Applicability of ASST-A helium refrigeration system for JLab End Station Refrigerator

Science.gov (United States)

Hasan, N.; Knudsen, P.; Ganni, V.

2017-12-01

The MØLLER experiment at Jefferson Lab (JLab) is a high power (5 kW) liquid hydrogen target scheduled to be operational in the 12 GeV-era. At present, cryogenic loads and targets at three of JLab’s four experimental halls are supported by the End Station Refrigerator (ESR) - a CTI/Helix 1.5 kW 4.5 K refrigerator. It is not capable of supporting the high power target load and a capacity upgrade of the ESR cryogenic system is essential. The ASST-A helium refrigeration system is a 4 kW 4.5 K refrigerator. It was designed and used for the Superconducting Super Collider Lab (SSCL) magnet string test and later obtained by JLab after the cancellation of that project. The modified ASST-A refrigeration system, which will be called ESR-II along with a support flow from JLab’s Central Helium Liquefier (CHL) is considered as an option for the End Station Refrigerator capacity upgrade. The applicability of this system for ESR-II under varying load conditions is investigated. The present paper outlines the findings of this process study.

EXPERIENCE AND PLANS OF THE JLAB FEL FACILITY AS A USER FACILITY

Energy Technology Data Exchange (ETDEWEB)

Michelle D. Shinn

2007-08-26

Jefferson Lab's IR Upgrade FEL building was planned from the beginning to be a user facility, and includes an associated 600 m2 area containing seven laboratories. The high average power capability (multikilowatt-level) in the near-infrared (1-3 microns), and many hundreds of watts at longer wavelengths, along with an ultrafast (~ 1 ps) high PRF (10's MHz) temporal structure makes this laser a unique source for both applied and basic research. In addition to the FEL, we have a dedicated laboratory capable of delivering high power (many tens of watts) of broadband THz light. After commissioning the IR Upgrade, we once again began delivering beam to users in 2005. In this presentation, I will give an overview of the FEL facility and its current performance, lessons learned over the last two years, and a synopsis of current and future experiments.

JLab SRF Cavity Fabrication Errors, Consequences and Lessons Learned

International Nuclear Information System (INIS)

Marhauser, Frank

2011-01-01

Today, elliptical superconducting RF (SRF) cavities are preferably made from deep-drawn niobium sheets as pursued at Jefferson Laboratory (JLab). The fabrication of a cavity incorporates various cavity cell machining, trimming and electron beam welding (EBW) steps as well as surface chemistry that add to forming errors creating geometrical deviations of the cavity shape from its design. An analysis of in-house built cavities over the last years revealed significant errors in cavity production. Past fabrication flaws are described and lessons learned applied successfully to the most recent in-house series production of multi-cell cavities.

Implementation of the Polarized HD target at the Thomas Jefferson National Accelerator Facility

International Nuclear Information System (INIS)

Chaden Djalali; David Tedeschi

2007-01-01

The original goal of this proposal was to study frozen spin polarized targets (HD target and other technologies) and produce a conceptual design report for the implementation of such a target in the HALL B detector of the Thomas Jefferson National Accelerator Facility (JLab). During the first two years of the proposal, we came to the conclusion that the best suited target for JLab was a frozen spin target and helped with the design of such a target. We have not only achieved our original goal but have exceeded it by being involved in the actual building and testing of parts the target. The main reason for this success has been the hiring of a senior research associate, Dr. Oleksandr Dzyubak, who had more than 10 years of experience in the field of frozen spin polarized targets. The current grant has allowed the USC nuclear physics group to strengthen its role in the JLab collaboration and make important contribution to both the detector development and the scientific program

Commissioning and Testing the 1970's Era LASS Solenoid Magnet in JLab's Hall D

Energy Technology Data Exchange (ETDEWEB)

Ballard, Joshua T. [Jefferson Lab, Newport News, VA; Biallas, George H. [Jefferson Lab, Newport News, VA; Brown, G.; Butler, David E. [Jefferson Lab, Newport News, VA; Carstens, Thomas J. [Jefferson Lab, Newport News, VA; Chudakov, Eugene A. [Jefferson Lab, Newport News, VA; Creel, Jonathan D. [Jefferson Lab, Newport News, VA; Egiyan, Hovanes [Jefferson Lab, Newport News, VA; Martin, F.; Qiang, Yi [Jefferson Lab, Newport News, VA; Smith, Elton S. [Jefferson Lab, Newport News, VA; Stevens, Mark A. [Jefferson Lab, Newport News, VA; Spiegel, Scot L. [Jefferson Lab, Newport News, VA; Whitlatch, Timothy E. [Jefferson Lab, Newport News, VA; Wolin, Elliott J. [Carnegie Mellon University , Pittsburgh, PA; Ghoshal, Probir K. [Jefferson Lab, Newport News, VA

2015-06-01

JLab refurbished and reconfigured the LASS1, 1.85m bore Solenoid and installed it as the principal analysis magnet for nuclear physics in the newly constructed, Hall D at Jefferson Lab. The magnet contains four superconducting coils within an iron yoke. The magnet was built in the early1970's at Stanford Linear Accelerator Center and used a second time at Los Alamos National Laboratory. The coils were extensively refurbished and individually tested by JLab. A new Cryogenic Distribution Box provides cryogens and their control valving, current distribution bus, and instrumentation pass-through. A repurposed CTI 2800 refrigerator system and new transfer line complete the system. We describe the re-configuration, the process and problems of re-commissioning the magnet and the results of testing the completed magnet.

Search for low mass exotic baryons in one pion electroproduction data measured at JLAB

International Nuclear Information System (INIS)

Tatischeff, B.; Tomasi-Gustafsson, E.

2007-02-01

This paper aims to give further evidence for the existence of low mass exotic baryons. Narrow structures in baryonic missing mass or baryonic invariant mass were previously observed during the last ten years. Since their existence is sometimes questionable, the structure functions of one pion electroproduction cross sections, measured at JLAB, are studied to add information on the possible existence of these narrow exotic baryonic resonances. (authors)

Characterization and Suppression of the Electromagnetic Interference Induced Phase Shift in the JLab FEL Photo - Injector Advanced Drive Laser System

Energy Technology Data Exchange (ETDEWEB)

F. G. Wilson, D. Sexton, S. Zhang

2011-09-01

The drive laser for the photo-cathode gun used in the JLab Free Electron Laser (FEL) facility had been experiencing various phase shifts on the order of tens of degrees (>20{sup o} at 1497 MHz or >40ps) when changing the Advanced Drive Laser (ADL) [2][3][4] micro-pulse frequencies. These phase shifts introduced multiple complications when trying to setup the accelerator for operation, ultimately inhibiting the robustness and overall performance of the FEL. Through rigorous phase measurements and systematic characterizations, we determined that the phase shifts could be attributed to electromagnetic interference (EMI) coupling into the ADL phase control loop, and subsequently resolved the issue of phase shift to within tenths of a degree (<0.5{sup o} at 1497 MHz or <1ps). The diagnostic method developed and the knowledge gained through the entire process will prove to be invaluable for future designs of similar systems.

Workshop on Physics with Neutral Kaon Beam at JLab (KL2016) Mini-Proceedings

Energy Technology Data Exchange (ETDEWEB)

Strakovsky, Igor I. [George Washington Univ., Washington, DC (United States); Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Amaryan, Moskov [Old Dominion Univ., Norfolk, VA (United States); Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Chudakov, Eugene A. [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Meyer, Curtis A. [Carnegie Mellon Univ., Pittsburgh, PA (United States); Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Pennington, Michael R. [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Ritman, James L. [Forschungszentrum Juelich Institut fuer Kernphysik

2016-05-01

The KL2016 Workshop is following the Letter of Intent LoI12-15-001 "Physics Opportunities with Secondary KL beam at JLab" submitted to PAC43 with the main focus on the physics of excited hyperons produced by the Kaon beam on unpolarized and polarized targets with GlueX setup in Hall D. Such studies will broaden a physics program of hadron spectroscopy extending it to the strange sector. The Workshop was organized to get a feedback from the community to strengthen physics motivation of the LoI and prepare a full proposal.

The JLab high power ERL light source

International Nuclear Information System (INIS)

Neil, G.R.; Behre, C.; Benson, S.V.

2006-01-01

A new THz/IR/UV photon source at Jefferson Lab is the first of a new generation of light sources based on an Energy-Recovered (superconducting) Linac (ERL). The machine has a 160MeV electron beam and an average current of 10mA in 75MHz repetition rate hundred femtosecond bunches. These electron bunches pass through a magnetic chicane and therefore emit synchrotron radiation. For wavelengths longer than the electron bunch the electrons radiate coherently a broadband THz ∼ half cycle pulse whose average brightness is >5 orders of magnitude higher than synchrotron IR sources. Previous measurements showed 20W of average power extracted [Carr, et al., Nature 420 (2002) 153]. The new facility offers simultaneous synchrotron light from the visible through the FIR along with broadband THz production of 100fs pulses with >200W of average power. The FELs also provide record-breaking laser power [Neil, et al., Phys. Rev. Lett. 84 (2000) 662]: up to 10kW of average power in the IR from 1 to 14μm in 400fs pulses at up to 74.85MHz repetition rates and soon will produce similar pulses of 300-1000nm light at up to 3kW of average power from the UV FEL. These ultrashort pulses are ideal for maximizing the interaction with material surfaces. The optical beams are Gaussian with nearly perfect beam quality. See www.jlab.org/FEL for details of the operating characteristics; a wide variety of pulse train configurations are feasible from 10ms long at high repetition rates to continuous operation. The THz and IR system has been commissioned. The UV system is to follow in 2005. The light is transported to user laboratories for basic and applied research. Additional lasers synchronized to the FEL are also available. Past activities have included production of carbon nanotubes, studies of vibrational relaxation of interstitial hydrogen in silicon, pulsed laser deposition and ablation, nitriding of metals, and energy flow in proteins. This paper will present the status of the system and

The JLab high power ERL light source

Energy Technology Data Exchange (ETDEWEB)

G.R. Neil; C. Behre; S.V. Benson; M. Bevins; G. Biallas; J. Boyce; J. Coleman; L.A. Dillon-Townes; D. Douglas; H.F. Dylla; R. Evans; A. Grippo; D. Gruber; J. Gubeli; D. Hardy; C. Hernandez-Garcia; K. Jordan; M.J. Kelley; L. Merminga; J. Mammosser; W. Moore; N. Nishimori; E. Pozdeyev; J. Preble; R. Rimmer; Michelle D. Shinn; T. Siggins; C. Tennant; R. Walker; G.P. Williams and S. Zhang

2005-03-19

A new THz/IR/UV photon source at Jefferson Lab is the first of a new generation of light sources based on an Energy-Recovered, (superconducting) Linac (ERL). The machine has a 160 MeV electron beam and an average current of 10 mA in 75 MHz repetition rate hundred femtosecond bunches. These electron bunches pass through a magnetic chicane and therefore emit synchrotron radiation. For wavelengths longer than the electron bunch the electrons radiate coherently a broadband THz {approx} half cycle pulse whose average brightness is > 5 orders of magnitude higher than synchrotron IR sources. Previous measurements showed 20 W of average power extracted[1]. The new facility offers simultaneous synchrotron light from the visible through the FIR along with broadband THz production of 100 fs pulses with >200 W of average power. The FELs also provide record-breaking laser power [2]: up to 10 kW of average power in the IR from 1 to 14 microns in 400 fs pulses at up to 74.85 MHz repetition rates and soon will produce similar pulses of 300-1000 nm light at up to 3 kW of average power from the UV FEL. These ultrashort pulses are ideal for maximizing the interaction with material surfaces. The optical beams are Gaussian with nearly perfect beam quality. See www.jlab.org/FEL for details of the operating characteristics; a wide variety of pulse train configurations are feasible from 10 microseconds long at high repetition rates to continuous operation. The THz and IR system has been commissioned. The UV system is to follow in 2005. The light is transported to user laboratories for basic and applied research. Additional lasers synchronized to the FEL are also available. Past activities have included production of carbon nanotubes, studies of vibrational relaxation of interstitial hydrogen in silicon, pulsed laser deposition and ablation, nitriding of metals, and energy flow in proteins. This paper will present the status of the system and discuss some of the discoveries we have made

Conducting Computer Security Assessments at Nuclear Facilities

International Nuclear Information System (INIS)

2016-06-01

Computer security is increasingly recognized as a key component in nuclear security. As technology advances, it is anticipated that computer and computing systems will be used to an even greater degree in all aspects of plant operations including safety and security systems. A rigorous and comprehensive assessment process can assist in strengthening the effectiveness of the computer security programme. This publication outlines a methodology for conducting computer security assessments at nuclear facilities. The methodology can likewise be easily adapted to provide assessments at facilities with other radioactive materials

Progress of Bep Treatments on Nb at JLAB

International Nuclear Information System (INIS)

Wu, A.T.; Jin, S.; Rimmer, R.A.; Lu, X.Y.; Zhao, K.

2010-01-01

Recent experimental results have indicated that Buffered Electropolishing (BEP) is a promising candidate for the next generation of surface treatment technique for Nb superconducting radio frequency (SRF) cavities to be used in particle accelerators. In order to lay the foundation for using BEP as the next generation surface treatment technique for Nb SRF cavities, some fundamental aspects of BEP treatments for Nb have to be investigated. In this report, recent progress on BEP study at JLab is shown. Improvements on the existing vertical BEP are made to allow water cooling from outside of a Nb single cell cavity in addition to cooling provided by acid circulation so that the temperature of the cavity can be stable during processing. Some investigation on the electrolyte mixture was performed to check the aging effect of the electrolyte. It is shown that good polishing results can still be obtained on Nb at a current density of 171 mA/cm when the BEP electrolyte was at the stationary condition and was more than 1.5 years old.

Tough and Conductive Hybrid Hydrogels Enabling Facile Patterning.

Science.gov (United States)

Zhu, Fengbo; Lin, Ji; Wu, Zi Liang; Qu, Shaoxing; Yin, Jun; Qian, Jin; Zheng, Qiang

2018-04-25

Conductive polymer hydrogels (CPHs) that combine the unique properties of hydrogels and electronic properties of conductors have shown their great potentials in wearable/implantable electronic devices, where materials with remarkable mechanical properties, high conductivity, and easy processability are demanding. Here, we have developed a new type of polyion complex/polyaniline (PIC/PAni) hybrid hydrogels that are tough, conductive, and can be facilely patterned. The incorporation of conductive phase (PAni) into PIC matrix through phytic acid resulted in hybrid gels with ∼65 wt % water; high conductivity while maintaining the key viscoelasticity of the tough matrix. The gel prepared from 1 M aniline (Ani) exhibited the breaking strain, fracture stress, tensile modulus, and electrical conductivity of 395%, 1.15 MPa, 5.31 MPa, and 0.7 S/m, respectively, superior to the most existing CPHs. The mechanical and electrical performance of PIC/PAni hybrid hydrogels exhibited pronounced rate-dependent and self-recovery behaviors. The hybrid gels can effectively detect subtle human motions as strain sensors. Alternating conductive/nonconductive patterns can be readily achieved by selective Ani polymerization using stencil masks. This facile patterning method based on PIC/PAni gels can be readily scaled up for fast fabrication of wavy gel circuits and multichannel sensor arrays, enabling real-time monitoring of the large-extent and large-area deformations with various sensitivities.

Facile synthesis of degradable and electrically conductive polysaccharide hydrogels.

Science.gov (United States)

Guo, Baolin; Finne-Wistrand, Anna; Albertsson, Ann-Christine

2011-07-11

Degradable and electrically conductive polysaccharide hydrogels (DECPHs) have been synthesized by functionalizing polysaccharide with conductive aniline oligomers. DECPHs based on chitosan (CS), aniline tetramer (AT), and glutaraldehyde were obtained by a facile one-pot reaction by using the amine group of CS and AT under mild conditions, which avoids the multistep reactions and tedious purification involved in the synthesis of degradable conductive hydrogels in our previous work. Interestingly, these one-pot hydrogels possess good film-forming properties, electrical conductivity, and a pH-sensitive swelling behavior. The chemical structure and morphology before and after swelling of the hydrogels were verified by FT-IR, NMR, and SEM. The conductivity of the hydrogels was tuned by adjusting the content of AT. The swelling ratio of the hydrogels was altered by the content of tetraaniline and cross-linker. The hydrogels underwent slow degradation in a buffer solution. The hydrogels obtained by this facile approach provide new possibilities in biomedical applications, for example, biodegradable conductive hydrogels, films, and scaffolds for cardiovascular tissue engineering and controlled drug delivery.

Production of Copper-Plated Beamline Bellows and Spools for LCLS-II

Energy Technology Data Exchange (ETDEWEB)

Wilson, Katherine M. [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Carpenter, Brian C. [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Daly, Ed [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Huque, Naeem A. [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Peshehonoff, Ted [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Arkan, Tug [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Lunin, A. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Premo, K. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States)

2017-05-01

The SLAC National Accelerator Laboratory is currently constructing a major upgrade to its accelerator, the Linac Coherent Light Source II (LCLS-II). Several Department of Energy national laboratories, including the Thomas Jefferson National Accelerator Facility (JLab) and Fermi National Accelerator Laboratory (FNAL), are participating in this project. The 1.3-GHz cryomodules for this project consist of eight cavities separated by bellows (expansion joints) and spools (tube sections), which are copper plated for RF conduction. JLab is responsible for procurement of these bellows and spools, which are delivered to JLab and FNAL for assembly into cryomodules. Achieving accelerator-grade copper plating is always a challenge and requires careful specification of requirements and application of quality control processes. Due to the demanding technical requirements of this part, JLab implemented procurement strategies to make the process more efficient as well as provide process redundancy. This paper discusses the manufacturing challenges that were encountered and resolved, as well as the strategies that were employed to minimize the impact of any technical issues.

Accurate measurement of the electron beam polarization in JLab Hall A using Compton polarimetry

International Nuclear Information System (INIS)

Escoffier, S.; Bertin, P.Y.; Brossard, M.; Burtin, E.; Cavata, C.; Colombel, N.; Jager, C.W. de; Delbart, A.; Lhuillier, D.; Marie, F.; Mitchell, J.; Neyret, D.; Pussieux, T.

2005-01-01

A major advance in accurate electron beam polarization measurement has been achieved at Jlab Hall A with a Compton polarimeter based on a Fabry-Perot cavity photon beam amplifier. At an electron energy of 4.6GeV and a beam current of 40μA, a total relative uncertainty of 1.5% is typically achieved within 40min of data taking. Under the same conditions monitoring of the polarization is accurate at a level of 1%. These unprecedented results make Compton polarimetry an essential tool for modern parity-violation experiments, which require very accurate electron beam polarization measurements

Theory Support for the Excited Baryon Analysis Program at the JLAB 12 GeV Upgrade

Energy Technology Data Exchange (ETDEWEB)

Burkert, Volker; Lee, Tsung-Shung; Mokeev, Viktor; Aznauryan, Inna; Braun, Vladimir; Capstick, Simon; Cloet, Ian; Edwards, Robert; Gianinni, M.; Lin, Huey-Wen; Roberts, C.D.; Stoler, Paul; Zhao, Qiang; Zou, Bing-Song

2009-01-01

This document summarizes the contributions of the Electromagnetic $\\gamma_vNN^*$ Transition Form Factors workshop participants that provide theoretical support of the excited baryon program at the 12 GeV energy upgrade at JLab. The main objectives of the workshop were (a) review the status of the $\\gamma_vNN^*$ transition form factors extracted from the meson electroproduction data, (b) call for the theoretical interpretations of the extracted $N$-$N^*$ transition form factors, that enable access to the mechanisms responsible for the N* formation and to their emergence from QCD.

Application of JLab 12GeV helium refrigeration system for the FRIB accelerator at MSU

International Nuclear Information System (INIS)

Ganni, V.; Knudsen, P.; Arenius, D.; Casagrande, F.

