to use these very weakly interacting particles for a practical purpose. The large flux of antineutrinos that leaves a reactor carries information about two quantities of interest for safeguards: the reactor power and fissile inventory. Measurements made with antineutrino detectors could therefore offer an alternative means for verifying the power history and fissile inventory of a reactors, as part of International Atomic Energy Agency (IAEA) and other reactor safeguards regimes. Several efforts to develop this monitoring technique are underway across the globe.

  7. Self isolating high frequency saturable reactor

    DOE Patents [OSTI]

    Moore, James A. (Powell, TN)

    1998-06-23T23:59:59.000Z

    The present invention discloses a saturable reactor and a method for decoupling the interwinding capacitance from the frequency limitations of the reactor so that the equivalent electrical circuit of the saturable reactor comprises a variable inductor. The saturable reactor comprises a plurality of physically symmetrical magnetic cores with closed loop magnetic paths and a novel method of wiring a control winding and a RF winding. The present invention additionally discloses a matching network and method for matching the impedances of a RF generator to a load. The matching network comprises a matching transformer and a saturable reactor.

  8. Reactor assessments of advanced bumpy torus configurations

    SciTech Connect (OSTI)

    Uckan, N.A.; Owen, L.W.; Spong, D.A.; Miller, R.L.; Ard, W.B.; Pipkins, J.F.; Schmitt, R.J.

    1983-01-01T23:59:59.000Z

    Recently, several configurational approaches and concept improvement schemes were introduced for enhancing the performance of the basic ELMO Bumpy Torus (EBT) concept and for improving its reactor potential. These configurations include planar racetrack and square geometries, Andreoletti coil systems, and bumpy torus-stellarator hybrids (which include twisted racetrack and helical axis stellarator-snakey torus). Preliminary evaluations of reactor implications of each of these configurations have been carried out based on magnetics (vacuum) calculations, transport and scaling relationships, and stability properties. Results indicate favorable reactor projections with a significant reduction in reactor physical size as compared to conventional EBT reactor designs carried out in the past.

  9. Savannah River Site production reactor technical specifications. K Production Reactor

    SciTech Connect (OSTI)

    NONE

    1996-02-01T23:59:59.000Z

    These technical specifications are explicit restrictions on the operation of the Savannah River Site K Production Reactor. They are designed to preserve the validity of the plant safety analysis by ensuring that the plant is operated within the required conditions bounded by the analysis, and with the operable equipment that is assumed to mitigate the consequences of an accident. Technical specifications preserve the primary success path relied upon to detect and respond to accidents. This report describes requirements on thermal-hydraulic limits; limiting conditions for operation and surveillance for the reactor, power distribution control, instrumentation, process water system, emergency cooling and emergency shutdown systems, confinement systems, plant systems, electrical systems, components handling, and special test exceptions; design features; and administrative controls.

  10. Nuclear reactor vessel fuel thermal insulating barrier

    DOE Patents [OSTI]

    Keegan, C. Patrick; Scobel, James H.; Wright, Richard F.

    2013-03-19T23:59:59.000Z

    The reactor vessel of a nuclear reactor installation which is suspended from the cold leg nozzles in a reactor cavity is provided with a lower thermal insulating barrier spaced from the reactor vessel that has a hemispherical lower section that increases in volume from the center line of the reactor to the outer extent of the diameter of the thermal insulating barrier and smoothly transitions up the side walls of the vessel. The space between the thermal insulating harrier and the reactor vessel forms a chamber which can be flooded with cooling water through passive valving to directly cool the reactor vessel in the event of a severe accident. The passive inlet valve for the cooling water includes a buoyant door that is normally maintained sealed under its own weight and floats open when the cavity is Hooded. Passively opening steam vents are also provided.