2014-01-01

The planned approach to have a turnkey helium refrigeration system for the MSU-FRIB accelerator system, encompassing the design, fabrication, installation and commissioning of the 4.5-K refrigerator cold box(es), cold compression system, warm compression system, gas management, oil removal and utility/ancillary systems, was found to be cost prohibitive. Following JLab’s suggestion, MSU-FRIB accelerator management made a formal request to evaluate the applicability of the recently designed 12GeV JLab cryogenic system for this application. The following paper will outline the findings and the planned approach for the FRIB helium refrigeration system

Electroweak Measurements of Neutron Densities in CREX and PREX at JLab, USA

Energy Technology Data Exchange (ETDEWEB)

Horowitz, Charles J. [Indiana U.; Kumar, Krishna S. [UMass; Michaels, Robert W. [JLAB

2014-02-01

Measurement of the parity-violating electron scattering asymmetry is an established technique at Jefferson Lab and provides a new opportunity to measure the weak charge distribution and hence pin down the neutron radius in nuclei in a relatively clean and model-independent way. This is because the Z boson of the weak interaction couples primarily to neutrons. We will describe the PREX and CREX experiments on ${}^{208}$Pb and ${}^{48}$Ca respectively; these are both doubly-magic nuclei whose first excited state can be discriminated by the high resolution spectrometers at JLab. The heavier lead nucleus, with a neutron excess, provides an interpretation of the neutron skin thickness in terms of properties of bulk neutron matter. For the lighter ${}^{48}$Ca nucleus, which is also rich in neutrons, microscopic nuclear theory calculations are feasible and are sensitive to poorly constrained 3-neutron forces.

Parity Violation in Deep Inelastic Scattering in Hall C at JLab

Science.gov (United States)

Dalton, Mark Macrae; Keppel, Cynthia; Paschke, Kent

2017-09-01

The measurement of parity-violation in inclusive electron deep inelastic scattering (DIS) from a proton or deuteron target can be used to study the flavor structure of the nucleon. While valence quark parton distribution functions (PDF) can be probed in high- x measurements such as with the proposed SoLID spectrometer, complementary measurements are possible at moderate x 0.1 where the sea quarks may still play a significant role. In particular, such measurements would provide a cleanly interpretable measurement of the strange quark PDF. These measurements are possible with the upgraded CEBAF accelerator at JLab and do not require significant new experimental hardware. The prospects and potential impacts of such a measurement will be presented. This material is based upon work supported by the U.S. Department of Energy, Office of Science, Office of Nuclear Physics under Contract DE-AC05-06OR23177 and DE-FG02-07ER41522.

Commissioning and operational results of the 12 GeV helium compression system at Jlab

Energy Technology Data Exchange (ETDEWEB)

Knudsen, Peter N. [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Ganni, Venkatarao [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Dixon, Kelly D. [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Norton, Robert O. [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Creel, Jonathan D. [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States)

2015-12-01

The new compressor system at Jefferson Lab (JLab) for the 12 GeV upgrade was commissioned in the spring of 2013 and incorporates many design changes, discussed in previous publications, to improve the operational range, efficiency, reliability and maintainability as compared to previous compressor skids used for this application. The 12 GeV helium compression system has five compressors configured with four pressure levels supporting three pressure levels in the new cold box. During compressor commissioning the compressors were operated independent of the cold box over a wide range of process conditions to verify proper performance including adequate cooling and oil removal. Isothermal and volumetric efficiencies over these process conditions for several built-involume ratios were obtained. This paper will discuss the operational envelope results and the modifications/improvements incorporated into the skids.

Parity Violation in DIS region with SoLID at the upgraded 12 GeV JLab

Science.gov (United States)

Tian, Ye; SoLID Collaboration

2017-09-01

In this talk, an overview of PVDIS future experiment by using a Solenoidal Large Intensity Device (SoLID) at Jefferson Lab (JLab) Hall A with the 12 GeV upgrade, along with a brief description of the proposed SoLID spectrometer is discussed. We will obtain data with high statistic and large kinematic coverage for Bjorken 0.3 physics of searching for charge asymmetry violation in PDF's and higher-twist effects with quark-quark correlations. In addition, the proton target experiment can be a powerful probe of the d / u ratio at high x without any nuclear correction. The designed SoLID spectrometer with its unique feature of high luminosity and large acceptance provides an opportunity to probe physics beyond the Standard Model.

Proposal for a slow positron facility at Jefferson National Laboratory

Science.gov (United States)

Mills, Allen P.

2018-05-01

One goal of the JPos-17 International Workshop on Physics with Positrons was to ascertain whether it would be a good idea to expand the mission of the Thomas Jefferson National Accelerator Facility (JLab) to include science with low energy (i.e. "slow") spin polarized positrons. It is probably true that experimentation with slow positrons would potentially have wide-ranging benefits comparable to those obtained with neutron and x-ray scattering, but it is certain that the full range of these benefits will never be fully available without an infrastructure comparable to that of existing neutron and x-ray facilities. The role for Jefferson Laboratory would therefore be to provide and maintain (1) a dedicated set of machines for making and manipulating high intensity, high brightness beams of polarized slow positrons; (2) a suite of unique and easily used instruments of wide utility that will make efficient use of the positrons; and (3) a group of on-site positron scientists to provide scientific leadership, instrument development, and user support. In this note some examples will be given of the science that might make a serious investment in a positron facility worthwhile. At the same time, the lessons learned from various proposed and successful positron facilities will be presented for consideration.

The DarkLight Experiment at the JLab FEL

Science.gov (United States)

Fisher, Peter

2013-10-01

DarkLight will study the production of gauge bosons associated with Dark Forces theories in the scattering of 100 MeV electrons on proton a target. DarkLight is a spectrometer to measure all the final state particles in e- + p -->e- + p +e- +e+ . QED allows this process and the invariant mass distribution of the e+e- pair is a continuum from nearly zero to nearly the electron beam energy. Dark Forces theories, which allow the dark matter mass scale to be over 1 TeV, predict a gauge boson A' in the mass range of 10-1,000 MeV and decays to an electron-positron pair with an invariant mass of mA'. We aim to search for this process using the 100 MeV, 10 mA electron beam at the JLab Free Electron Laser impinging on a hydrogen target with a 1019 cm-2 density. The resulting luminosity of 6 ×1035/cm2-s gives the experiment enough sensitivity to probe A' couplings of 10-9 α . DarkLight is unique in its design to detect all four particles in the final state. The leptons will be measured in a large high-rate TPC and a silicon sensor will measure the protons. A 0.5 T solenoidal magnetic field provides the momentum resolution and focuses the copious Møller scattering background down the beam line, away from the detectors. A first beam test has shown the FEL beam is compatible with the target design and that the hall backgrounds are manageable. The experiment has been approved by Jefferson Lab for first running in 2017.

Implementation of conduct of operations at Paducah uranium hexafluoride (UF{sub 6}) sampling and transfer facility

Energy Technology Data Exchange (ETDEWEB)

Penrod, S.R. [Martin Marietta Energy Systems, Inc., KY (United States)

1991-12-31

This paper describes the initial planning and actual field activities associated with the implementation of {open_quotes}Conduct of Operations{close_quotes}. Conduct of Operations is an operating philosophy that was developed through the Institute of Nuclear Power Operations (INPO). Conduct of Operations covers many operating practices and is intended to provide formality and discipline to all aspects of plant operation. The implementation of these operating principles at the UF{sub 6} Sampling and Transfer Facility resulted in significant improvements in facility operations.

Implementation of conduct of operations at Paducah uranium hexafluoride (UF{sub 6}) sampling and transfer facility

Energy Technology Data Exchange (ETDEWEB)

Penrod, S.R. [Martin Marietta Energy Systems, Inc., KY (United States)

1991-12-31

This paper describes the initial planning and actual field activities associated with the implementation of {open_quotes}Conduct of Operations{close_quotes}, Conduct of Operations is an operating philosophy that was developed through the Institute of Nuclear Power Operations (INPO). Conduct of Operations covers many operating practices and is intended to provide formality and discipline to all aspects of plant operation. The implementation of these operating principles at the UF{sub 6} Sampling and Transfer Facility resulted in significant improvements in facility operations.

FRIB Cryogenic Plant Status

Energy Technology Data Exchange (ETDEWEB)

Dixon, Kelly D. [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Ganni, Venkatarao [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Knudsen, Peter N. [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Casagranda, Fabio [Michigan State Univ., East Lansing, MI (United States)

2015-12-01

After practical changes were approved to the initial conceptual design of the cryogenic system for MSU FRIB and an agreement was made with JLab in 2012 to lead the design effort of the cryogenic plant, many activities are in place leading toward a cool-down of the linacs prior to 2018. This is mostly due to using similar equipment used at CHLII for the 12 GeV upgrade at JLab and an aggressive schedule maintained by the MSU Conventional Facilities department. Reported here is an updated status of the cryogenic plant, including the equipment procurement status, plant layout, facility equipment and project schedule.

Procedures for conducting probabilistic safety assessment for non-reactor nuclear facilities

International Nuclear Information System (INIS)

2002-01-01

A well performed and adequately documented safety assessment of a nuclear facility will serve as a basis to determine whether the facility complies with the safety objectives, principles and criteria as stipulated by the national regulatory body of the country where the facility is in operation. International experience shows that the practices and methodologies used to perform safety assessments and periodic safety re-assessment for non-reactor nuclear facilities differ significantly from county to country. Most developing countries do not have methods and guidance for safety assessment that are prescribed by the regulatory body. Typically the safety evaluation for the facility is based on a case by case assessment. Whilst conservative deterministic analyses are predominantly used as a licensing basis in many countries, recently probabilistic safety assessment (PSA) techniques have been applied as a useful complementary tool to support safety decision making. The main benefit of PSA is to provide insights into the safety aspects of facility design and operation. PSA points up the potential environmental impacts of postulated accidents, including the dominant risk contributors, and enables safety analysts to compare options for reducing risk. In order to advise on how to apply PSA methodology for the safety assessment of non-reactor nuclear facilities, the IAEA organized several consultants meetings, which led to the preparation of this TECDOC. This document is intended as guidance for the conduct of PSA in non-nuclear facilities. The main emphasis here is on the general procedural steps of a PSA that is specific for a non-reactor nuclear facility, rather than the details of the specific methods. The report is directed at technical staff managing or performing such probabilistic assessments and to promote a standardized framework, terminology and form of documentation for these PSAs. It is understood that the level of detail implied in the tasks presented in this

Compact X-ray source at STF (Super Conducting Accelerator Test Facility)

International Nuclear Information System (INIS)

Urakawa, J

2012-01-01

KEK-STF is a super conducting linear accelerator test facility for developing accelerator technologies for the ILC (International Linear Collider). We are supported in developing advanced accelerator technologies using STF by Japanese Ministry (MEXT) for Compact high brightness X-ray source development. Since we are required to demonstrate the generation of high brightness X-ray based on inverse Compton scattering using super conducting linear accelerator and laser storage cavity technologies by October of next year (2012), the design has been fixed and the installation of accelerator components is under way. The necessary technology developments and the planned experiment are explained.

Standard protocol for conducting pre-operational environmental surveillance around nuclear facilities

International Nuclear Information System (INIS)

Hegde, A.G.; Verma, P.C.; Rajan, M.P.

2009-02-01

This document presents the standard procedures for evaluation of site specific environmental transfer factors around NPP sites. The scope of this document is to provide standard protocol to be followed for conducting pre-operational environmental surveillance around nuclear facilities. Such surveillances have been proposed to be carried out by university professionals under DAE-BRNS projects. This document contains a common methodology in terms of sampling, processing, measurements and analysis of elemental/radionuclides, while keeping the site specific requirements also in place. (author)

Standard protocol for conducting pre-operational environmental surveillance around nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Hegde, A G; Verma, P C; Rajan, M P [Health Safety and Environment Group, Bhabha Atomic Research Centre, Mumbai (India)

2009-02-15

This document presents the standard procedures for evaluation of site specific environmental transfer factors around NPP sites. The scope of this document is to provide standard protocol to be followed for conducting pre-operational environmental surveillance around nuclear facilities. Such surveillances have been proposed to be carried out by university professionals under DAE-BRNS projects. This document contains a common methodology in terms of sampling, processing, measurements and analysis of elemental/radionuclides, while keeping the site specific requirements also in place. (author)

Measurement of the photon electroproduction cross section at JLAB with the goal of performing a Rosenbluth separation of the DVCS contribution

Energy Technology Data Exchange (ETDEWEB)

Jimenez-Arguello, Alejandro Marti [Univ. of Paris, Orsay (France). Inst. of Nuclear Physics

2014-07-11

The study of the inner structure of hadrons allows us to understand the nature of the interactions between partons, quarks and gluons, described by Quantum Chromodynamics. The elastic scattering reactions, which have been studied in order to measure the nucleon form factors, are included in this frame. The inelastic scattering reactions are also included in this frame, they allow us to obtain information about the nucleon structure thanks to the development of the parton distribution functions (PDFs). While through elastic scattering we can obtain information about the charge distribution of the nucleon, and hence, about the spatial distribution of the partons, through inelastic scattering we obtain information about the momentum distributions of partons, by employing the PDFs. However, we can study the exclusive inelastic scattering reactions, such as the Deeply Virtual Compton Scattering (DVCS), wich allow us to access to the spatial and momentum distributions simultaneously. This is possible thanks to the generalized parton distributions (GPDs), which allow us to correlate both types of distributions. The process known as DVCS is the easiest way to access the GPDs. This process can be expressed as the scattering of an electron by a proton by means of a virtual photon with the result of the scattered initial particles plus a real photon. We find a process competing with DVCS known as Bethe-Heitler (BH), in which the real photon is radiated by the lepton rather than the quark. Due to the small cross section of DVCS, of the order of nb, in order to conduct these kind of experiments it is necessary to make use of facilities capable of providing high beam intensities. One of these facilities is the Thomas Jefferson National Accelerator Facility , where the experiment JLab E07-007, "Complete Separation of Virtual Photon and π⁰ Electroproduction Observables of Unpolarized Protons", took place during the months of October to December of 2010. The main goal of this

Results of gap conductance tests in the power burst facility

International Nuclear Information System (INIS)

Garner, R.W.; Sparks, D.T.

1977-01-01

Light water reactor (LWR) fuel rod behavior studies are being conducted by the Thermal Fuels Behavior Program of EG and G Idaho, Inc. These studies are being performed under contract to the Energy Research and Development Adminstration at the Idaho National Engineering Laboratory (INEL), as part of the Nuclear Regulatory Commission's Water Reactor Safety Research Fuel Behavior Program. Experimental data for verification of analytical models developed to predict light water nuclear fuel rod behavior under normal and postulated accident conditions are being obtained from a variety of in-reactor and out-of-reactor experiments. This paper summarizes the results of tests performed in the Power Burst Facility (PBF) to obtain data from which the thermal response, gap conductance, and stored energy of LWR fuel rods can be determined. Primary objectives of the PBF gap conductance test program are (a) to obtain data on a variety of pressurized water reactor (PWR) and boiling water reactor (BWR) fuel rod designs, under a wide range of operating conditions, from which gap conductance values can be determined and (b) to evaluate experimentally the power oscillation method for measuring the gap conductance and thermal response of a fresh or burned LWR fuel rod. Tests have been performed with both irradiated and unirradiated PWR-type fuel and with fresh BWR-type fuel rods. Some PWR rod test results are described, and the thermal response data from BWR rod tests are discussed in greater detail. Comparisons are made of gap conductance values determined by the tests with analytically calculated values using the Fuel Rod Analysis Program-Transient (FRAP-T) computer code. These comparisons provide insight into both the experimental measurements methods and the validity of the gap conductance models

Progress on the design of the polarized Medium-energy Electron Ion Collider at JLAB

Energy Technology Data Exchange (ETDEWEB)

Lin, F.; Bogacz, A.; Brindza, P.; Camsonne, A.; Daly, E.; Derbenev, Ya. S.; Douglas, D.; Ent, R.; Gaskell, D.; Geng, R.; Grames, J.; Guo, J.; Harwood, L.; Hutton, A.; Jordan, K.; Kimber, A.; Krafft, G.; Li, R.; Michalski, T.; Morozov, V. S.; Nadel-Turonski, P.; /Jefferson Lab /Argonne /DESY /Moscow , Inst. Phys. Tech., Dolgoprydny /Dubna, JINR /Northern Illinois U. /Old Doominion U. /Novosibirsk, GOO Zaryad /SLAC /Texas A-M

2015-07-14

The Medium-energy Electron Ion Collider (MEIC) at JLab is designed to provide high luminosity and high polarization needed to reach new frontiers in the exploration of nuclear structure. The luminosity, exceeding 10³³ cm^-2s^-1 in a broad range of the center-of-mass (CM) energy and maximum luminosity above 10³⁴ cm^-2s^-1, is achieved by high-rate collisions of short small-emittance low-charge bunches made possible by high-energy electron cooling of the ion beam and synchrotron radiation damping of the electron beam. The polarization of light ion species (p, d, ³He) can be easily preserved and manipulated due to the unique figure-8 shape of the collider rings. A fully consistent set of parameters have been developed considering the balance of machine performance, required technical development and cost. This paper reports recent progress on the MEIC accelerator design including electron and ion complexes, integrated interaction region design, figure-8-ring-based electron and ion polarization schemes, RF/SRF systems and ERL-based high-energy electron cooling. Luminosity performance is also presented for the MEIC baseline design.

MHD studies conducted at the U-25 Facility (V)

International Nuclear Information System (INIS)

1977-01-01

The U-25 facility research status is summarized. The main rated parameters of the U-25 facility have been attained, and the main stages of the facility shakedown are briefly discussed. Experimental studies have recently been focused on design of the RM frame channel, development of a method for processing experimental data obtained at the U-25 facility, study of the seed injection/removal system, and steam generator studies

CATHARE 2 analysis of the small break LOCA experiment SP-SB-03, conducted in SPES facility

International Nuclear Information System (INIS)

Meloni, P.

1995-01-01

SPES integral test facility is a scale model of a commercial three-loop PWR plant, making the simulation of a wide range of accident scenarios possible. A Small Break Loss of Coolant test was carried out in this facility in 1991 to serve as a counterpart of tests conducted on BETHSY (France), LSTF (Japan) and LOBI (EC) facilities. A post-test analysis of this test, performed with CATHARE 2 code was realized by ENEA in the framework of the co-operation ENEA-CEA on advanced reactors. This paper presents a survey of the results of the post-test calculation. (author). 5 refs, 11 figs, 3 tabs

Mechanical and Thermal Design of the CEBAF Hall A Beam Calorimeter

CERN Document Server

Bevins, Michael E; Degtiarenko, Pavel; Dillon-Townes, Lawrence A; Freyberger, Arne; Gilman, Ronald; Saha, Arun; Slachtouski, Stephanie

2005-01-01

A calorimeter has been proposed to provide 0.5% - 1.0% absolute measurements of beam current in the Hall A end station of the Thomas Jefferson National Accelerator Facility (JLab) CEBAF machine. Silver and copper calorimeters built in the 1960's achieved precisions of about 1%. Modern powder metallurgy processes have produced high density, high thermal conductivity tungsten-copper composite materials that will minimize beam loss while maintaining a rapid thermal response time. Heat leaks will be minimized by mounting the mass in vacuum on glass ceramic mounts. A conduction cooling scheme utilizes an advanced carbon fiber compliant thermal interface material. Transient finite difference and finite element models were developed to estimate heat leaks and thermal response times.

Separate effects tests to determine the effective thermal conductivity in the PBMR HTTU test facility

Energy Technology Data Exchange (ETDEWEB)

Rousseau, P.G., E-mail: pgr@mtechindustrial.com [School of Mechanical and Nuclear Engineering, North-West University, Private Bag X6001, Potchefstroom 2520 (South Africa); Toit, C.G. du; Antwerpen, W. van [School of Mechanical and Nuclear Engineering, North-West University, Private Bag X6001, Potchefstroom 2520 (South Africa); Antwerpen, H.J. van [M-Tech Industrial (Pty) Ltd., PO Box 19855, Noordbrug 2522 (South Africa)

2014-05-01

Thermal-fluid simulations are used extensively to predict the maximum fuel temperatures, flows, pressure drops and thermal capacitance of pebble bed gas cooled reactors in support of the reactor safety case. The PBMR company developed the HTTU non-nuclear test facility in cooperation with M-Tech Industrial (Pty) Ltd. and the North-West University in South Africa to conduct comprehensive separate effects tests as well as integrated effects tests to study the different thermal-fluid phenomena. This paper describes the separate effects tests that were conducted to determine the effective thermal conductivity through the pebble bed under near-vacuum conditions and temperatures up to 1200 °C. It also presents the measured temperature distributions and the methodology applied in the data analysis to derive the resultant values of effective thermal conductivity and its associated uncertainty.

Separate effects tests to determine the effective thermal conductivity in the PBMR HTTU test facility

International Nuclear Information System (INIS)

Rousseau, P.G.; Toit, C.G. du; Antwerpen, W. van; Antwerpen, H.J. van

2014-01-01

Thermal-fluid simulations are used extensively to predict the maximum fuel temperatures, flows, pressure drops and thermal capacitance of pebble bed gas cooled reactors in support of the reactor safety case. The PBMR company developed the HTTU non-nuclear test facility in cooperation with M-Tech Industrial (Pty) Ltd. and the North-West University in South Africa to conduct comprehensive separate effects tests as well as integrated effects tests to study the different thermal-fluid phenomena. This paper describes the separate effects tests that were conducted to determine the effective thermal conductivity through the pebble bed under near-vacuum conditions and temperatures up to 1200 °C. It also presents the measured temperature distributions and the methodology applied in the data analysis to derive the resultant values of effective thermal conductivity and its associated uncertainty

Challenges in conducting research in pediatric long-term care facilities.

Science.gov (United States)

Larson, Elaine L; Cohen, Bevin; Murray, Meghan; Saiman, Lisa

2014-10-01

Children residing in long-term care facilities (LTCFs) have complex medical problems and unique care needs, yet research in this setting is rare. As part of an intervention study to improve patient safety (Keep It Clean for Kids [KICK]), we describe the challenges encountered and recommend approaches to build a successful and sustained collaborative relationship between pediatric LTCFs and the research team. We implemented a program with 5 components: leadership commitment, active staff participation by the creation of KICK teams, workflow assessments, staff training in the World Health Organization's "5 Moments for Hand Hygiene," and electronic monitoring and feedback to staff regarding hand hygiene practices. Major challenges encountered were establishing trust, building research teams, enhancing staff participation, and engaging families and visitors. Approaches to deal with these challenges are discussed. Conducting research in pediatric LTCFs requires sustained commitment to dealing with challenges and establishing collaborative relationships with administrative and frontline staff. © The Author(s) 2014.

Facility effluent monitoring plan for the 327 Facility

International Nuclear Information System (INIS)

1994-11-01

The 327 Facility [Post-Irradiation Testing Laboratory] provides office and laboratory space for Pacific Northwest Laboratory (PNL) scientific and engineering staff conducting multidisciplinary research in the areas of post-irradiated fuels and structural materials. The facility is designed to accommodate the use of radioactive and hazardous materials in the conduct of these activities. This report summarizes the airborne emissions and liquid effluents and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

A Facile Method for Preparing Transparent, Conductive, and Paper-Like Silver Nanowire Films

Directory of Open Access Journals (Sweden)

Yajie Wang

2011-01-01

Full Text Available Transparent, conductive, and flexible silver nanowire (AgNW films have been fabricated by a facile two-step method. Firstly, the well-dispersed AgNW suspension is vacuum filtered using mixed esters of cellulose (MCE membranes as filters. Then, the AgNW-MCE films are treated with acetone vapor. After the infiltration of acetone vapor, the white and porous MCE membranes change into transparent and pore-free, and AgNW-MCE films are obtained with extraordinary optical, conductive, and mechanical properties. An optimal result is obtained with transmittance of 85% at 550 nm and sheet resistance about 50 Ohm/sq. The flexibility of AgNW-MCE films is remarkable, which is comparable to that of the AgNW film on flexible polyethylene terephthalate (PET. More important, AgNW-MCE films show an excellent adhesion to the substrate, which causes a stable electrical conductivity even after scotch tape test and finger friction test. As a result of improved adhesion to the substrate, the sheet resistance of AgNW-MCE films is about 20% smaller than that of AgNW-PET films.

K-Long Facility for JLab and its Scientific Potential

Energy Technology Data Exchange (ETDEWEB)

Strakovski, Igor I. [George Washington Univ., Washington, DC (United States); Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States)

2016-11-29

Our main interest in creating a secondary high-quality KL-beam is to investigate hyperon spectroscopy through both formation and production processes. We propose to study two-body reactions induced by the KL-beam on the proton target. The experiment should measure both differential cross sections and self-analyzed polarizations of the produced $\\Lambda$-, $\\Sigma$-, and $\\Xi$-hyperons using the GlueX detector at the Jefferson Lab Hall D. New data will greatly constrain partial-wave analysis and reduce model-dependent uncertainties in the extraction of strange resonance properties, providing a new benchmark for comparisons with QCD-inspired models and LQCD calculations. The measurements will span c.m. $\\cos\\theta$ from -0.95 to 0.95 in c.m. range above W = 1490MeV and up to 4000 MeV.

Beam Spin Asymmetry Measurements for Two Pion Photoproduction at CLAS

Energy Technology Data Exchange (ETDEWEB)

Anderson, Mark D. [Univ. of Glasgow, Scotland (United Kingdom)

2015-09-01

The overarching goal of this analysis, and many like it, is to develop our understanding of the strong force interactions within the nucleon by examining the nature of their excitation spectra. As the resonances of these spectra have very short lifetimes (tau = 1x10^-23 s) and often have very similar masses, it is often impossible to directly observe resonances in the excitation spectra of nucleons. Polarization observables allow us to study the resonances by looking at how they affect the spin state of final state particles. The beam asymmetry is a polarization observable that allows us to detect the sensitivity of these resonances, and other transition mechanisms, to the electric vector orientation of incident photons. Presented in this thesis are first measurements of the beam asymmetries in the resonant region for the reaction channel pgamma p --> p π⁺ π^-focusing on the intermediate mesonic states rho^0 and f^0, and the final state pions. The analysis used data from the g8b experiment undertaken at the Thomas Jefferson National Accelerator Facility (JLab), the first experiment at JLab to use a linearly polarized photon beam. Using the coherent Bremsstrahlung facility and the CLAS detector of Hall B at JLab allowed for many multi-channel reactions to be detected and the first measurements of many polarization observables including those presented here. A brief overview of the theoretical framework used to undertake this analysis is given, followed by a description of the experimental details of the facilities used, then a description of the calibration of the Bremsstrahlung tagging facility which the author undertook, and finally the analysis is presented and the resulting measurements.

RF Processing of the Couplers for the SNS Superconducting Cavities

International Nuclear Information System (INIS)

Y.Kang; I.E. Campisi; D. Stout; A. Vassioutchenko; M. Stirbet; M. Drury; T. Powers

2005-01-01

All eighty-one fundamental power couplers for the 805 MHz superconducting cavities of the SNS linac have been RF conditioned and installed in the cryomodules successfully. The couplers were RF processed at JLAB or at the SNS in ORNL: more than forty couplers have been RF conditioned in the SNS RF Test Facility (RFTF) after the first forty couplers were conditioned at JLAB. The couplers were conditioned up to 650 kW forward power at 8% duty cycle in traveling and standing waves. They were installed on the cavities in the cryomodules and then assembled with the airside waveguide transitions. The couplers have been high power RF tested with satisfactory accelerating field gradients in the cooled cavities

Structure and spin of the nucleon

Directory of Open Access Journals (Sweden)

Avakian H.

2014-03-01

Great progress has been made since then in measurements of different Single Spin Asymmetries (SSAs in semi-inclusive and hard exclusive processes providing access to TMDs and GPDs, respectively. Facilities world-wide involved in studies of the 3D structure of nucleon include HERMES, COMPASS, BELLE, BaBar, Halls A, B, and C at JLab, and PHENIX and STAR at RHIC (BNL. TMD studies in the Drell-Yan process are also becoming an important part of the program of hadron scattering experiments. Studies of TMDs are also among the main driving forces of the JLab 12-GeV upgrade project, several of the forward upgrade proposals of STAR and PHENIX at RHIC, and future facilities, such as the Electron Ion Collider (EIC, FAIR in Germany, and NICA in Russia. In this contribution we present an overview of the latest developments in studies of parton distributions and discuss newly released results, ongoing activities, as well as some future measurements.

Super Conducting and Conventional Magnets Test & Mapping Facilities

Data.gov (United States)

Federal Laboratory Consortium — Vertical Magnet Test Facility: Accommodate a device up to 3.85 m long, 0.61 m diameter, and 14,400 lbs. Configured for 5 psig sub-cooled liquid helium bath cooling...

Operating experience review -- Conduct of operations at Department of Energy facilities

International Nuclear Information System (INIS)

1994-08-01

This research examined human error related occurrences, reported in the ORPS database, for the purpose of identifying weaknesses in the implementation of the guidance regarding the Conduct of Operations contained in DOE 5480.19. Specifically, this research examined three separate samples of occurrence reports from Defense Program facilities, which cited human error as a direct or contributing cause. These reports were evaluated using a coding scheme which incorporated the guidelines present in 5480.19, as well as a number of generic human factors concerns. The second chapter of this report summarizes the coding scheme which was used to evaluate the occurrence reports. Since the coding scheme is quite lengthy, only the parts of the scheme needed to make the remainder of the report clear are included in this chapter. Details on the development and content of the coding scheme are reported in Appendices A, B, and C. Chapter 3 presents the analysis of three different data sets. This chapter demonstrates that similar results were obtained across different data sets, collected at different points in time, and coded by different raters. The implications of the results obtained in Chapter 3 are discussed in Chapter 4. This chapter makes a number of suggestions for reducing the problems found in the occurrence reports. Chapter 5 applies the methodology that has been developed in this report to two facilities at Los Alamos National Laboratory. Finally, Chapter 6 reiterates the major findings of this report. Several additional analyses appear in appendices at the end of this report

Report on Beryllium Strength Experiments Conducted at the TA-55 40 mm Impact Test Facility, Fiscal Year 2017

Energy Technology Data Exchange (ETDEWEB)

Anderson, William Wyatt [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Hollowell, Benjamin Charles [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Martinez, Todd P. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Owens, Charles Thomas [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Rivera, Joseph Lee [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-10-10

A series of experiments is currently in progress at eth 40 mm Impact Test Facility (ITF), located at TA-55, to understand the strength behavior of Beryllium metal at elevated temperature and pressure. In FY 2017, three experiments were conducted as a part of this project.

Facile high-yield synthesis of polyaniline nanosticks with intrinsic stability and electrical conductivity.

Science.gov (United States)

Li, Xin-Gui; Li, Ang; Huang, Mei-Rong

2008-01-01

Chemical oxidative polymerization at 15 degrees C was used for the simple and productive synthesis of polyaniline (PAN) nanosticks. The effect of polymerization media on the yield, size, stability, and electrical conductivity of the PAN nanosticks was studied by changing the concentration and nature of the acid medium and oxidant and by introducing organic solvent. Molecular and supramolecular structure, size, and size distribution of the PAN nanosticks were characterized by UV/Vis and IR spectroscopy, X-ray diffraction, laser particle-size analysis, and transmission electron microscopy. Introduction of organic solvent is advantageous for enhancing the yield of PAN nanosticks but disadvantageous for formation of PAN nanosticks with small size and high conductivity. The concentration and nature of the acid medium have a major influence on the polymerization yield and conductivity of the nanosized PAN. The average diameter and length of PAN nanosticks produced with 2 M HNO(3) and 0.5 M H(2)SO(4) as acid media are about 40 and 300 nm, respectively. The PAN nanosticks obtained in an optimal medium (i.e., 2 M HNO(3)) exhibit the highest conductivity of 2.23 S cm(-1) and the highest yield of 80.7 %. A mechanism of formation of nanosticks instead of nanoparticles is proposed. Nanocomposite films of the PAN nanosticks with poly(vinyl alcohol) show a low percolation threshold of 0.2 wt %, at which the film retains almost the same transparency and strength as pure poly(vinyl alcohol) but 262 000 times the conductivity of pure poly(vinyl alcohol) film. The present synthesis of PAN nanosticks requires no external stabilizer and provides a facile and direct route for fabrication of PAN nanosticks with high yield, controllable size, intrinsic self-stability, strong redispersibility, high purity, and optimizable conductivity.

Facile Fabrication of Electrically Conductive Low-Density Polyethylene/Carbon Fiber Tubes for Novel Smart Materials via Multiaxial Orientation.

Science.gov (United States)

Li, Yijun; Nie, Min; Wang, Qi

2018-01-10

Electromechanical sensors are indispensable components in functional devices and robotics application. However, the fabrication of the sensors still maintains a challenging issue that high percolation threshold and easy failure of conductive network are derived from uniaxial orientation of conductive fillers in practical melt processing. Herein, we reported a facile fabrication method to prepare a multiaxial low-density polyethylene (LDPE)/carbon fibers (CFs) tube with bidirectional controllable electrical conductivity and sensitive strain-responsive performance via rotation extrusion technology. The multidimensional helical flow is confirmed in the reverse rotation extrusion, and the CFs readily respond to the flow field leading to a multiaxial orientation in the LDPE matrix. In contrast to uniaxial LDPE/CF composites, which perform a "head to head" conjunction, multiaxial-orientated CF networks exhibit a unique multilayer structure in which the CFs with distinct orientation direction intersect in the interface, endowing the LDPE/CF composites with a low percolation threshold (15 wt %) to those of the uniaxial ones (∼35 wt %). The angles between two axes play a vital role in determining the density of the conductive networks in the interface, which is predominant in tuning the bending-responsive behaviors with a gauge factor range from 12.5 to 56.3 and the corresponding linear respond region from ∼15 to ∼1%. Such a superior performance of conductive LDPE/CF tube confirms that the design of multiaxial orientation paves a novel way to facile fabrication of advanced cost-effective CF-based smart materials, shedding light on promising applications such as smart materials and intelligent engineering monitoring.

12 GeV detector technology at Jefferson Lab

Energy Technology Data Exchange (ETDEWEB)

Leckey, John P. [Indiana University, Bloomington, IN 47405 (United States); Collaboration: GlueX Collaboration

2013-04-19

The Thomas Jefferson National Accelerator Facility (JLab) is presently in the middle of an upgrade to increase the energy of its CW electron beam from 6 GeV to 12 GeV along with the addition of a fourth experimental hall. Driven both by necessity and availability, novel detectors and electronics modules have been used in the upgrade. One such sensor is the Silicon Photomultiplier (SiPM), specifically a Multi-Pixel Photon Counter (MPPC), which is an array of avalanche photodiode pixels operating in Geiger mode that are used to sense photons. The SiPMs replace conventional photomultiplier tubes and have several distinct advantages including the safe operation in a magnetic field and the lack of need for high voltage. Another key to 12 GeV success is advanced fast electronics. Jlab will use custom 250 MHz and 125 MHz 12-bit analog to digital converters (ADCs) and time to digital converters (TDCs) all of which take advantage of VME Switched Serial (VXS) bus with its GB/s high bandwidth readout capability. These new technologies will be used to readout drift chambers, calorimeters, spectrometers and other particle detectors at Jlab once the 12 GeV upgrade is complete. The largest experiment at Jlab utilizing these components is GlueX - an experiment in the newly constructed Hall D that will study the photoproduction of light mesons in the search for hybrid mesons. The performance of these components and their respective detectors will be presented.

The National Ignition Facility (NIF) as a User Facility

Science.gov (United States)

Keane, Christopher; NIF Team

2013-10-01

The National Ignition Facility (NIF) has made significant progress towards operation as a user facility. Through June 2013, NIF conducted over 1200 experiments in support of ICF, HED science, and development of facility capabilities. The NIF laser has met or achieved all specifications and a wide variety of diagnostic and target fabrication capabilities are in place. A NIF User Group and associated Executive Board have been formed. Two User Group meetings have been conducted since formation of the User Group. NIF experiments in fundamental science have provided important new results. NIF ramp compression experiments have been conducted using diamond and iron, with EOS results obtained at pressures up to approximately 50 Mbar and 8 Mbar, respectively. Initial experiments in supernova hydrodynamics, the fundamental physics of the Rayleigh-Taylor instability, and equation of state in the Gbar pressure regime have also been conducted. This presentation will discuss the fundamental science program at NIF, including the proposal solicitation and scientific review processes and other aspects of user facility operation. This work was performed under the auspices of the Lawrence Livermore National Security, LLC, (LLNS) under Contract No. DE-AC52-07NA27344.

Facility effluent monitoring plan determinations for the 400 Area facilities

International Nuclear Information System (INIS)

Nickels, J.M.

1991-09-01

This Facility Effluent Monitoring Plan determination resulted from an evaluation conducted for the Westinghouse Hanford Company 400 Area facilities on the Hanford Site. The Facility Effluent Monitoring Plan determinations have been prepared in accordance with A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans. Two major Westinghouse Hanford Company facilities in the 400 Area were evaluated: the Fast Flux Test Facility and the Fuels Manufacturing and examination Facility. The determinations were prepared by Westinghouse Hanford Company. Of these two facilities, only the Fast Flux Test Facility will require a Facility Effluent Monitoring Plan. 7 refs., 5 figs., 4 tabs

LCLS-II CRYOMODULE TRANSPORT SYSTEM TESTING

Energy Technology Data Exchange (ETDEWEB)

Huque, Naeem [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Daly, Edward F. [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); McGee, Michael W. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States)

2018-04-01

The Cryomodules (CM) for the Linear Coherent Light Source II (LCLS-II) will be shipped to SLAC (Menlo Park, California) from JLab (Newport News, Virginia) and FNAL (Batavia, Illinois). A transportation system has been designed and built to safely transport the CMs over the road. It uses an array of helical isolator springs to attenuate shocks on the CM to below 1.5g in all directions. The system rides on trailers equipped with Air-Ride suspension, which attenuates vibration loads. The prototype LCLS-II CM (pCM) was driven 750 miles to test the transport system; shock loggers recorded the shock attenuation on the pCM and vacuum gauges were used to detect any compromises in beamline vacuum. Alignment measurements were taken before and after the trip to check whether cavity positions had shifted beyond the ± 0.2mm spec. Passband frequencies and cavity gradients were measured at 2K at the Cryomodule Test Facility (CMTF) at JLab to identify any degradation of CM performance after transportation. The transport system was found to have safely carried the CM and is cleared to begin shipments from JLab and FNAL to SLAC.

Commissioning and operational results of helium refrigeration system at JLab for the 12GeV upgrade

Energy Technology Data Exchange (ETDEWEB)

Knudsen, Peter N. [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Ganni, Venkatarao [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Dixon, Kelly D. [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Norton, Robert O. [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Creel, Jonathan D. [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States)

2015-12-01

The new 4.5 K refrigerator system at the Jefferson Lab (JLab) Central Helium Liquefier (CHL-2) for the 12 GeV upgrade was commissioned in late spring of 2013, following the commissioning of the new compressor system, and has been supporting 12 GeV LINAC commissioning since that time. Six design modes were tested during commissioning, consisting of a maximum capacity, nominal capacity, maximum liquefaction, maximum refrigeration, maximum fill and a stand-by/reduced load condition. The maximum capacity was designed to support a 238 g/s, 30 K and 1.16 bar cold compressor return flow, a 15 g/s, 4.5 K liquefaction load and a 12.6 kW, 35-55 K shield load. The other modes were selected to ensure proper component sizing and selection to allow the cold box to operate over a wide range of conditions and capacities. The cold box system is comprised of two physically independent cold boxes with interconnecting transfer-lines. The outside (upper) 300-60 K vertical cold box has no turbines and incorporates a liquid nitrogen pre-cooler and 80-K beds. The inside (lower) 60-4.5 K horizontal cold box houses seven turbines that are configured in four expansion stages including one Joule-Thompson expander and a 20-K bed. The helium compression system has five compressors to support three pressure levels in the cold box. This paper will summarize the analysis of the test data obtained over the wide range of operating conditions and capacities which were tested.