  11. Safety control circuit for a neutronic reactor

    DOE Patents [OSTI]

    Ellsworth, Howard C. (Richland, WA)

    2004-04-27T23:59:59.000Z

    A neutronic reactor comprising an active portion containing material fissionable by neutrons of thermal energy, means to control a neutronic chain reaction within the reactor comprising a safety device and a regulating device, a safety device including means defining a vertical channel extending into the reactor from an aperture in the upper surface of the reactor, a rod containing neutron-absorbing materials slidably disposed within the channel, means for maintaining the safety rod in a withdrawn position relative to the active portion of the reactor including means for releasing said rod on actuation thereof, a hopper mounted above the active portion of the reactor having a door disposed at the bottom of the hopper opening into the vertical channel, a plurality of bodies of neutron-absorbing materials disposed within the hopper, and means responsive to the failure of the safety rod on actuation thereof to enter the active portion of the reactor for opening the door in the hopper.

  12. HOOPER BAY HOUSING ANALYSIS AND ENERGY FEASIBILITY REPORT

    SciTech Connect (OSTI)

    SEA LION CORPORATION; COLD CLIMATE HOUSING RESEARCH CENTER; SOLUTIONS FOR HEALTHY BREATHING; WHITNEY CONSTRUCTION

    2012-12-30T23:59:59.000Z

    Sea Lion applied for and received a grant from the Department of Energy (DOE) towards this end titled â??Energy Efficiency Development and Deployment in Indian Countryâ?ť. The initial objectives of the Hooper Bay Energy Efficiency Feasibility Study were to demonstrate a 30% reduction in residential/commercial energy usage and identify the economic benefits of implementing energy efficiency measures to the Tribe through: (1) partnering with Whitney Construction and Solutions for Healthy Breathing in the training and hire of 2 local energy assessors to conduct energy audits of 9 representative housing models and 2 commercial units in the community. These homes are representative of 52 homes constructed across different eras. (2) partnering with Cold Climate Housing Research Center to document current electrical and heating energy consumption and analyze data for a final feasibility report (3) assessing the economics of electricity & heating fuel usage; (4) projecting energy savings or fossil fuel reduction by modeling of improvement scenarios and cost feasibility The following two objectives will be completed after the publication of this report: (5) the development of materials lists for energy efficiency improvements (6) identifying financing options for the follow-up energy efficiency implementation phase.

  13. Deep porosity preservation in the Norphlet Formation, Mobil Bay, Alabama

    SciTech Connect (OSTI)

    Ajdukiewicz, J.M.; Paxton, S.T.; Szabvo, J.O. (Exxon Production Research Co., Houston, TX (United States))

    1991-03-01T23:59:59.000Z

    Compaction and pressure solution have commonly been assumed to destroy primary intergranular porosity in deeply buried sandstones. However, primary porosities of up to 20% are preserved at depths greater than 20,000 feet in the Norphlet Formation of Mobile Bay. Previous workers have called upon a number of mechanisms to preserve these high porosities in the Norphlet, specifically chlorite rim cements, gas emplacement, overpressuring, and decementation. In contrast, our study of data from 23 Norphlet wells, including 450 thin sections, indicates that these suggested mechanisms are not the primary cause of porosity preservation in the Norphlet. The authors propose an alternative interpretation: that in the Norphlet, as in other well-sorted, ductile-grain-poor sandstones, porosity loss from compaction did not go to completion under reservoir (premetamorphic) conditions, but stabilized at depths of about 5,000-8,000 feet and porosity values of about 26%. Porosity loss below these values is due to cementation. For cementation to occur, both an adequate source of cement and geochemical conditions favoring cement precipitation must be present. Computer simulations of Norphlet burial history, including post-depositional fluid-flow patterns, suggest that conditions favorable to quartz cementation never occurred in the bulk of the Norphlet because of the formation's stratigraphic position and isolation from a basinward source of silica-saturated fluids.

  14. Fast-acting nuclear reactor control device

    SciTech Connect (OSTI)

    Kotlyar, O.M.; West, P.B.