Selected problems in nuclear/high energy physics: Experimental hypernuclear physics, muon rare decay, and development of new detector system applicable to nuclear/high energy physics experiments. Final close-out report, June 1, 1994--May 31, 1997

International Nuclear Information System (INIS)

Tang, L.; Continuous Electron Beam Accelerator Facility, Newport News, VA

1998-08-01

Under this DOE funding, the experimental program described in this report now consists of two major approved experiments at Jlab: Investigation of the Spin Dependence of the Effective AN interaction in p Shell (E89-009) which is tentatively scheduled to be completed in the fall of 1999 and Direct measurement of the Lifetime of the Heavy Λ-Hypernuclei at CEBAF (E95-002) which will be run in parasitic mode with E89-009. Also, a new experiment (E97-008) which attempts a directly observation of the spin-orbital splitting in the higher orbits with medium heavy targets was proposed and conditionally approved by Jlab PAC-12 in 1997. The condition for this experiment is simply to run E89-009 first and study the best possible energy resolution. The experimental group at Hampton University has played a leadership role in the development and preparation of these experiments. The Principal Investigator (PI) of this grant is spokesperson and acting program coordinator for all three experiments. Establishment of Jlab experiments is the group's main focus. In addition as originally proposed in the grant proposal, the group also contributed in completing the MEGA experiment at LAMPF. The detector development program established in the NuHEP Center has successfully constructed a large active area Lucite detector which uses a total internal reflection technique as a part of the kaon identification system for the Jlab Hall C SOS spectrometer. Its application in the first two experiments using the (e,e'K) reaction, E91-16 and E93-18 in 1996, has proved its effectiveness to reject the proton background both on-line and off-line. The author continued the program to develop new techniques and equipment associated with the Jlab experiments and possible future experiments at different national laboratories. This new work included developing: (1) a fission fragment detector with excellent timing and position resolution for the lifetime measurement of heavy hypernuclei and (2) new

Analysis of the Cause of High External Q Modes in the JLab High Gradient Prototype Cryomodule Renascence

Energy Technology Data Exchange (ETDEWEB)

Li, Z.; Akcelik, V.; Xiao, L.; Lee, L.; Ng, C.; Ko, K.; /SLAC; Wang, H.; Marhauser, F.; Sekutowicz, J.; Reece, C.; Rimmer, R.; /Jefferson Lab

2008-06-27

implemented to avoid such problem in the final upgrade design and manufacture. The goal of this work is to utilize advanced simulation tools to understand the high external Q (Q{sub ext}) problem observed in the Renascence cryomodule. In the past years, SLAC has built a set of state-of-the-art advanced simulation tools based on finite-element unstructured meshes and parallel computation implementations on supercomputers [2, 3]. The codes are capable of simulating large complex RF systems with unprecedented resolution and turnaround time. They have been successfully applied to many existing and future accelerator R&D projects to improve the machine performance and to optimize the designs. These tools are essential to perform accurate full system analyses such as the JLab's SRF cavities. We will use the simulation results and the data from the RF measurements to gain a better understanding of the cavity performance and tolerance issues and provide a solid foundation to do the BBU simulation and prediction for the 12GeV Upgrade project by using JLab's BBU codes. In this report, we will focus on the following two main tasks: (1) Ideal cavity simulation--to evaluate the effectiveness of the damping by the higher-order-mode (HOM) couplers, and search for possible trapped modes in a back-to-back cavity pair (e.g. cavity No.4 & No.5). (2) Abnormal cavity study--to understand the cause of the high Q{sub ext} modes in cavity No.5 using an advanced Shape Determination Tool.

Helicity Asymmetry Measurement for π⁰ Photoproduction with FROST

Energy Technology Data Exchange (ETDEWEB)

Iwamoto, Hideko [George Washington Univ., Washington, DC (United States)

2011-08-15

This thesis reports on the first helicity asymmetry measurement for single neutral pion photoproduction using the CLAS detector in Hall B at the Thomas Jefferson National Accelerator Facility (JLab). This measurement used longitudinally polarized protons and circularly polarized photons at energies between 350 MeV and 2400 MeV. The experimental results are compared to three available model calculations.

Helicity Asymmetry Measurement for pi⁰ Photoproduction with FROST

Energy Technology Data Exchange (ETDEWEB)

Iwamoto, Hideko [George Washington Univ., Washington, DC (United States)

2011-08-15

This thesis reports on the first helicity asymmetry measurement for single neutral pion photoproduction using the CLAS detector in Hall B at the Thomas Jefferson National Accelerator Facility (JLab). This measurement used longitudinally polarized protons and circularly polarized photons at energies between 350 MeV and 2400 MeV. The experimental results are compared to three available model calculations.

Communication grounding facility

International Nuclear Information System (INIS)

Lee, Gye Seong

1998-06-01

It is about communication grounding facility, which is made up twelve chapters. It includes general grounding with purpose, materials thermal insulating material, construction of grounding, super strength grounding method, grounding facility with grounding way and building of insulating, switched grounding with No. 1A and LCR, grounding facility of transmission line, wireless facility grounding, grounding facility in wireless base station, grounding of power facility, grounding low-tenton interior power wire, communication facility of railroad, install of arrester in apartment and house, install of arrester on introduction and earth conductivity and measurement with introduction and grounding resistance.

Amorphous transparent conducting oxides in context: Work function survey, trends, and facile modification

Science.gov (United States)

Yeh, T. C.; Zhu, Q.; Buchholz, D. B.; Martinson, A. B.; Chang, R. P. H.; Mason, T. O.

2015-03-01

The work functions of various amorphous and crystalline transparent conducting oxides (TCOs) were measured using Kelvin probe. The films, made by pulsed laser deposition, exhibited varying work functions dependent on the composition and deposition parameters. Tin oxide showed the largest work functions of the oxides measured, while zinc oxide showed the lowest. Binary and ternary combinations of the basis TCOs showed intermediate work functions dependent on the endpoint components. Amorphous TCOs, important in OPV and other technological applications, exhibited similar work functions to their crystalline counterparts. UV/ozone treatment of TCOs temporarily increased the work function, consistent with proposed defect mechanisms associated with near-surface changes in carrier content and Fermi level. Finally, a method for facile adjustment of the work function of commercial TCOs by atomic layer deposition (ALD) capping layers was presented, illustrated by the growth of zinc oxide layers on commercial crystalline ITO films.

Nucleon Spin Structure: Longitudinal and Transverse

International Nuclear Information System (INIS)

Chen, Jian-Ping

2011-01-01

Inclusive Deep-Inelastic Scattering (DIS) experiments have provided us with the most extensive information on the unpolarized and longitudinal polarized parton (quark and gluon) distributions in the nucleon. It has becoming clear that transverse spin and transverse momentum dependent distributions (TMDs) study are crucial for a more complete understanding of the nucleon structure and the dynamics of the strong interaction. The transverse spin structure and the TMDs are the subject of increasingly intense theoretical and experimental study recently. With a high luminosity electron beam facility, JLab has played a major role in the worldwide effort to study both the longitudinal and transverse spin structure. Highlights of recent results will be presented. With 12-GeV energy upgrade, JLab will provide the most precise measurements in the valence quark region to close a chapter in longitudinal spin study. JLab will also perform a multi-dimensional mapping of the transverse spin structure and TMDs in the valence quark region through Semi-Inclusive DIS (SIDIS) experiments, providing a 3-d partonic picture of the nucleon in momentum space and extracting the u and d quark tensor charges of the nucleon. The precision mapping of TMDs will also allow a detailed study of the quark orbital motion and its dynamics.

Electron-Ion Collider: The next QCD frontier. Understanding the glue that binds us all

Energy Technology Data Exchange (ETDEWEB)

Accardi, A. [Hampton University, Hampton, VA (United States); Thomas Jefferson National Accelerator Facility, Newport News, VA (United States); Albacete, J.L. [Universite Paris-Sud 11, CNRS/IN2P3, IPNO, Orsay (France); Anselmino, M. [Torino University (Italy); INFN, Torino (Italy); Armesto, N. [University of Santiago de Campostela, Santiago de Compostela (Spain); Aschenauer, E.C.; Burton, T.; Fazio, S.; Hao, Y.; Lamont, M.A.C.; Lee, J.H.; Lee, Y.; Litvinenko, V.; Ludlam, T.W.; Ptitsyn, V.; Qiu, J.W.; Roser, T.; Toll, T.; Trbojevic, D.; Ullrich, T.; Venugopalan, R.; Vigdor, S. [Brookhaven National Laboratory, Upton, NY (United States); Bacchetta, A. [University of Pavia, Pavia (Italy); Boer, D. [University of Groningen, Groningen (Netherlands); Brooks, W.K.; Hakobyan, H.; Kopeliovich, B. [Universidad Tecnica Federico Santa Maria, Valparaiso (Chile); Chang, N.B.; Huang, M. [Shandong University, Shandong (China); Deng, W.T. [Frankfurt University, FIAS, Frankfurt (Germany); Shandong University, Shandong (China); Deshpande, A.; Kumar, K. [Stony Brook University, Stony Brook, NY (United States); Diehl, M. [DESY, Hamburg (Germany); Dumitru, A.; Jalilian-Marian, J. [Baruch College, CUNY, New York, NY (United States); Dupre, R.; Sabatie, F. [Centre de Saclay, CEA, Gif-sur-Yvette (France); Ent, R.; Guzey, V.; Hutton, A.; Lin, F.L.; McKeown, R.; Morozov, V.S.; Nadel-Turonski, P.; Prokudin, A.; Weiss, C.; Zhang, Y.H. [Thomas Jefferson National Accelerator Facility, Newport News, VA (United States); Gao, H. [Duke University, Durham, NC (United States); Hasch, D. [INFN, LNF, Frascati (Italy); Holt, R. [Argonne National Laboratory, Argonne, IL (United States); Horn, T. [The Catholic University of America, N.E. Washington, DC (United States); Hyde, C. [Old Dominion University, Norfolk, VA (United States); Klein, S.; Sichtermann, E.; Yuan, F. [Lawrence Berkeley National Laboratory, Berkeley, CA (United States); Kovchegov, Y. [The Ohio State University, Columbus, OH (United States); Kumericki, K. [University of Zagreb, Zagreb (Croatia); Lappi, T.; Paukkunen, H. [University of Jyvaskyla, Jyvaskyla (Finland); Levin, E.M. [Tel Aviv University, Tel Aviv (Israel); Universidad Tecnica Federico Santa Maria, Valparaiso (Chile); Marquet, C. [CERN, Geneva (Switzerland); Meziani, Z.E.; Metz, A. [Temple University, Philadelphia, PA (United States); Milner, R. [Massachusetts Institute of Technology, Cambridge, MA (United States); Mueller, A.H. [Columbia University, New York, NY (US); Mueller, B. [Brookhaven National Laboratory, Upton, NY (US); Duke University, Durham, NC (US); Mueller, D. [Ruhr-University Bochum, Bochum (DE); Qian, X. [California Institute of Technology, Pasadena, CA (US); Ramsey-Musolf, M. [University of Massachusetts at Amherst, Amherst, MA (US); Sassot, R. [University of Buenos Aires, Buenos Aires (AR); Schnell, G. [University of Basque Country, Bilbao (ES); Schweitzer, P. [University of Connecticut, Storrs, CT (US); Stratmann, M.; Vogelsang, W. [University of Tuebingen, Tuebingen (DE); Strikman, M. [Pennsylvania State University, Philadelphia, PA (US); Sullivan, M. [Stanford Linear Accelerator Center, Menlo Park, CA (US); Taneja, S. [Dalhousie University, Halifax, Nova Scotia (CA); Stony Brook University, Stony Brook, NY (US); Xiao, B.W. [Central China Normal University, Wuhan, Hubei (CN); Zheng, L. [Brookhaven National Laboratory, Upton, NY (US); Central China Normal University, Wuhan, Hubei (CN)

2016-09-15

This White Paper presents the science case of an Electron-Ion Collider (EIC), focused on the structure and interactions of gluon-dominated matter, with the intent to articulate it to the broader nuclear science community. It was commissioned by the managements of Brookhaven National Laboratory (BNL) and Thomas Jefferson National Accelerator Facility (JLab) with the objective of presenting a summary of scientific opportunities and goals of the EIC as a follow-up to the 2007 NSAC Long Range plan. This document is a culmination of a community-wide effort in nuclear science following a series of workshops on EIC physics over the past decades and, in particular, the focused ten-week program on ''Gluons and quark sea at high energies'' at the Institute for Nuclear Theory in Fall 2010. It contains a brief description of a few golden physics measurements along with accelerator and detector concepts required to achieve them. It has been benefited profoundly from inputs by the users' communities of BNL and JLab. This White Paper offers the promise to propel the QCD science program in the US, established with the CEBAF accelerator at JLab and the RHIC collider at BNL, to the next QCD frontier. (orig.)

A Methodology for Conducting Space Utilization Studies within Department of Defense Medical Facilities

Science.gov (United States)

1992-07-01

database programs, such as dBase or Microsoft Excell, to yield statistical reports that can profile the health care facility . Ladeen (1989) feels that the...service specific space status report would be beneficial to the specific service(s) under study, it would not provide sufficient data for facility -wide...change in the Master Space Plan. The revised methodology also provides a mechanism and forum for spuce management education within the facility . The

Facility effluent monitoring plan determinations for the 200 Area facilities

International Nuclear Information System (INIS)

Nickels, J.M.

1991-11-01

The following facility effluent monitoring plan determinations document the evaluations conducted for the Westinghouse Hanford Company 200 Area facilities (chemical processing, waste management, 222-S Laboratory, and laundry) on the Hanford Site in south central Washington State. These evaluations determined the need for facility effluent monitoring plans for the 200 Area facilities. The facility effluent monitoring plan determinations have been prepared in accordance with A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438 (WHC 1991). The Plutonium/Uranium Extraction Plant and UO 3 facility effluent monitoring plan determinations were prepared by Los Alamos Technical Associates, Richland, Washington. The Plutonium Finishing Plant, Transuranic Waste Storage and Assay Facility, T Plant, Tank Farms, Low Level Burial Grounds, and 222-S Laboratory determinations were prepared by Science Applications International Corporation of Richland, Washington. The B Plant Facility Effluent Monitoring Plan Determination was prepared by ERCE Environmental Services of Richland, Washington

Electrical conductivity of the thermal dusty plasma under the conditions of a hybrid plasma environment simulation facility

Science.gov (United States)

Zhukhovitskii, Dmitry I.; Petrov, Oleg F.; Hyde, Truell W.; Herdrich, Georg; Laufer, Rene; Dropmann, Michael; Matthews, Lorin S.

2015-05-01

We discuss the inductively heated plasma generator (IPG) facility in application to the generation of the thermal dusty plasma formed by the positively charged dust particles and the electrons emitted by them. We develop a theoretical model for the calculation of plasma electrical conductivity under typical conditions of the IPG. We show that the electrical conductivity of dusty plasma is defined by collisions with the neutral gas molecules and by the electron number density. The latter is calculated in the approximations of an ideal and strongly coupled particle system and in the regime of weak and strong screening of the particle charge. The maximum attainable electron number density and corresponding maximum plasma electrical conductivity prove to be independent of the particle emissivity. Analysis of available experiments is performed, in particular, of our recent experiment with plasma formed by the combustion products of a propane-air mixture and the CeO2 particles injected into it. A good correlation between the theory and experimental data points to the adequacy of our approach. Our main conclusion is that a level of the electrical conductivity due to the thermal ionization of the dust particles is sufficiently high to compete with that of the potassium-doped plasmas.

Facile methods for enhancement of conductivity in polyaniline

NARCIS (Netherlands)

Vaidya, S.G.

2009-01-01

More than three decades ago polymers were considered to be insulators. Polymers could be made more or less conductive by the addition of fillers such as carbon black. This notion changed after the ‘experimental accidental discovery’ of extremely high conductivities in doped polyacetylene. This

Experiments in intermediate energy physics

International Nuclear Information System (INIS)

Dehnhard, D.

2003-01-01

Research in experimental nuclear physics was done from 1979 to 2002 primarily at intermediate energy facilities that provide pion, proton, and kaon beams. Particularly successful has been the work at the Los Alamos Meson Physics Facility (LAMPF) on unraveling the neutron and proton contributions to nuclear ground state and transition densities. This work was done on a wide variety of nuclei and with great detail on the carbon, oxygen, and helium isotopes. Some of the investigations involved the use of polarized targets which allowed the extraction of information on the spin-dependent part of the triangle-nucleon interaction. At the Indiana University Cyclotron Facility (IUCF) we studied proton-induced charge exchange reactions with results of importance to astrophysics and the nuclear few-body problem. During the first few years, the analysis of heavy-ion nucleus scattering data that had been taken prior to 1979 was completed. During the last few years we created hypernuclei by use of a kaon beam at Brookhaven National Laboratory (BNL) and an electron beam at Jefferson Laboratory (JLab). The data taken at BNL for a study of the non-mesonic weak decay of the A particle in a nucleus are still under analysis by our collaborators. The work at JLab resulted in the best resolution hypernuclear spectra measured thus far with magnetic spectrometers

Experiments in intermediate energy physics

Energy Technology Data Exchange (ETDEWEB)

Dehnhard, D.

2003-02-28

Research in experimental nuclear physics was done from 1979 to 2002 primarily at intermediate energy facilities that provide pion, proton, and kaon beams. Particularly successful has been the work at the Los Alamos Meson Physics Facility (LAMPF) on unraveling the neutron and proton contributions to nuclear ground state and transition densities. This work was done on a wide variety of nuclei and with great detail on the carbon, oxygen, and helium isotopes. Some of the investigations involved the use of polarized targets which allowed the extraction of information on the spin-dependent part of the triangle-nucleon interaction. At the Indiana University Cyclotron Facility (IUCF) we studied proton-induced charge exchange reactions with results of importance to astrophysics and the nuclear few-body problem. During the first few years, the analysis of heavy-ion nucleus scattering data that had been taken prior to 1979 was completed. During the last few years we created hypernuclei by use of a kaon beam at Brookhaven National Laboratory (BNL) and an electron beam at Jefferson Laboratory (JLab). The data taken at BNL for a study of the non-mesonic weak decay of the A particle in a nucleus are still under analysis by our collaborators. The work at JLab resulted in the best resolution hypernuclear spectra measured thus far with magnetic spectrometers.

Hydrophilicity Reinforced Adhesion of Anodic Alumina Oxide Template Films to Conducting Substrates for Facile Fabrication of Highly Ordered Nanorod Arrays.

Science.gov (United States)

Wang, Chuanju; Wang, Guiqiang; Yang, Rui; Sun, Xiangyu; Ma, Hui; Sun, Shuqing

2017-01-17

Arrays of ordered nanorods are of special interest in many fields. However, it remains challenging to obtain such arrays on conducting substrates in a facile manner. In this article, we report the fabrication of highly ordered and vertically standing nanorod arrays of both metals and semiconductors on Au films and indium tin oxide glass substrates without an additional layering. In this approach, following the simple hydrophilic treatment of an anodic aluminum oxide (AAO) membrane and conducting substrates, the AAO membrane was transferred onto the modified substrates with excellent adhesion. Subsequently, nanorod arrays of various materials were electrodeposited on the conducting substrates directly. This method avoids any expensive and tedious lithographic and ion milling process, which provides a simple yet robust route to the fabrication of arrays of 1D materials with high aspect ratio on conducting substrates, which shall pave the way for many practical applications in a range of fields.

Recoil polarization measurements in $\\pi^{0}$ electroproduction at the peak of the Delta (1232)

CERN Document Server

Sarty, A J

2001-01-01

This talk presents a status report, along with some preliminary/on line results, from the Thomas Jefferson National Accelerator Facility (JLab) experiment E91011 which was performed in Hall A at JLab during the summer of 2000. The experiment measured angular distributions for the differential cross section and recoil proton polarizations in the reaction p(e, e'p) pi /sup 0/. Kinematics were chosen to be centered at a CMS energy of W=1232 MeV, and a squared four momentum transfer of Q/sup 2/=1.0 (GeV/c)/sup 2/. The primary objectives of the experiment are to isolate contributions from the resonant quadrupole N to Delta , multipole S/sub 1+/, and to clarify the role of other, small nonresonant multipole contributions to the reaction. Details of the experiment itself will be given, along with sample spectra illustrating the quality and coverage of the data obtained. (10 refs) .

A facile strategy for the reduction of graphene oxide and its effect on thermal conductivity of epoxy based composites

Directory of Open Access Journals (Sweden)

F. Xie

2016-06-01

Full Text Available A facile and efficient approach to reduce graphene oxide with Al particles and potassium hydroxide was developed at moderate temperature and the graphene/epoxy composite was prepared by mould casting method. The as-prepared graphene has been confirmed by Transmission electron microscopy, Fourier transform infrared spectrometer, Raman spectroscopy, X-ray diffraction, X-ray photoelectron spectroscopy and Thermal gravimetric analysis. This provides a new green way to synthesize graphene with high surface area and opens another opportunity for the production of graphene. Effects of graphene on thermal conductivity, thermal stability and microstructures of the epoxy-based composite were also investigated. The results showed that thermal conductivity of the composite exhibited a remarkable improvement with increasing content of graphene and thermal conductivity could reach 1.192 W/(m*K when filled with 3 wt% graphene. Moreover, graphene/epoxy composite exhibits good thermal stability with 3 wt% graphene.

Millimeter-wave Instrumentation Test Facility

Data.gov (United States)

Federal Laboratory Consortium — The Millimeter-wave Instrumentation Test Facility conducts basic research in propagation phenomena, remote sensing, and target signatures. The facility has a breadth...

Study of the exotic Θ+ with polarized photon beams

International Nuclear Information System (INIS)

Zhao Qiang

2004-01-01

We carry out an analysis of the pentaquark Θ + photoproduction with polarized photon beams. Kinematical and dynamical aspects are examined for the purpose of determining Θ + 's spin and parity. It shows that the polarized photon beam asymmetry in association with certain dynamical properties of the production mechanism would provide further information on its quantum numbers. Facilities at SPring-8, JLab, ELSA, and ESRF will have access to them

Determination of the Optimal Operating Parameters for Jefferson Laboratory's Cryogenic Cold Compressor Systems

Energy Technology Data Exchange (ETDEWEB)

Wilson, Jr., Joe D. [Christopher Newport Univ., Newport News, VA (United States)

2003-01-01

The technology of Jefferson Laboratory's (JLab) Continuous Electron Beam Accelerator Facility (CEBAF) and Free Electron Laser (FEL) requires cooling from one of the world's largest 2K helium refrigerators known as the Central Helium Liquefier (CHL). The key characteristic of CHL is the ability to maintain a constant low vapor pressure over the large liquid helium inventory using a series of five cold compressors. The cold compressor system operates with a constrained discharge pressure over a range of suction pressures and mass flows to meet the operational requirements of CEBAF and FEL. The research topic is the prediction of the most thermodynamically efficient conditions for the system over its operating range of mass flows and vapor pressures with minimum disruption to JLab operations. The research goal is to find the operating points for each cold compressor for optimizing the overall system at any given flow and vapor pressure.

Electron Ion Collider: The Next QCD Frontier - Understanding the glue that binds us all

CERN Document Server

Accardi, A.; Anselmino, M.; Armesto, N.; Aschenauer, E.C.; Bacchetta, A.; Boer, D.; Brooks, W.K.; Burton, T.; Chang, N.B.; Deng, W.T.; Deshpande, A.; Diehl, M.; Dumitru, A.; Dupré, R.; Ent, R.; Fazio, S.; Gao, H.; Guzey, V.; Hakobyan, H.; Hao, Y.; Hasch, D.; Holt, R.; Horn, T.; Huang, M.; Hutton, A.; Hyde, C.; Jalilian-Marian, J.; Klein, S.; Kopeliovich, B.; Kovchegov, Y.; Kumar, K.; Kumerički, K.; Lamont, M.A.C.; Lappi, T.; Lee, J.H.; Lee, Y.; Levin, E.M.; Lin, F.L.; Litvinenko, V.; Ludlam, T.W.; Marquet, C.; Meziani, Z.E.; McKeown, R.; Metz, A.; Milner, R.; Morozov, V.S.; Mueller, A.H.; Müller, B.; Müller, Dieter; Nadel-Turonski, P.; Paukkunen, H.; Prokudin, A.; Ptitsyn, V.; Qian, X.; Qiu, J.W.; Ramsey-Musolf, M.; Roser, T.; Sabatié, F.; Sassot, R.; Schnell, G.; Schweitzer, P.; Sichtermann, E.; Stratmann, M.; Strikman, M.; Sullivan, M.; Taneja, S.; Toll, T.; Trbojevic, D.; Ullrich, T.; Venugopalan, R.; Vigdor, S.; Vogelsang, W.; Weiss, C.; Xiao, B.W.; Yuan, F.; Zhang, Y.H.; Zheng, L.

2016-01-01

This White Paper presents the science case of an Electron-Ion Collider (EIC), focused on the structure and interactions of gluon-dominated matter, with the intent to articulate it to the broader nuclear science community. It was commissioned by the managements of Brookhaven National Laboratory (BNL) and Thomas Jefferson National Accelerator Facility (JLab) with the objective of presenting a summary of scientific opportunities and goals of the EIC as a follow-up to the 2007 NSAC Long Range plan. This document is a culmination of a community-wide effort in nuclear science following a series of workshops on EIC physics and, in particular, the focused ten-week program on "Gluons and quark sea at high energies" at the Institute for Nuclear Theory in Fall 2010. It contains a brief description of a few golden physics measurements along with accelerator and detector concepts required to achieve them, and it benefited from inputs from the users' communities of BNL and JLab. This White Paper offers the promise to prope...

Tricobalt tetroxide nanoplate arrays on flexible conductive fabric substrate: Facile synthesis and application for electrochemical supercapacitors

Science.gov (United States)

Nagaraju, Goli; Ko, Yeong Hwan; Yu, Jae Su

2015-06-01

Tricobalt tetroxide (Co3O4) nanoplate arrays (NPAs) were synthesized on flexible conductive fabric substrate (FCFs) by a facile two-electrode system based electrochemical deposition method, followed by a simple heat treatment process. Initially, cobalt hydroxide (Co(OH)2) NPAs were electrochemically deposited on FCFs by applying an external voltage of -1.5 V for 30 min. Then, the Co3O4 NPAs on FCFs was obtained by thermal treatment of as-deposited Co(OH)2 NPAs on FCFs at 200 °C for 2 h. From the analysis of morphological and crystal properties, the Co3O4 NPAs were well integrated and uniformly covered over the entire surface of substrate with good crystallinity in the cubic phase. Additionally, the fabricated sample was directly used as a binder-free electrode to examine the feasibility for electrochemical supercapacitors using cyclic voltammetry and galvanic charge-discharge measurements in 1 M KOH electrolyte solution. The Co3O4 NPAs coated FCFs electrode exhibited a maximum specific capacitance of 145.6 F/g at a current density of 1 A/g and an excellent rate capability after 1000 cycles at a current density of 3 A/g. This facile fabrication method for integrating the Co3O4 nanostructures on FCFs could be a promising approach for advanced flexible electronic and energy-storage device applications.

A facile way to prepare CuS-oil nanofluids with enhanced thermal conductivity and appropriate viscosity

Energy Technology Data Exchange (ETDEWEB)

Qin, Ji-Hua; Liu, Zhao-Qing; Li, Nan, E-mail: nanli@gzhu.edu.cn; Chen, Yi-Bo; Wang, Dong-Yao [Guangzhou University, School of Chemistry and Chemical Engineering/Guangzhou Key Laboratory for Environmentally Functional Materials and Technology (China)

2017-02-15

The nanofluid as a pivotal role in heat transfer system has attracted more and more attention. Herein, the stearic acid-modified CuS (SA-CuS) nanoparticles with a uniform diameter of 60 nm were synthesized successfully by a facile two-phase approach. Accordingly, the CuS-oil nanofluids, with SA-CuS concentrations ranging from 0.01 to 0.04 vol%, were prepared by a one-step method in the heat transfer oil. These CuS-oil nanofluids exhibit good stability and considerable enhanced thermal conductivity. The improvement is even up to 20.5% with a volume fraction of 0.04 vol% at 30 °C. Furthermore, the effect of volume fraction and temperature on the viscosity of the nanofluids was also systematically investigated.

Trauma facilities in Denmark

DEFF Research Database (Denmark)

Weile, Jesper; Nielsen, Klaus; Primdahl, Stine C

2018-01-01

Background: Trauma is a leading cause of death among adults aged challenge. Evidence supports the centralization of trauma facilities and the use multidisciplinary trauma teams. Because knowledge is sparse on the existing distribution of trauma facilities...... and the organisation of trauma care in Denmark, the aim of this study was to identify all Danish facilities that care for traumatized patients and to investigate the diversity in organization of trauma management. Methods: We conducted a systematic observational cross-sectional study. First, all hospitals in Denmark...... were identified via online services and clarifying phone calls to each facility. Second, all trauma care manuals on all facilities that receive traumatized patients were gathered. Third, anesthesiologists and orthopedic surgeons on call at all trauma facilities were contacted via telephone...

33 CFR 126.30 - What are the conditions for conducting welding and hotwork?

Science.gov (United States)

2010-07-01

... conducting welding and hotwork? 126.30 Section 126.30 Navigation and Navigable Waters COAST GUARD, DEPARTMENT... FACILITIES § 126.30 What are the conditions for conducting welding and hotwork? (a) The facility operator must ensure that all welding or hotwork conducted at the facility meets the requirements of this...

PRTR/309 building nuclear facility preliminary

International Nuclear Information System (INIS)

Cornwell, B.C.

1994-01-01

The hazard classification of the Plutonium Recycle Test Reactor (PRTR)/309 building as a ''Radiological Facility'' and the office portions as ''Other Industrial Facility'' are documented by this report. This report provides: a synopsis of the history and facility it's uses; describes major area of the facility; and assesses the radiological conditions for the facility segments. The assessment is conducted using the hazard category threshold values, segmentation methodology, and graded approach guidance of DOE-STD-1027-92

Facility effluent monitoring plan for the 324 Facility

International Nuclear Information System (INIS)

1994-11-01

The 324 Facility [Waste Technology Engineering Laboratory] in the 300 Area primarily supports the research and development of radioactive and nonradioactive waste vitrification technologies, biological waste remediation technologies, spent nuclear fuel studies, waste mixing and transport studies, and tritium development programs. All of the above-mentioned programs deal with, and have the potential to, release hazardous and/or radioactive material. The potential for discharge would primarily result from (1) conducting research activities using the hazardous materials, (2) storing radionuclides and hazardous chemicals, and (3) waste accumulation and storage. This report summarizes the airborne and liquid effluents, and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterizing effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

Airborne Evaluation Facility

Data.gov (United States)

Federal Laboratory Consortium — AFRL's Airborne Evaluation Facility (AEF) utilizes Air Force Aero Club resources to conduct test and evaluation of a variety of equipment and concepts. Twin engine...

Phenomenology of Baryon Resonances

Energy Technology Data Exchange (ETDEWEB)

Doring, Michael [George Washington Univ., Washington, DC (United States); Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Landay, Justin [George Washington Univ., Washington, DC (United States); Mai, Maxim [George Washington Univ., Washington, DC (United States); Molina, Raquel [Univ. of Sao Paulo (Brazil); Ronchen, Deborah [Univ. of Bonn (Germany)

2018-04-01

Results for light baryon spectroscopy by different collaborations and the state of the art in the subfield is reviewed. Highlights contain common efforts of different phenomenology groups and the impact of recent high-precision data from ELSA, JLab, MAMI, and other facilities. Questions will be addressed, on one side, of how to proceed to reach conclusive answers in baryon spectroscopy, and, on the other side, how phenomenology can be connected to theory in a meaningful way.

Thermal-Hydraulic Experiment Facility (THEF)

International Nuclear Information System (INIS)

Martinell, J.S.

1982-01-01

This paper provides an overview of the Thermal-Hydraulic Experiment Facility (THEF) at the Idaho National Engineering Laboratory (INEL). The overview describes the major test systems, measurements, and data acquisition system, and presents objectives, facility configuration, and results for major experimental projects recently conducted at the THEF. Plans for future projects are also discussed. The THEF is located in the Water Reactor Research Test Facility (WRRTF) area at the INEL

Construction method for plant facility

International Nuclear Information System (INIS)

Ito, Arata; Hirono, Hideharu; Kyoda, Shigeru; Hanawa, Minoru; Sato, Hitoshi

1998-01-01

A caisson structure is disposed on a construction site for facilities of nuclear power plants. A digging work is performed below the caisson structure and, simultaneous with the digging work, a construction of a base, construction of plant facilities including a building and installation of plant facility are performed on the caisson structure. Then, the caisson structure is sank together with the structures on a base rock in association with the progress of the digging work and secured on the base rock. When securing them on the base rock, a groove is formed to the base rock along tuyere of the caisson structure so that the tuyere and a ceiling portion of the caisson structure are in direct contact with the base rock. Since the construction for the containing building conducted on the caisson structure is performed simultaneous with the digging work conducted below the caisson structure, the term required for the construction of the plant facilities can greatly reduced. (N.H.)

National software infrastructure for lattice gauge theory

International Nuclear Information System (INIS)

Brower, Richard C

2005-01-01

The current status of the SciDAC software infrastructure project for lattice gauge theory is summarized. This includes the the design of a QCD application programmers interface (API) that allows existing and future codes to be run efficiently on Terascale hardware facilities and to be rapidly ported to new dedicated or commercial platforms. The critical components of the API have been implemented and are in use on the US QCDOC hardware at BNL and on both the switched and mesh architecture Pentium 4 clusters at Fermi National Accelerator Laboratory (FNAL) and Thomas Jefferson National Accelerator Facility (JLab). Future software infrastructure requirements and research directions are also discussed

DUPIC facility engineering

Energy Technology Data Exchange (ETDEWEB)

Lee, J S; Choi, J W; Go, W I; Kim, H D; Song, K C; Jeong, I H; Park, H S; Im, C S; Lee, H M; Moon, K H; Hong, K P; Lee, K S; Suh, K S; Kim, E K; Min, D K; Lee, J C; Chun, Y B; Paik, S Y; Lee, E P; Yoo, G S; Kim, Y S; Park, J C

1997-09-01

In the early stage of the project, a comprehensive survey was conducted to identify the feasibility of using available facilities and of interface between those facilities. It was found out that the shielded cell M6 interface between those facilities. It was found out that the shielded cell M6 of IMEF could be used for the main process experiments of DUPIC fuel fabrication in regard to space adequacy, material flow, equipment layout, etc. Based on such examination, a suitable adapter system for material transfer around the M6 cell was engineered. Regarding the PIEF facility, where spent PWR fuel assemblies are stored in an annex pool, disassembly devices in the pool are retrofitted and spent fuel rod cutting and shipping system to the IMEF are designed and built. For acquisition of casks for radioactive material transport between the facilities, some adaptive refurbishment was applied to the available cask (Padirac) based on extensive analysis on safety requirements. A mockup test facility was newly acquired for remote test of DUPIC fuel fabrication process equipment prior to installation in the M6 cell of the IMEF facility. (author). 157 refs., 57 tabs., 65 figs.

DUPIC facility engineering

International Nuclear Information System (INIS)

Lee, J. S.; Choi, J. W.; Go, W. I.; Kim, H. D.; Song, K. C.; Jeong, I. H.; Park, H. S.; Im, C. S.; Lee, H. M.; Moon, K. H.; Hong, K. P.; Lee, K. S.; Suh, K. S.; Kim, E. K.; Min, D. K.; Lee, J. C.; Chun, Y. B.; Paik, S. Y.; Lee, E. P.; Yoo, G. S.; Kim, Y. S.; Park, J. C.

1997-09-01

In the early stage of the project, a comprehensive survey was conducted to identify the feasibility of using available facilities and of interface between those facilities. It was found out that the shielded cell M6 interface between those facilities. It was found out that the shielded cell M6 of IMEF could be used for the main process experiments of DUPIC fuel fabrication in regard to space adequacy, material flow, equipment layout, etc. Based on such examination, a suitable adapter system for material transfer around the M6 cell was engineered. Regarding the PIEF facility, where spent PWR fuel assemblies are stored in an annex pool, disassembly devices in the pool are retrofitted and spent fuel rod cutting and shipping system to the IMEF are designed and built. For acquisition of casks for radioactive material transport between the facilities, some adaptive refurbishment was applied to the available cask (Padirac) based on extensive analysis on safety requirements. A mockup test facility was newly acquired for remote test of DUPIC fuel fabrication process equipment prior to installation in the M6 cell of the IMEF facility. (author). 157 refs., 57 tabs., 65 figs

NWFSC OA facility water chemistry - Ocean acidification species exposure experimental facility

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — We have developed a unique facility for conducting high-quality experiments on marine organisms in seawater with controlled carbon chemistry conditions. The...

Nuclear physics accelerator facilities

International Nuclear Information System (INIS)

1988-12-01

This paper describes many of the nuclear physics heavy-ion accelerator facilities in the US and the research programs being conducted. The accelerators described are: Argonne National Laboratory--ATLAS; Brookhaven National Laboratory--Tandem/AGS Heavy Ion Facility; Brookhaven National Laboratory--Relativistic Heavy Ion Collider (RHIC) (Proposed); Continuous Electron Beam Accelerator Facility; Lawrence Berkeley Laboratory--Bevalac; Lawrence Berkeley Laboratory--88-Inch Cyclotron; Los Alamos National Laboratory--Clinton P. Anderson Meson Physics Facility (LAMPF); Massachusetts Institute of Technology--Bates Linear Accelerator Center; Oak Ridge National Laboratory--Holifield Heavy Ion Research Facility; Oak Ridge National Laboratory--Oak Ridge Electron Linear Accelerator; Stanford Linear Accelerator Center--Nuclear Physics Injector; Texas AandM University--Texas AandM Cyclotron; Triangle Universities Nuclear Laboratory (TUNL); University of Washington--Tandem/Superconducting Booster; and Yale University--Tandem Van de Graaff

Powder Metallurgy Facility

Data.gov (United States)

Federal Laboratory Consortium — The facility is uniquely equipped as the only laboratory within DA to conduct PM processing of refractory metals and alloys as well as the processing of a wide range...

Refurbishment of JMTR pure water facility

International Nuclear Information System (INIS)

Asano, Norikazu; Hanakawa, Hiroki; Kusunoki, Hidehiko; Satou, Shinichi

2012-05-01

In the refurbishment of JMTR, facilities were classified into which (1) were all updated, (2) were partly updated, and (3) were continuance used by the considerations of the maintenance history, the change parts availability and the latest technology. The JMTR pure water facility was classified into all updated facility based on the consideration. The Update construction was conducted in between FY2007 and FY2008. The refurbishment of JMTR pure water facility is summarized in this report. (author)

PFP Wastewater Sampling Facility

International Nuclear Information System (INIS)

Hirzel, D.R.