    1993-08-03T23:59:59.000Z

    A fast-acting nuclear reactor control device is described for controlling a safety control rod within the core of a nuclear reactor, the reactor controlled by a reactor control system, the device comprising: a safety control rod drive shaft and an electromagnetic clutch co-axial with the drive shaft operatively connected to the safety control rod for driving and positioning the safety control rod within or without the reactor core during reactor operation, the safety rod being oriented in a substantially vertical position to allow the rod to fall into the reactor core under the influence of gravity during shutdown of the reactor; the safety control rod drive shaft further operatively connected to a hydraulic pump such that operation of the drive shaft simultaneously drives and positions the safety control rod and operates the hydraulic pump such that a hydraulic fluid is forced into an accumulator, filling the accumulator with oil for the storage and supply of primary potential energy for safety control rod insertion such that the release of potential energy in the accumulator causes hydraulic fluid to flow through the hydraulic pump, converting the hydraulic pump to a hydraulic motor having speed and power capable of full length insertion and high speed driving of the safety control rod into the reactor core; a solenoid valve interposed between the hydraulic pump and the accumulator, said solenoid valve being a normally open valve, actuated to close when the safety control rod is out of the reactor during reactor operation; and further wherein said solenoid opens in response to a signal from the reactor control system calling for shutdown of the reactor and rapid insertion of the safety control rod into the reactor core, such that the opening of the solenoid releases the potential energy in the accumulator to place the safety control rod in a safe shutdown position.

  15. Nuclear reactor alignment plate configuration

    DOE Patents [OSTI]

    Altman, David A; Forsyth, David R; Smith, Richard E; Singleton, Norman R

    2014-01-28T23:59:59.000Z

    An alignment plate that is attached to a core barrel of a pressurized water reactor and fits within slots within a top plate of a lower core shroud and upper core plate to maintain lateral alignment of the reactor internals. The alignment plate is connected to the core barrel through two vertically-spaced dowel pins that extend from the outside surface of the core barrel through a reinforcement pad and into corresponding holes in the alignment plate. Additionally, threaded fasteners are inserted around the perimeter of the reinforcement pad and into the alignment plate to further secure the alignment plate to the core barrel. A fillet weld also is deposited around the perimeter of the reinforcement pad. To accomodate thermal growth between the alignment plate and the core barrel, a gap is left above, below and at both sides of one of the dowel pins in the alignment plate holes through with the dowel pins pass.

  16. Spectral shift reactor control method

    SciTech Connect (OSTI)

    Impink, A.J. Jr.

    1984-02-21T23:59:59.000Z

    A method of operating a pressurized water nuclear reactor is described which comprises the determining of the present core power and reactivity levels and predicting the change in such levels due to displacer rod movements. Groups or single clusters of displacer rods can be inserted or withdrawn based on the predicted core power and reactivity levels to change the core power level and power distribution thereby providing load follow capability, without changing control rod positions or coolant boron concentrations.

  17. The ARIES tokamak reactor study

    SciTech Connect (OSTI)

    Not Available

    1989-10-01T23:59:59.000Z

    The ARIES study is a community effort to develop several visions of tokamaks as fusion power reactors. The aims are to determine the potential economics, safety, and environmental features of a range of possible tokamak reactors, and to identify physics and technology areas with the highest leverage for achieving the best tokamak reactor. Three ARIES visions are planned, each having a different degree of extrapolation from the present data base in physics and technology. The ARIES-I design assumes a minimum extrapolation from current tokamak physics (e.g., 1st stability) and incorporates technological advances that can be available in the next 20 to 30 years. ARIES-II is a DT-burning tokamak which would operate at a higher beta in the 2nd MHD stability regime. It employs both potential advances in the physics and expected advances in technology and engineering. ARIES-II will examine the potential of the tokamak and the D{sup 3}He fuel cycle. This report is a collection of 14 papers on the results of the ARIES study which were presented at the IEEE 13th Symposium on Fusion Engineering (October 2-6, 1989, Knoxville, TN). This collection describes the ARIES research effort, with emphasis on the ARIES-I design, summarizing the major results, the key technical issues, and the central conclusions.