1995-01-01

This test report documents the results obtained while conducting operational testing of the sampling equipment in the 225-WC building, the PFP Wastewater Sampling Facility. The Wastewater Sampling Facility houses equipment to sample and monitor the PFP's liquid effluents before discharging the stream to the 200 Area Treated Effluent Disposal Facility (TEDF). The majority of the streams are not radioactive and discharges from the PFP Heating, Ventilation, and Air Conditioning (HVAC). The streams that might be contaminated are processed through the Low Level Waste Treatment Facility (LLWTF) before discharging to TEDF. The sampling equipment consists of two flow-proportional composite samplers, an ultrasonic flowmeter, pH and conductivity monitors, chart recorder, and associated relays and current isolators to interconnect the equipment to allow proper operation. Data signals from the monitors are received in the 234-5Z Shift Office which contains a chart recorder and alarm annunciator panel. The data signals are also duplicated and sent to the TEDF control room through the Local Control Unit (LCU). Performing the OTP has verified the operability of the PFP wastewater sampling system. This Operability Test Report documents the acceptance of the sampling system for use

Photoproduction of Multiply-Strange Hyperons at CLAS

International Nuclear Information System (INIS)

Price, John

2016-01-01

The activities of the California State University, Dominguez Hills (CSUDH) Hadronic Structure Laboratory, undertaken with the support of the U.S. Department of Energy's Office of Science under grant DE-FG02-07ER41525, are described. This grant was originally awarded in 2007, and then renewed in 2009 and 2012, before it expired in 2015. The work was performed primarily at the home institution on the CSUDH campus in Carson, CA. A significant portion of the work was carried out at the Thomas Jefferson National Accelerator Facility (JLab) in Newport News, VA. The work covered in this award involves the study of the structure of the proton, which is done indirectly by looking at the Ξ particle. This is a particle with a spin and spatial structure similar to that of the proton, but with a different quark structure. Their properties are expected to be related due to SU(3)_F symmetry. Additional work performed under this grant involved the construction of the High Threshold Cherenkov Counter, which was done by CSUDH undergraduate students in collaboration with JLab staff scientists.

JLABGEO: a new survey and alignment data manager

Energy Technology Data Exchange (ETDEWEB)

Tremblay, K.J.; Curtis, C.J. [Thomas Jefferson National Accelerator Facility, Virginia (United States)

1999-07-01

The Survey and Alignment group at Thomas Jefferson National Accelerator Facility has relied upon the MS-Dos program Geonet, originally developed at Stanford Linear Accelerator, as its central data manager. With the Lab decision to only use Microsoft Windows NT as the platform for PCs, limitations were reached in using Geonet. A program has been developed at Jefferson Lab, JLabGeo to mimic as many of the Geonet functions as possible, while also expanding and enhancing its capabilities. All of the adjustment programs, originally developed by Dr. Ingolf Burstedde, have been revised in order to work with arrays of any size, and operate as console applications in the NT environment. Integrating the use of a central file server as both the source of the executable programs and data files also ensures that all workstations are using the most recent data. Work continues on developing JLabGeo, notably the integration of all of our survey data types into a easily retrievable database, and the development of a central repository for beamline information and ideal coordinates. (authors)

JLABGEO: a new survey and alignment data manager

International Nuclear Information System (INIS)

Tremblay, K.J.; Curtis, C.J.

1999-01-01

The Survey and Alignment group at Thomas Jefferson National Accelerator Facility has relied upon the MS-Dos program Geonet, originally developed at Stanford Linear Accelerator, as its central data manager. With the Lab decision to only use Microsoft Windows NT as the platform for PCs, limitations were reached in using Geonet. A program has been developed at Jefferson Lab, JLabGeo to mimic as many of the Geonet functions as possible, while also expanding and enhancing its capabilities. All of the adjustment programs, originally developed by Dr. Ingolf Burstedde, have been revised in order to work with arrays of any size, and operate as console applications in the NT environment. Integrating the use of a central file server as both the source of the executable programs and data files also ensures that all workstations are using the most recent data. Work continues on developing JLabGeo, notably the integration of all of our survey data types into a easily retrievable database, and the development of a central repository for beamline information and ideal coordinates. (authors)

Trauma facilities in Denmark - A nationwide cross-sectional benchmark study of facilities and trauma care organisation

DEFF Research Database (Denmark)

Weile, Jesper; Nielsen, Klaus; Primdahl, Stine C.

2018-01-01

Background: Trauma is a leading cause of death among adults aged trauma facilities and the use multidisciplinary trauma teams. Because knowledge is sparse on the existing distribution of trauma facilities...... and the organisation of trauma care in Denmark, the aim of this study was to identify all Danish facilities that care for traumatized patients and to investigate the diversity in organization of trauma management. Methods: We conducted a systematic observational cross-sectional study. First, all hospitals in Denmark...... were identified via online services and clarifying phone calls to each facility. Second, all trauma care manuals on all facilities that receive traumatized patients were gathered. Third, anesthesiologists and orthopedic surgeons on call at all trauma facilities were contacted via telephone...

Vehicle Thermal Management Facilities | Transportation Research | NREL

Science.gov (United States)

Integration Facility The Vehicle Testing and Integration Facility features a pad to conduct vehicle thermal station next to the pad provides a continuous data stream on temperature, humidity, wind speed, and solar

Effect of Information Communication Technology Facilities on ...

African Journals Online (AJOL)

This study examined the effect of ICT facilities on students' performance by comparing ... The comparison was conducted using subtests of English language and ... ICT facilities in all secondary schools to enhance teaching and learning.

20 CFR 638.303 - Site selection and facilities management.

Science.gov (United States)

2010-04-01

... 20 Employees' Benefits 3 2010-04-01 2010-04-01 false Site selection and facilities management. 638... Facilities Management § 638.303 Site selection and facilities management. (a) The Job Corps Director shall... center, facilities engineering and real estate management will be conducted by the Job Corps Director or...

Final Technical Report - Nuclear Studies with Intermediate Energy Probes

Energy Technology Data Exchange (ETDEWEB)

Norum, Blaine [Univ. of Virginia, Charlottesville, VA (United States)

2017-12-14

During the almost 20 year period of this grant research was carried out on atomic nuclei and their constituents using both photons and electrons. Research was carried out at the electron accelerator facility of the Netherlands Institute for Nuclear and High Energy Physics (NIKHEFK, Amsterdam) until the electron accelerator facility was closed in 1998. Subsequently, research was carried out at the Laser-Electron Gamma Source (LEGS) of the National Synchrotron Light Source (NSLS) located at the Brookhaven National Laboratory (BNL) until the LEGS was closed at the end of 2006. During the next several years research was carried out at both the Thomas Jefferson National Accelerator Facility (JLAB) and the High Intensity Gamma Source (HIGS) of the Tri-Universities Nuclear Laboratory (TUNL) located on the campus of Duke University. Since approximately 2010 the principal focus was on research at TUNL, although analysis of data from previous research at other facilities continued. The principal early focus of the research was on the role of pions in nuclei. This was studied by studying the production of pions using both photons (at LEGS) and electrons (at NIKHEF-K and JLAB). Measurements of charged pion photoproduction from deuterium at LEGS resulted in the most interesting result of these two decades of work. By measuring the production of a charged pion (p + ) in coincidence with an emitted photon we observed structures in the residual two-nucleon system. These indicated the existence of long-lived states not explicable by standard nuclear theory; they suggest a set of configurations not explicable in terms of a nucleon-nucleon pair. The existence of such “exotic” structures has formed the foundation for most of the work that has ensued.

Hanford Facility resource conservation and recovery act permit general inspection plan

International Nuclear Information System (INIS)

Beagles, D.B.

1995-12-01

The Hanford Facility Resource Conservation and Recovery Act Permit, General Inspection Requirements, includes a requirement that general facility inspections be conducted of the 100, 200 East, 200 West, 300, 400, and 1100 Areas and the banks of the Columbia River. This inspection plan describes the activities that shall be conducted for a general inspection of the Hanford Facility

Overview - Defense Waste Processing Facility Operating Experience

International Nuclear Information System (INIS)

Norton, M.R.

2002-01-01

The Savannah River Site's Defense Waste Processing Facility (DWPF) near Aiken, SC is the world's largest radioactive waste vitrification facility. Radioactive operations began in March 1996 and over 1,000 canisters have been produced. This paper presents an overview of the DWPF process and a summary of recent facility operations and process improvements. These process improvements include efforts to extend the life of the DWPF melter, projects to increase facility throughput, initiatives to reduce the quantity of wastewater generated, improved remote decontamination capabilities, and improvements to remote canyon equipment to extend equipment life span. This paper also includes a review of a melt rate improvement program conducted by Savannah River Technology Center personnel. This program involved identifying the factors that impacted melt rate, conducting small scale testing of proposed process changes and developing a cost effective implementation plan

National synchrotron light source guidelines for the conduct of operations

International Nuclear Information System (INIS)

Buckley, M.

1998-01-01

To improve the quality and uniformity of operations at the Department of Energy's facilities, the DOE issued Order 5480.19 ''Conduct of Operations Requirements at DOE facilities.'' This order recognizes that the success of a facility's mission critically depends upon a high level of performance by its personnel and equipment. This performance can be severely impaired if the facility's Conduct of Operations pays inadequate attention to issues of organization, safety, health, and the environment. These guidelines are Brookhaven National Laboratory's and the National Synchrotron Light Source's acknowledgement of the principles of Conduct of Operations and the response to DOE Order 5480.19. These guidelines cover the following areas: (1) operations organization and administration; (2) shift routines and operating practices; (3) control area activities; (4) communications; (5) control of on-shift training; (6) investigation of abnormal events; (7) notifications; (8) control of equipment and system studies; (9) lockouts and tagouts; (10) independent verification; (11) log-keeping; (12) operations turnover; (13) operations aspects of facility process control (14) required reading; (15) timely orders to operators; (16) operations procedures; (17) operator aid posting; and (18) equipment sizing and labeling

Pacific Northwest Laboratory (PNL) spent fuel transportation and handling facility models

Energy Technology Data Exchange (ETDEWEB)

Andrews, W.B.; Bower, J.C.; Burnett, R.A.; Engel, R.L.; Rolland, C.W.

1979-09-01

A spent fuel logistics study was conducted in support of the US DOE program to develop facilities for preparing spent unreprocessed fuel from commercial LWRs for geological storage. Two computerized logistics models were developed. The first one was the site evaluation model. Two studies of spent fuel handling facility and spent fuel disposal facility siting were completed; the first postulates a single spent fuel handling facility located at any of six DOE laboratory sites, while the second study examined siting strategies with the spent fuel repository relative to the spent fuel handling facility. A second model to conduct storage/handling facility simulations was developed. (DLC)

Pacific Northwest Laboratory (PNL) spent fuel transportation and handling facility models

International Nuclear Information System (INIS)

Andrews, W.B.; Bower, J.C.; Burnett, R.A.; Engel, R.L.; Rolland, C.W.

1979-09-01

A spent fuel logistics study was conducted in support of the US DOE program to develop facilities for preparing spent unreprocessed fuel from commercial LWRs for geological storage. Two computerized logistics models were developed. The first one was the site evaluation model. Two studies of spent fuel handling facility and spent fuel disposal facility siting were completed; the first postulates a single spent fuel handling facility located at any of six DOE laboratory sites, while the second study examined siting strategies with the spent fuel repository relative to the spent fuel handling facility. A second model to conduct storage/handling facility simulations was developed

Online helium inventory monitoring of JLab cryogenic systems

Science.gov (United States)

Hasan, N.; Knudsen, P.; Wright, M.

2017-12-01

There are five cryogenic plants at Jefferson Lab which support the LINAC, experiment hall end-stations and test facility. The majority of JLab’s helium inventory, which is around 15 tons, is allocated in the LINAC cryo-modules, with the majority of the balance of helium distributed at the cryogenic-plant level mainly as stored gas and liquid for stable operation. Due to the organic evolution of the five plants and independent actions within the experiment halls, the traditional inventory management strategy suffers from rapid identification of potential leaks. This can easily result in losses many times higher than the normally accepted (average) loss rate. A real-time program to quickly identify potential excessive leakage was developed and tested. This program was written in MATLAB© for portability, easy diagnostics and modification. It interfaces directly with EPICS to access the cryogenic system state, and with and NIST REFPROP© for real fluid properties. This program was validated against the actual helium offloaded into the system. The present paper outlines the details of the inventory monitoring program, its validation and a sample of the achieved results.

On-orbit technology experiment facility definition

Science.gov (United States)

Russell, Richard A.; Buchan, Robert W.; Gates, Richard M.

1988-01-01

A study was conducted to identify on-orbit integrated facility needs to support in-space technology experiments on the Space Station and associated free flyers. In particular, the first task was to examine the proposed technology development missions (TDMX's) from the model mission set and other proposed experimental facilities, both individually and by theme, to determine how and if the experiments might be combined, what equipment might be shared, what equipment might be used as generic equipment for continued experimentation, and what experiments will conflict with the conduct of other experiments or Space Station operations. Then using these results, to determine on-orbit facility needs to optimize the implementation of technology payloads. Finally, to develop one or more scenarios, design concepts, and outfitting requirements for implementation of onboard technology experiments.

RADON-type disposal facility safety case for the co-ordinated research project on improvement of safety assessment methodologies for near surface radioactive waste disposal facilities (ISAM)

International Nuclear Information System (INIS)

Guskov, A.; Batanjieva, B.; Kozak, M.W.; Torres-Vidal, C.

2002-01-01

The ISAM safety assessment methodology was applied to RADON-type facilities. The assessments conducted through the ISAM project were among the first conducted for these kinds of facilities. These assessments are anticipated to lead to significantly improved levels of safety in countries with such facilities. Experience gained though this RADON-type Safety Case was already used in Russia while developing national regulatory documents. (author)

Argonne-West facility requirements for a radioactive waste treatment demonstration

International Nuclear Information System (INIS)

Dwight, C.C.; Felicione, F.S.; Black, D.B.; Kelso, R.B.; McClellan, G.C.

1995-01-01

At Argonne National Laboratory-West (ANL-W), near Idaho Falls, Idaho, facilities that were originally constructed to support the development of liquid-metal reactor technology are being used and/or modified to meet the environmental and waste management research needs of DOE. One example is the use of an Argonne-West facility to conduct a radioactive waste treatment demonstration through a cooperative project with Science Applications International Corporation (SAIC) and Lockheed Idaho Technologies Company. The Plasma Hearth Process (PBP) project will utilize commercially-adapted plasma arc technology to demonstrate treatment of actual mixed waste. The demonstration on radioactive waste will be conducted at Argonne's Transient Reactor Test Facility (TREAT). Utilization of an existing facility for a new and different application presents a unique set of issues in meeting applicable federal state, and local requirements as well as the additional constraints imposed by DOE Orders and ANL-W site requirements. This paper briefly describes the PHP radioactive demonstrations relevant to the interfaces with the TREAT facility. Safety, environmental design, and operational considerations pertinent to the PHP radioactive demonstration are specifically addressed herein. The personnel equipment, and facility interfaces associated with a radioactive waste treatment demonstration are an important aspect of the demonstration effort. Areas requiring significant effort in preparation for the PBP Project being conducted at the TREAT facility include confinement design, waste handling features, and sampling and analysis considerations. Information about the facility in which a radioactive demonstration will be conducted, specifically Argonne's TREAT facility in the case of PHP, may be of interest to other organizations involved in developing and demonstrating technologies for mixed waste treatment

Weapons engineering tritium facility overview

Energy Technology Data Exchange (ETDEWEB)

Najera, Larry [Los Alamos National Laboratory

2011-01-20

Materials provide an overview of the Weapons Engineering Tritium Facility (WETF) as introductory material for January 2011 visit to SRS. Purpose of the visit is to discuss Safety Basis, Conduct of Engineering, and Conduct of Operations. WETF general description and general GTS program capabilities are presented in an unclassified format.

Development of Chinese HTR-PM pebble bed equivalent conductivity test facility

Energy Technology Data Exchange (ETDEWEB)

Ren, Cheng; Yang, Xingtuan; Jiang, Shengyao [Tsinghua Univ., Beijing (China). Inst. of Nuclear and New Energy Technology

2016-01-15

The first two 250-MWt high-temperature reactor pebble bed modules (HTR-PM) have been installing at the Shidaowan plant in Shandong Province, China. The values of the effective thermal conductivity of the pebble bed core are essential parameters for the design. For their determination, Tsinghua University in China has proposed a full-scale heat transfer experiment to conduct comprehensive thermal transfer tests in packed pebble bed and to determine the effective thermal conductivity.

Auditing radiation sterilization facilities

Science.gov (United States)

Beck, Jeffrey A.

The diversity of radiation sterilization systems available today places renewed emphasis on the need for thorough Quality Assurance audits of these facilities. Evaluating compliance with Good Manufacturing Practices is an obvious requirement, but an effective audit must also evaluate installation and performance qualification programs (validation_, and process control and monitoring procedures in detail. The present paper describes general standards that radiation sterilization operations should meet in each of these key areas, and provides basic guidance for conducting QA audits of these facilities.

International Mapping of Antenna-Measurement Facilities

DEFF Research Database (Denmark)

Boccia, Luigi; Breinbjerg, Olav; Di Massa, Giuseppe

2006-01-01

This paper presents a comprehensive international mapping of antenna-measurement facilities. This initiative, conducted within the framework of the Antenna Centre of Excellence (ACE) of the European Union, is oriented toward all institutions having research, development, or operational activities...... measurements, in particular from the wireless communication industry, to identify and contact antenna-measurement facilities. The first phase of the mapping showed a significant and encouraging reaction to this initiative, with more than 50 European facilities currently registered. The next phase aims...

Overview of nucleon form factor experiments with 12 GeV at Jefferson Lab

Directory of Open Access Journals (Sweden)

Cisbani Evaristo

2014-06-01

A selection of the relevant properties of the FF's, and the main results of JLab are shortly reviewed; the new proposed and approved experiments on FF's at JLab are presented addressing some key details, the expected experimental achievements and the new equipment designed for them.

Detonation Engine Research Facility (DERF)

Data.gov (United States)

Federal Laboratory Consortium — Description: This facility is configured to safely conduct experimental pressuregain combustion research. The DERF is capable of supporting up to 60,000 lbf thrust...

Kalman filter-based gap conductance modeling

International Nuclear Information System (INIS)

Tylee, J.L.

1983-01-01

Geometric and thermal property uncertainties contribute greatly to the problem of determining conductance within the fuel-clad gas gap of a nuclear fuel pin. Accurate conductance values are needed for power plant licensing transient analysis and for test analyses at research facilities. Recent work by Meek, Doerner, and Adams has shown that use of Kalman filters to estimate gap conductance is a promising approach. A Kalman filter is simply a mathematical algorithm that employs available system measurements and assumed dynamic models to generate optimal system state vector estimates. This summary addresses another Kalman filter approach to gap conductance estimation and subsequent identification of an empirical conductance model

Trisonic Gas-Dynamics Facility (TGF)

Data.gov (United States)

Federal Laboratory Consortium — Description: The TGF is a two-foot square, continuous-flow, closed-circuit wind tunnel which is optimal for conducting research experiments. The facility provides a...

Welding and Production Metallurgy Facility

Data.gov (United States)

Federal Laboratory Consortium — This 6000 square foot facility represents the only welding laboratory of its kind within DA. It is capable of conducting investigations associated with solid state...

Optimization of the RF cavity heat load and trip rates for CEBAF at 12 GeV

Energy Technology Data Exchange (ETDEWEB)

Zhang, He [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Roblin, Yves R. [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Freyberger, Arne P. [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Krafft, Geoffrey A. [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Terzic, Balsa P. [Old Dominion Univ., Norfolk, VA (United States)

2017-05-01

The Continuous Electron Beam Accelerator Facility at JLab has 200 RF cavities in the north linac and the south linac respectively after the 12 GeV upgrade. The purpose of this work is to simultaneously optimize the heat load and the trip rate for the cavities and to reconstruct the pareto-optimal front in a timely manner when some of the cavities are turned down. By choosing an efficient optimizer and strategically creating the initial gradients, the pareto-optimal front for no more than 15 cavities down can be re-established within 20 seconds.

LCLS-II Cryomodules Production at Fermilab

Energy Technology Data Exchange (ETDEWEB)

Arkan, Tug [Fermilab; Grimm, Chuck [Fermilab; Kaluzny, Joshua [Fermilab; Orlov, Yuriy [Fermilab; Peterson, Thomas [Fermilab; Premo, Ken [Fermilab

2017-05-01

LCLS-II is an upgrade project for the linear coherent light source (LCLS) at SLAC. The LCLS-II linac will consist of thirty-five 1.3 GHz and two 3.9 GHz superconducting RF continuous wave (CW) cryomodules that Fermilab and Jefferson Lab (JLab) will assemble in collaboration with SLAC. The LCLS-II 1.3 GHz cryomodule design is based on the European XFEL pulsed-mode cryomodule design with modifications needed for CW operation. Fermilab and JLab will each assemble and test a prototype 1.3 GHz cryomodule to assess the results of the CW modifications, in advance of 16 and 17 production 1.3 GHz cryomodules, respectively. Fermilab is solely responsible for the 3.9 GHz cryomodules. After the prototype cryomodule tests are complete and lessons learned incorporated, both laboratories will increase their cryomodule production rates to meet the challenging LCLS-II project requirement of approximately one cryomodule per month per laboratory. This paper presents the Fermilab Cryomodule Assembly Facility (CAF) infrastructure for LCLS-II cryomodule production, the Fermilab prototype 1.3 GHz CW cryomodule (pCM) assembly and readiness for production assembly.

Photoproduction of Multiply-Strange Hyperons at CLAS

Energy Technology Data Exchange (ETDEWEB)

Price, John [California State Univ., Dominguez Hills, Carson, CA (United States)

2016-08-30

The activities of the California State University, Dominguez Hills (CSUDH) Hadronic Structure Laboratory, undertaken with the support of the U.S. Department of Energy's Office of Science under grant DE-FG02-07ER41525, are described. This grant was originally awarded in 2007, and then renewed in 2009 and 2012, before it expired in 2015. The work was performed primarily at the home institution on the CSUDH campus in Carson, CA. A significant portion of the work was carried out at the Thomas Jefferson National Accelerator Facility (JLab) in Newport News, VA. The work covered in this award involves the study of the structure of the proton, which is done indirectly by looking at the Ξ particle. This is a particle with a spin and spatial structure similar to that of the proton, but with a different quark structure. Their properties are expected to be related due to SU(3)_F symmetry. Additional work performed under this grant involved the construction of the High Threshold Cherenkov Counter, which was done by CSUDH undergraduate students in collaboration with JLab staff scientists.

Facility Effluent Monitoring Plan for the 3720 Building

Energy Technology Data Exchange (ETDEWEB)

Shields, K.D.; Ballinger, M.Y.

1999-04-02

This Facility Effluent Monitoring Plan (FEMP) has been prepared for the Environmental Science Laboratory (3720 Facility) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs'' This FEMP has been prepared for the 3720 Facility primarily because it has a major (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The 3720 Facility provides office and laboratory space for PNNL scientific and engineering staff conducting multidisciplinary research in the areas of materials characterization and testing and waste management. The facility is designed to accommodate the use of radioactive and hazardous materials to conduct these activities. Radioactive material storage and usage occur throughout the facility and include a large number of isotopes. This material is in several forms, including solid, liquid, and dispersible particulate. The facility is in the process of being vacated for shutdown, but is considered a Major Emission Point as of the date of this document approval.

Westinghouse GOCO conduct of casualty drills

International Nuclear Information System (INIS)

Ames, C.P.

1996-02-01

Purpose of this document is to provide Westinghouse Government Owned Contractor Operated (GOCO) Facilities with information that can be used to implement or improve drill programs. Elements of this guide are highly recommended for use when implementing a new drill program or when assessing an existing program. Casualty drills focus on response to abnormal conditions presenting a hazard to personnel, environment, or equipment; they are distinct from Emergency Response Exercises in which the training emphasis is on site, field office, and emergency management team interaction. The DOE documents which require team training and conducting drills in nuclear facilities and should be used as guidance in non-nuclear facilities are: DOE 5480.19 (Chapter 1 of Attachment I) and DOE 5480.20 (Chapter 1, paragraphs 7 a. and d. of continuing training). Casualty drills should be an integral part of the qualification and training program at every DOE facility

Altitude simulation facility for testing large space motors

Science.gov (United States)

Katz, U.; Lustig, J.; Cohen, Y.; Malkin, I.

1993-02-01

This work describes the design of an altitude simulation facility for testing the AKM motor installed in the 'Ofeq' satellite launcher. The facility, which is controlled by a computer, consists of a diffuser and a single-stage ejector fed with preheated air. The calculations of performance and dimensions of the gas extraction system were conducted according to a one-dimensional analysis. Tests were carried out on a small-scale model of the facility in order to examine the design concept, then the full-scale facility was constructed and operated. There was good agreement among the results obtained from the small-scale facility, from the full-scale facility, and from calculations.

A Data Analysis Center for Electromagnetic and Hadronic Interaction. Products of the DAC members

Energy Technology Data Exchange (ETDEWEB)

Briscoe, William John [George Washington Univ., Washington, DC (United States); Strakovsky, Igor I. [George Washington Univ., Washington, DC (United States); Workman, Ronald L. [George Washington Univ., Washington, DC (United States)

2015-08-31

The Data Analysis Center (DAC) of the Center for Nuclear Studies (CNS) at the George Washington University (GW) has made significant progress in its program to enhance and expand the partial-wave (and multipole) analyses of fundamental two- and three-body reactions (such as pion-nucleon, photon-nucleon, and nucleon-nucleon scattering) by maintaining and augmenting the analysis codes and databases associated with these reactions. These efforts provide guidance to experimental groups at the international level, forming an important link between theory and experiment. A renaissance in light hadron spectroscopy is underway as a continuous stream of polarization data issues from existing precision electromagnetic facilities and the coming Jefferson Lab 12 GeV Upgrade. Our principal goals have been focused on supporting the national N* resonance physics program. We have also continued to study topics more generally related to the problems associated with partial-wave analysis. On the Experimental side of the CNS DAC. Its primary goal is the enhancement of the body of data necessary for our analyses of fundamental γ - N reactions. We perform experiments that study the dynamics responsible for the internal structure of the nucleon and its excitations. Our principal focus is on the N* programs at JLab and MAMI. At JLab we study spin-polarization observables using polarized photons, protons and neutrons and yielding charged final states. Similarly at MAMI we study neutral meson photoproduction off polarized protons and neutrons. We use the Crystal Ball and TAPS spectrometers (CBT) to detect photons and neutrons to measure the photoproduction of π0, η, 2π0, π0η, and K0 off the neutron. The CBT program complements our program at JLab, which studies reactions resulting in charged final states. We are also involved in a renewed effort to make neutral pion photoproduction measurements close to threshold at Mainz. In addition to the programs underway, we are contributing to

Energy efficiency in California laboratory-type facilities

Energy Technology Data Exchange (ETDEWEB)

Mills, E.; Bell, G.; Sartor, D. [and others

1996-07-31

The central aim of this project is to provide knowledge and tools for increasing the energy efficiency and performance of new and existing laboratory-type facilities in California. We approach the task along three avenues: (1) identification of current energy use and savings potential, (2) development of a {ital Design guide for energy- Efficient Research Laboratories}, and (3) development of a research agenda for focused technology development and improving out understanding of the market. Laboratory-type facilities use a considerable amount of energy resources. They are also important to the local and state economy, and energy costs are a factor in the overall competitiveness of industries utilizing laboratory-type facilities. Although the potential for energy savings is considerable, improving energy efficiency in laboratory-type facilities is no easy task, and there are many formidable barriers to improving energy efficiency in these specialized facilities. Insufficient motivation for individual stake holders to invest in improving energy efficiency using existing technologies as well as conducting related R&D is indicative of the ``public goods`` nature of the opportunity to achieve energy savings in this sector. Due to demanding environmental control requirements and specialized processes, laboratory-type facilities epitomize the important intersection between energy demands in the buildings sector and the industrial sector. Moreover, given the high importance and value of the activities conducted in laboratory-type facilities, they represent one of the most powerful contexts in which energy efficiency improvements stand to yield abundant non-energy benefits if properly applied.

Lewis Research Center space station electric power system test facilities

Science.gov (United States)

Birchenough, Arthur G.; Martin, Donald F.

1988-01-01

NASA Lewis Research Center facilities were developed to support testing of the Space Station Electric Power System. The capabilities and plans for these facilities are described. The three facilities which are required in the Phase C/D testing, the Power Systems Facility, the Space Power Facility, and the EPS Simulation Lab, are described in detail. The responsibilities of NASA Lewis and outside groups in conducting tests are also discussed.

Survey of EPA facilities for solar thermal energy applications

Science.gov (United States)

Nelson, E. V.; Overly, P. T.; Bell, D. M.

1980-01-01

A study was done to assess the feasibility of applying solar thermal energy systems to EPA facilities. A survey was conducted to determine those EPA facilities where solar energy could best be used. These systems were optimized for each specific application and the system/facility combinations were ranked on the basis of greatest cost effectiveness.

Socioeconomic issues and analyses for radioactive waste disposal facilities

International Nuclear Information System (INIS)

Ulland, L.

1988-01-01

Radioactive Waste facility siting and development can raise major social and economic issues in the host area. Initial site screening and analyses have been conducted for both potential high-level and low-level radioactive waste facilities; more detailed characterization and analyses are being planned. Results of these assessments are key to developing community plans that identify and implement measures to mitigate adverse socioeconomic impacts. Preliminary impact analyses conducted at high-level sites in Texas and Nevada, and site screening activities for low-level facilities in Illinois and California have identified a number of common socioeconomic issues and characteristics as well as issues and characteristics that differ between the sites and the type of facilities. Based on these comparisons, implications for selection of an appropriate methodology for impact assessment and elements of impact mitigation are identified

Facilities for studying the double beta decay processes

International Nuclear Information System (INIS)

Zdesenko, Yu.G.

1980-01-01

Modern state, tendencies and perspectiVes of the development of experimental installations to study double β-decay are treated. The main peculiarities of direct recognition and full experiments on the study of double β-decay are considered. A simple ratio is obtained from statistical considerations which connects the life time limits of the nuclei with the facility parameters to conduct direct recognition experiments. Possibilities of different detectors are evaluated on the basis of the ratio. Requirements for the modern technique for complete investigation of double β-decay are formulated and two designs of facilities meeting the requirements are considered. It is shown that the facility with proportional chambers is more perspective. On the basis of the analysis of the facility development to study double β-decay, conclusion is made that the final and unambiguous proof of the existence of double β-decay process can be obtained only directly in the experiments with immediate recording of the decay acts. Possibilities of the existing and developed facilities to conduct recognition (direct) experiments are such, that with their help life time limits as to neutronless double β-decay at the level of 10 21 -10 22 years can be established. Counters on the basis of the condensed noble gases, semiconductor detectors made of TeCd, scintillators of big volume are the most perspective detectors. To conduct complete experiments it is necessary to develop a facility with sensitivity sufficient for the detection of two-neutrino double β-activeness when Tsub(1/2)=10sup(21) years [ru

Decommissioning of Facilities. General Safety Requirements. Pt. 6

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-07-15

Decommissioning is the last step in the lifetime management of a facility. It must also be considered during the design, construction, commissioning and operation of facilities. This publication establishes requirements for the safe decommissioning of a broad range of facilities: nuclear power plants, research reactors, nuclear fuel cycle facilities, facilities for processing naturally occurring radioactive material, former military sites, and relevant medical, industrial and research facilities. It addresses all the aspects of decommissioning that are required to ensure safety, aspects such as roles and responsibilities, strategy and planning for decommissioning, conduct of decommissioning actions and termination of the authorization for decommissioning. It is intended for use by those involved in policy development, regulatory control and implementation of decommissioning.

Measured Radiation and Background Levels During Transmission of Megawatt Electron Beams Through Millimeter Apertures

Energy Technology Data Exchange (ETDEWEB)

Alarcon, Ricardo [Arizona State University, Glendale, AZ (United States); Balascuta, S. [Arizona State University, Glendale, AZ (United States); Benson, Stephen V. [Thomas Jefferson National Accelerator Facility, Newport News, VA (United States); Bertozzi, William [Massachusetts Institute of Technology, Cambridge, MA (United States); Boyce, James R. [Thomas Jefferson National Accelerator Facility, Newport News, VA (United States); Cowan, Ray [Massachusetts Institute of Technology, Cambridge, MA (United States); Douglas, David R. [Thomas Jefferson National Accelerator Facility, Newport News, VA (United States); Evtushenko, Pavel [Thomas Jefferson National Accelerator Facility, Newport News, VA (United States); Fisher, P. [Massachusetts Institute of Technology, Cambridge, MA (United States); Ihloff, Ernest E. [Hampton University, Hampton, VA (United States); Kalantarians, Narbe [Hampton University, Hampton, VA (United States); Kelleher, Aidan Michael [Massachusetts Institute of Technology, Cambridge, MA (United States); Krossler, W. J. [William and Mary College, Williamsburg, VA (United States); Legg, Robert A. [Thomas Jefferson National Accelerator Facility, Newport News, VA (United States); Long, Elena [University of New Hampshire, Durham, NH (United States); Milner, Richard [Massachusetts Institute of Technology, Cambridge, MA (United States); Neil, George R. [Thomas Jefferson National Accelerator Facility, Newport News, VA (United States); Ou, Longwu [Massachusetts Institute of Technology, Cambridge, MA (United States); Schmookler, Barack Abraham [Massachusetts Institute of Technology, Cambridge, MA (United States); Tennant, Christopher D. [Thomas Jefferson National Accelerator Facility, Newport News, VA (United States); Tschalar, C. [Massachusetts Institute of Technology, Cambridge, MA (United States); Williams, Gwyn P. [Thomas Jefferson National Accelerator Facility, Newport News, VA (United States); Zhang, Shukui [Thomas Jefferson National Accelerator Facility, Newport News, VA (United States)

2013-11-01

We report measurements of photon and neutron radiation levels observed while transmitting a 0.43 MW electron beam through millimeter-sized apertures and during beam-off, but accelerating gradient RF-on, operation. These measurements were conducted at the Free-Electron Laser (FEL) facility of the Jefferson National Accelerator Laboratory (JLab) using a 100 MeV electron beam from an energy-recovery linear accelerator. The beam was directed successively through 6 mm, 4 mm, and 2 mm diameter apertures of length 127 mm in aluminum at a maximum current of 4.3 mA (430 kW beam power). This study was conducted to characterize radiation levels for experiments that need to operate in this environment, such as the proposed DarkLight Experiment. We find that sustained transmission of a 430 kW continuous-wave (CW) beam through a 2 mm aperture is feasible with manageable beam-related backgrounds. We also find that during beam-off, RF-on operation, multipactoring inside the niobium cavities of the accelerator cryomodules is the primary source of ambient radiation when the machine is tuned for 130 MeV operation.

Macro Security Methodology for Conducting Facility Security and Sustainability Assessments

International Nuclear Information System (INIS)

Herdes, Greg A.; Freier, Keith D.; Wright, Kyle A.

2007-01-01

Pacific Northwest National Laboratory (PNNL) has developed a macro security strategy that not only addresses traditional physical protection systems, but also focuses on sustainability as part of the security assessment and management process. This approach is designed to meet the needs of virtually any industry or environment requiring critical asset protection. PNNL has successfully demonstrated the utility of this macro security strategy through its support to the NNSA Office of Global Threat Reduction implementing security upgrades at international facilities possessing high activity radioactive sources that could be used in the assembly of a radiological dispersal device, commonly referred to as a 'dirty bomb'. Traditional vulnerability assessments provide a snap shot in time of the effectiveness of a physical protection system without significant consideration to the sustainability of the component elements that make up the system. This paper describes the approach and tools used to integrate technology, plans and procedures, training, and sustainability into a simple, quick, and easy-to-use security assessment and management tool.

Developing a model lifeline protection program for DOE facilities

International Nuclear Information System (INIS)

Lowing, A.N.

1996-01-01

A National Lifeline Standard Development Program is currently being conducted by FEMA and NIST. The Department of Energy is following these developments and supplementing them to meet Life-Safety and mission requirements for all DOE facilities as part of the Natural Phenomena Hazards Mitigation Plan. The task will be overseen by a DOE management team with technical guidance provided by a Steering Group of management and operating contractor representatives. The DOE will participate in the federal program by conducting a workshop on lifeline protection issues, developing an overall plan, organizing a Steering Group, and conducting a pilot study at a DOE facility

Underground characterisation and research facility ONKALO

International Nuclear Information System (INIS)

Ikonen, Antti; Ylae-Mella, Mia; Aeikaes, Timo

2006-01-01

Posiva's repository for geological disposal of the spent fuel from Finnish nuclear reactors will be constructed at Olkiluoto. The selection of Olkiluoto was made based on site selection research programme conducted between 1987-2001. The next step is to carry out complementary investigations of the site and apply for the construction license for the disposal facility. The license application will be submitted in 2012. To collect detailed information of the geological environment at planned disposal depth an underground characterisation and research facility will be built at the site. This facility, named as ONKALO, will comprise a spiral access tunnel and two vertical shafts. The excavation of ONKALO is in progress and planned depth (400 m) will be reached in 2009. During the course of the excavation Posiva will conduct site characterisation activities to assess the structure and other properties of the site geology. The aim is that construction will not compromise the favourable conditions of the planned disposal depth or introduce harmful effects in the surrounding bedrock which could jeopardize the long-term safety of the geological disposal. (author)

Trauma facilities in Denmark - a nationwide cross-sectional benchmark study of facilities and trauma care organisation.

Science.gov (United States)

Weile, Jesper; Nielsen, Klaus; Primdahl, Stine C; Frederiksen, Christian A; Laursen, Christian B; Sloth, Erik; Mølgaard, Ole; Knudsen, Lars; Kirkegaard, Hans

2018-03-27

Trauma is a leading cause of death among adults aged facilities and the use multidisciplinary trauma teams. Because knowledge is sparse on the existing distribution of trauma facilities and the organisation of trauma care in Denmark, the aim of this study was to identify all Danish facilities that care for traumatized patients and to investigate the diversity in organization of trauma management. We conducted a systematic observational cross-sectional study. First, all hospitals in Denmark were identified via online services and clarifying phone calls to each facility. Second, all trauma care manuals on all facilities that receive traumatized patients were gathered. Third, anesthesiologists and orthopedic surgeons on call at all trauma facilities were contacted via telephone for structured interviews. A total of 22 facilities in Denmark were found to receive traumatized patients. All facilities used a trauma care manual and all had a multidisciplinary trauma team. The study found three different trauma team activation criteria and nine different compositions of teams who participate in trauma care. Training was heterogeneous and, beyond the major trauma centers, databases were only maintained in a few facilities. The study established an inventory of the existing Danish facilities that receive traumatized patients. The trauma team activation criteria and the trauma teams were heterogeneous in both size and composition. A national database for traumatized patients, research on nationwide trauma team activation criteria, and team composition guidelines are all called for.

Profiles of facilities used for HTR research and testing

International Nuclear Information System (INIS)

1980-05-01

This report contains a current description of facilities supporting HTR research and development submitted by countries participating in the IWGFR. It has the purpose of providing an overview of the facilities available for use and of the types of experiments that can be conducted therein

A qualitative analysis of facilities maintenance — A school ...