  18. Reference worldwide model for antineutrinos from reactors

    E-Print Network [OSTI]

    Marica Baldoncini; Ivan Callegari; Giovanni Fiorentini; Fabio Mantovani; Barbara Ricci; Virginia Strati; Gerti Xhixha

    2015-02-16T23:59:59.000Z

    Antineutrinos produced at nuclear reactors constitute a severe source of background for the detection of geoneutrinos, which bring to the Earth's surface information about natural radioactivity in the whole planet. In this framework we provide a reference worldwide model for antineutrinos from reactors, in view of reactors operational records yearly published by the International Atomic Energy Agency (IAEA). We evaluate the expected signal from commercial reactors for ongoing (KamLAND and Borexino), planned (SNO+) and proposed (Juno, RENO-50, LENA and Hanohano) experimental sites. Uncertainties related to reactor antineutrino production, propagation and detection processes are estimated using a Monte Carlo based approach, which provides an overall site dependent uncertainty on the signal in the geoneutrino energy window on the order of 3%. We also implement the off-equilibrium correction to the reference reactor spectra associated with the long-lived isotopes and we estimate a 2.4% increase of the unoscillated event rate in the geoneutrino energy window due to the storage of spent nuclear fuels in the cooling pools. We predict that the research reactors contribute to less than 0.2% to the commercial reactor signal in the investigated 14 sites. We perform a multitemporal analysis of the expected reactor signal over a time lapse of 10 years using reactor operational records collected in a comprehensive database published at www.fe.infn.it/antineutrino.

  19. Updating reactor control: mini-computers

    SciTech Connect (OSTI)

    Crawford, K.C.; Sandquist, G.M. [University of Utah, Salt Lake City, UT (United States)

    1984-07-01T23:59:59.000Z

    An aging reactor control console and a limited operating budget have impeded many research projects in the TRIGA reactor facility at the University of Utah. The, University's present console is Circa 1959 vintage and repairs to the console are frequently required which present many electronic problems to a staff with little electronic training. As an alternative to a single function control console we are developing a TRIGA control system based upon a mini-computer. The system hardware has been specified and the hardware is currently being acquired. The software will be programmed by the staff to customize the system to the reactor's physical systems and technical specifications. The software will be designed to monitor and control all reactor functions, control a pneumatic sample transfer system, acquire and analyze neutron activation data, provide reactor facility security surveillance, provide reactor documentation including online logging of physical parameters, and record regularly scheduled reactor calibrations and laboratory accounting procedures. The problem of hardware rewiring and changing technical specifications and changing safety system characteristics can be easily handled in the software. Our TRIGA reactor also functions as a major educational resource using available reactor based software. The computer control system can be employed to provide on-line training in reactor physics and kinetics. (author)

  20. Advanced Safeguards Approaches for New Fast Reactors

    SciTech Connect (OSTI)

    Durst, Philip C.; Therios, Ike; Bean, Robert; Dougan, A.; Boyer, Brian; Wallace, Rick L.; Ehinger, Michael H.; Kovacic, Don N.; Tolk, K.

    2007-12-15T23:59:59.000Z

    This third report in the series reviews possible safeguards approaches for new fast reactors in general, and the ABR in particular. Fast-neutron spectrum reactors have been used since the early 1960s on an experimental and developmental level, generally with fertile blanket fuels to “breed” nuclear fuel such as plutonium. Whether the reactor is designed to breed plutonium, or transmute and “burn” actinides depends mainly on the design of the reactor neutron reflector and the whether the blanket fuel is “fertile” or suitable for transmutation. However, the safeguards issues are very similar, since they pertain mainly to the receipt, shipment and storage of fresh and spent plutonium and actinide-bearing “TRU”-fuel. For these reasons, the design of existing fast reactors and details concerning how they have been safeguarded were studied in developing advanced safeguards approaches for the new fast reactors. In this regard, the design of the Experimental Breeder Reactor-II “EBR-II” at the Idaho National Laboratory (INL) was of interest, because it was designed as a collocated fast reactor with a pyrometallurgical reprocessing and fuel fabrication line – a design option being considered for the ABR. Similarly, the design of the Fast Flux Facility (FFTF) on the Hanford Site was studied, because it was a successful prototype fast reactor that ran for two decades to evaluate fuels and the design for commercial-scale fast reactors.