African Journals Online (AJOL)

I analysed school facilities maintenance, a school governance function in South Africa. Qualitative interviews were conducted with 13 principals and three deputy principals as coordinators of this function at their schools. The interviews were purposively and conveniently selected to gather data regarding school facilities ...

HOM Survey of the First CEBAF Upgrade Style Cavity Pair

International Nuclear Information System (INIS)

Marhauser, Frank; Daly, Edward; Davis, G.; Drury, Michael; Grenoble, Christiana; Hogan, John; Manus, Robert; Preble, Joseph; Reece, Charles; Rimmer, Robert; Tian, Kai; Wang, Haipeng

2009-01-01

The planned upgrade of the Continuous Electron Beam Accelerator Facility (CEBAF) at the Thomas Jefferson National Accelerator Laboratory (JLab) requires ten new superconducting rf (SRF) cavity cryomodules to double the beam energy to the envisaged 12 GeV. Adequate cavity Higher Order Mode (HOM) suppression is essential to avoid multipass, multibunch beam break-up (BBU) instabilities of the recirculating beam. We report on detailed HOM surveys performed for the first two upgrade style cavities tested in a dedicated cavity pair cryomodule at 2K. The safety margin to the BBU threshold budget at 12 GeV has been assessed.

340 Facility maintenance implementation plan

International Nuclear Information System (INIS)

1995-03-01

This Maintenance Implementation Plan (MIP) has been developed for maintenance functions associated with the 340 Facility. This plan is developed from the guidelines presented by Department of Energy (DOE) Order 4330.4B, Maintenance Management Program (DOE 1994), Chapter II. The objective of this plan is to provide baseline information for establishing and identifying Westinghouse Hanford Company (WHC) conformance programs and policies applicable to implementation of DOE order 4330.4B guidelines. In addition, this maintenance plan identifies the actions necessary to develop a cost-effective and efficient maintenance program at the 340 Facility. Primary responsibility for the performance and oversight of maintenance activities at the 340 Facility resides with Westinghouse Hanford Company (WHC). Maintenance at the 340 Facility is performed by ICF-Kaiser Hanford (ICF-KH) South Programmatic Services crafts persons. This 340 Facility MIP provides interface requirements and responsibilities as they apply specifically to the 340 Facility. This document provides an implementation schedule which has been developed for items considered to be deficient or in need of improvement. The discussion sections, as applied to implementation at the 340 Facility, have been developed from a review of programs and practices utilizing the graded approach. Biennial review and additional reviews are conducted as significant programmatic and mission changes are made. This document is revised as necessary to maintain compliance with DOE requirements

340 Facility maintenance implementation plan

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-03-01

This Maintenance Implementation Plan (MIP) has been developed for maintenance functions associated with the 340 Facility. This plan is developed from the guidelines presented by Department of Energy (DOE) Order 4330.4B, Maintenance Management Program (DOE 1994), Chapter II. The objective of this plan is to provide baseline information for establishing and identifying Westinghouse Hanford Company (WHC) conformance programs and policies applicable to implementation of DOE order 4330.4B guidelines. In addition, this maintenance plan identifies the actions necessary to develop a cost-effective and efficient maintenance program at the 340 Facility. Primary responsibility for the performance and oversight of maintenance activities at the 340 Facility resides with Westinghouse Hanford Company (WHC). Maintenance at the 340 Facility is performed by ICF-Kaiser Hanford (ICF-KH) South Programmatic Services crafts persons. This 340 Facility MIP provides interface requirements and responsibilities as they apply specifically to the 340 Facility. This document provides an implementation schedule which has been developed for items considered to be deficient or in need of improvement. The discussion sections, as applied to implementation at the 340 Facility, have been developed from a review of programs and practices utilizing the graded approach. Biennial review and additional reviews are conducted as significant programmatic and mission changes are made. This document is revised as necessary to maintain compliance with DOE requirements.

Quality of the delivery services in health facilities in Northern Ethiopia.

Science.gov (United States)

Fisseha, Girmatsion; Berhane, Yemane; Worku, Alemayehu; Terefe, Wondwossen

2017-03-09

Substantial improvements have been observed in the coverage of and access to maternal health service, especially in skilled birth attendants, in Ethiopia. However, the quality of care has been lagging behind. Therefore, this study investigated the status of the quality of delivery services in Northern Ethiopia. A facility based survey was conducted from December 2014 to February 2015 in Northern Ethiopia. The quality of delivery service was assessed in 32 health facilities using a facility audit checklist, by reviewing delivery, by conducting in-depth interview and observation, and by conducting exit interviews with eligible mothers. Facilities were considered as 'good quality' if they scored positively on 75% of the quality indicators set in the national guidelines for all the three components; input (materials, infrastructure, and human resource), process (adherence to standard care procedures during intrapartum and immediate postpartum periods) and output (the mothers' satisfaction and utilization of lifesaving procedures). Overall 2 of 32 (6.3%) of the study facilities fulfilled all the three quality components; input, process and output. Two of the three components were assessed as good in 11 of the 32 (34.4%) health facilities. The input quality was the better of the other quality components; which was good in 21 out of the 32 (65.6%) health facilities. The process and output quality was good in only 10 of the 32 (31.3%) facilities. Only 6.3% of the studied health facilities had good quality in all three dimensions of quality measures that was done in accordance to the national delivery service guidelines. The most compromised quality component was the process. Systematic and sustained efforts need to be strengthened to improve all dimensions of quality in order to achieve the desired quality of delivery services and increase the proportion of births occurring in health facilities.

A new facility for advanced rocket propulsion research

Science.gov (United States)

Zoeckler, Joseph G.; Green, James M.; Raitano, Paul

1993-06-01

A new test facility was constructed at the NASA Lewis Research Center Rocket Laboratory for the purpose of conducting rocket propulsion research at up to 8.9 kN (2000 lbf) thrust, using liquid oxygen and gaseous hydrogen propellants. A laser room adjacent to the test cell provides access to the rocket engine for advanced laser diagnostic systems. The size and location of the test cell provide the ability to conduct large amounts of testing in short time periods, with rapid turnover between programs. These capabilities make the new test facility an important asset for basic and applied rocket propulsion research.

Evaluation of scaling concepts for integral system test facilities

International Nuclear Information System (INIS)

Condie, K.G.; Larson, T.K.; Davis, C.B.

1987-01-01

A study was conducted by EG and G Idaho, Inc., to identify and technically evaluate potential concepts which will allow the U.S. Nuclear Regulatory Commission to maintain the capability to conduct future integral, thermal-hydraulic facility experiments of interest to light water reactor safety. This paper summarizes the methodology used in the study and presents a rankings for each facility concept relative to its ability to simulate phenomena identified as important in selected reactor transients in Babcock and Wilcox and Westinghouse large pressurized water reactors. Established scaling methodologies are used to develop potential concepts for scaled integral thermal-hydraulic experiment facilities. Concepts selected included: full height, full pressure water; reduced height, reduced pressure water; reduced height, full pressure water; one-tenth linear, full pressure water; and reduced height, full scaled pressure Freon. Results from this study suggest that a facility capable of operating at typical reactor operating conditions will scale most phenomena reasonably well. Local heat transfer phenomena is best scaled by the full height facility, while the reduced height facilities provide better scaling where multi-dimensional phenomena are considered important. Although many phenomena in facilities using Freon or water at nontypical pressure will scale reasonably well, those phenomena which are heavily dependent on quality can be distorted. Furthermore, relation of data produced in facilities operating with nontypical fluids or at nontypical pressures to large plants will be a difficult and time-consuming process

Electromagnetic Interference (EMI) and TEMPEST Test Facility

Data.gov (United States)

Federal Laboratory Consortium — Electromagnetic Interference (EMI), Electromagnetic Compatibility (EMC) and TEMPEST testing are conducted at EPG's Blacktail Canyon Test Facility in one of its two...

A security/safety survey of long term care facilities.

Science.gov (United States)

Acorn, Jonathan R

2010-01-01

What are the major security/safety problems of long term care facilities? What steps are being taken by some facilities to mitigate such problems? Answers to these questions can be found in a survey of IAHSS members involved in long term care security conducted for the IAHSS Long Term Care Security Task Force. The survey, the author points out, focuses primarily on long term care facilities operated by hospitals and health systems. However, he believes, it does accurately reflect the security problems most long term facilities face, and presents valuable information on security systems and practices which should be also considered by independent and chain operated facilities.

Saltstone studies using the scaled continuous processing facility

Energy Technology Data Exchange (ETDEWEB)

Fowley, M. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Cozzi, A. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hansen, E. K. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2015-08-01

The Savannah River National Laboratory (SRNL) has supported the Saltstone Facility since its conception with bench-scale laboratory experiments, mid-scale testing at vendor facilities, and consultations and testing at the Saltstone Facility. There have been minimal opportunities for the measurement of rheological properties of the grout slurry at the Saltstone Production Facility (SPF); thus, the Scaled Continuous Processing Facility (SCPF), constructed to provide processing data related to mixing, transfer, and other operations conducted in the SPF, is the most representative process data for determining the expected rheological properties in the SPF. These results can be used to verify the laboratory scale experiments that support the SPF using conventional mixing processes that appropriately represent the shear imparted to the slurry in the SPF.

Authorization basis status report (miscellaneous TWRS facilities, tanks and components)

Energy Technology Data Exchange (ETDEWEB)

Stickney, R.G.

1998-04-29

This report presents the results of a systematic evaluation conducted to identify miscellaneous TWRS facilities, tanks and components with potential needed authorization basis upgrades. It provides the Authorization Basis upgrade plan for those miscellaneous TWRS facilities, tanks and components identified.

Authorization basis status report (miscellaneous TWRS facilities, tanks and components)

International Nuclear Information System (INIS)

Stickney, R.G.

1998-01-01

This report presents the results of a systematic evaluation conducted to identify miscellaneous TWRS facilities, tanks and components with potential needed authorization basis upgrades. It provides the Authorization Basis upgrade plan for those miscellaneous TWRS facilities, tanks and components identified

Spent Fuel Handling and Packaging Program: a survey of hot cell facilities

International Nuclear Information System (INIS)

Menon, M.N.

1978-07-01

Hot cell facilities in the United States were surveyed to determine their capabilities for conducting integral fuel assembly and individual fuel rod examinations that are required in support of the Spent Fuel Handling and Packaging Program. The ability to receive, handle, disassemble and reconstitute full-length light water reactor spent fuel assemblies, and the ability to conduct nondestructive and destructive examinations on full-length fuel rods were of particular interest. Three DOE-supported facilities and three commercial facilities were included in the survey. This report provides a summary of the findings

Fractal analysis of the hydraulic conductivity on a sandy porous media reproduced in a laboratory facility.

Science.gov (United States)

de Bartolo, S.; Fallico, C.; Straface, S.; Troisi, S.; Veltri, M.

2009-04-01

The complexity characterization of the porous media structure, in terms of the "pore" phase and the "solid" phase, can be carried out by means of the fractal geometry which is able to put in relationship the soil structural properties and the water content. It is particularly complicated to describe analytically the hydraulic conductivity for the irregularity of the porous media structure. However these can be described by many fractal models considering the soil structure as the distribution of particles dimensions, the distribution of the solid aggregates, the surface of the pore-solid interface and the fractal mass of the "pore" and "solid" phases. In this paper the fractal model of Yu and Cheng (2002) and Yu and Liu (2004), for a saturated bidispersed porous media, was considered. This model, using the Sierpinsky-type gasket scheme, doesn't contain empiric constants and furnishes a well accord with the experimental data. For this study an unconfined aquifer was reproduced by means of a tank with a volume of 10 Ã- 7 Ã- 3 m3, filled with a homogeneous sand (95% of SiO2), with a high percentage (86.4%) of grains between 0.063mm and 0.125mm and a medium-high permeability. From the hydraulic point of view, 17 boreholes, a pumping well and a drainage ring around its edge were placed. The permeability was measured utilizing three different methods, consisting respectively in pumping test, slug test and laboratory analysis of an undisturbed soil cores, each of that involving in the measurement a different support volume. The temporal series of the drawdown obtained by the pumping test were analyzed by the Neuman-type Curve method (1972), because the saturated part above the bottom of the facility represents an unconfined aquifer. The data analysis of the slug test were performed by the Bouwer & Rice (1976) method and the laboratory analysis were performed on undisturbed saturated soil samples utilizing a falling head permeameter. The obtained values either of the

Nuclear criticality safety program at the Fuel Cycle Facility

International Nuclear Information System (INIS)

Lell, R.M.; Fujita, E.K.; Tracy, D.B.; Klann, R.T.; Imel, G.R.; Benedict, R.W.; Rigg, R.H.

1994-01-01

The Fuel Cycle Facility (FCF) is designed to demonstrate the feasibility of a novel commercial-scale remote pyrometallurgical process for metallic fuels from liquid metal-cooled reactors and to show closure of the Integral Fast Reactor (IFR) fuel cycle. Requirements for nuclear criticality safety impose the most restrictive of the various constraints on the operation of FCF. The upper limits on batch sizes and other important process parameters are determined principally by criticality safety considerations. To maintain an efficient operation within appropriate safety limits, it is necessary to formulate a nuclear criticality safety program that integrates equipment design, process development, process modeling, conduct of operations, a measurement program, adequate material control procedures, and nuclear criticality analysis. The nuclear criticality safety program for FCF reflects this integration, ensuring that the facility can be operated efficiently without compromising safety. The experience gained from the conduct of this program in the Fuel cycle Facility will be used to design and safely operate IFR facilities on a commercial scale. The key features of the nuclear criticality safety program are described. The relationship of these features to normal facility operation is also described

42 CFR 483.450 - Condition of participation: Client behavior and facility practices.

Science.gov (United States)

2010-10-01

... 42 Public Health 5 2010-10-01 2010-10-01 false Condition of participation: Client behavior and... Retarded § 483.450 Condition of participation: Client behavior and facility practices. (a) Standard: Facility practices—Conduct toward clients. (1) The facility must develop and implement written policies and...

Near-facility environmental monitoring

Energy Technology Data Exchange (ETDEWEB)

Schmidt, J.W.; Johnson, A.R.; Markes, B.M.; McKinney, S.M.; Perkins, C.J.

1995-06-01

This section of the 1994 Hanford Site Environmental Report summarizes the routine near-facility environmental monitoring programs which are presently being conducted at the Hanford Site. Several types of environmental media are sampled near nuclear facilities to monitor the effectiveness of waste management and restoration activities, and effluent treatment and control practices. These media include air, surface water and springs, surface contamination, soil and vegetation, investigative sampling (which can include wildlife), and external radiation. Sampling and analysis information and analytical results for 1994 for each of these media are summarized in this section. Additional data and more detailed information may be found in Westinghouse Hanford Company Operational Environmental Monitoring Annual Report, Calendar Year 1994.

Long conduction time POs experiments on MITE

International Nuclear Information System (INIS)

Woodall, H.N.; McDaniel, D.H.; Mendel, C.W.; Rochau, G.E.; Zagar, D.M.; Simpson, W.W.; Zuchowski, N.P.

1990-01-01

MITE is a power flow test bed that has been modified to conduct experiments in high power plasma opening switch (POS) technology and apply this technology to Inertial Confinement Fusion. The goal of the experiment is to develop a plasma opening switch that conducts megampere currents for 300 ns, then opens in 5--10 ns. MITE/POS is an advanced power flow experiment that uses a magnetically insulated transmission line (MITL) as the inductive energy store and as a means to shape the output pulse. This experiment demonstrates that a simplified, lower-cost facility can be built by eliminating water pulse-forming lines and water-switching. Another advantage of this approach is that high energy efficiency at peak power can be achieved. The disadvantage is that a new technology, the triggered POS, must be implemented. The triggered POS is necessary for synchronization of multiple modules with a long conduction-time POS. The MITE facility has been modified to drive a 250 nH, 16.6 Ohm MITL at 0.9 MA to accommodate this power flow experiment. A MITL inductive energy storage of 101 kJ is available for POS switching to a matched load. Experiments have been conducted using segmented flashboards and magnetic-field controlled plasma sources. These experiments will lead to the development of the triggered POS. The initial experiments with plasma conduction times of 120 ns to 800 ns are discussed

Waste Encapsulation and Storage Facility (WESF) Hazards Assessment

International Nuclear Information System (INIS)

COVEY, L.I.

2000-01-01

This report documents the hazards assessment for the Waste Encapsulation and Storage Facility (WESF) located on the U.S. Department of Energy (DOE) Hanford Site. This hazards assessment was conducted to provide the emergency planning technical basis for WESF. DOE Orders require an emergency planning hazards assessment for each facility that has the potential to reach or exceed the lowest level emergency classification

Radiological characterization of the TAN-IET facility

Energy Technology Data Exchange (ETDEWEB)

Koeppen, L.D.; Rodriguez, S.V.; Wheeler, O.A.; Cadwell, E.D.; Simpson, O.D.

1982-06-01

The Initial Engine Test (IET) facility is located on the Idaho National Engineering Laboratory (INEL) site at the north end of Test Area North (TAN). The IET facility was constructed and used for the Aircraft Nuclear Propulsion Program during the 1950's and was later used for two other programs: the Space Nuclear Auxiliary Power Transient (SNAP-TRAN) and the Hallam Decontamination and Decommissioning Project. The facility is no longer in use, therefore, a complete radiological characterization was conducted at the IET site. The characterization included measurements of beta-gamma dose rates; beta-gamma and alpha surface contamination; concentrations of selected radionuclides in subsurface storage tanks, surface soil, the exhaust duct, stack and test pad; and a walk-over surface survey of the entire facility. The information contained in this report will be of great value as the IET facility goes through the decommissioning and decontamination process.

Liquefied Gaseous Fuels Spill Test Facility

International Nuclear Information System (INIS)

1993-02-01

The US Department of Energy's liquefied Gaseous Fuels Spill Test Facility is a research and demonstration facility available on a user-fee basis to private and public sector test and training sponsors concerned with safety aspects of hazardous chemicals. Though initially designed to accommodate large liquefied natural gas releases, the Spill Test Facility (STF) can also accommodate hazardous materials training and safety-related testing of most chemicals in commercial use. The STF is located at DOE's Nevada Test Site near Mercury, Nevada, USA. Utilization of the Spill Test Facility provides a unique opportunity for industry and other users to conduct hazardous materials testing and training. The Spill Test Facility is the only facility of its kind for either large- or small-scale testing of hazardous and toxic fluids including wind tunnel testing under controlled conditions. It is ideally suited for test sponsors to develop verified data on prevention, mitigation, clean-up, and environmental effects of toxic and hazardous gaseous liquids. The facility site also supports structured training for hazardous spills, mitigation, and clean-up. Since 1986, the Spill Test Facility has been utilized for releases to evaluate the patterns of dispersion, mitigation techniques, and combustion characteristics of select materials. Use of the facility can also aid users in developing emergency planning under US P.L 99-499, the Superfund Amendments and Reauthorization Act of 1986 (SARA) and other regulations. The Spill Test Facility Program is managed by the US Department of Energy (DOE), Office of Fossil Energy (FE) with the support and assistance of other divisions of US DOE and the US Government. DOE/FE serves as facilitator and business manager for the Spill Test Facility and site. This brief document is designed to acquaint a potential user of the Spill Test Facility with an outline of the procedures and policies associated with the use of the facility

Using Tools of Strategic Management in Medical Facilities of Lublin Region

Directory of Open Access Journals (Sweden)

Jaworzynska Magdalena

2017-06-01

Full Text Available The purpose of this article is to evaluate the use of tools of strategic management in hospitals in Lublin region. The study was conducted among 14 medical entities from the area of Lublin Voivodeship. The survey was addressed to economic directors or chief accountants of health care facilities and sent by post. The questionnaire was also helpful in conducting an in-depth interview as it provided a required structure. As part of the interviews with managers of health care facilities, information beyond the questionnaire was acquired, e.g. about the mission. According to studies, most health care facilities develop strategic plans (71.4%. For 21.4% of the studied facilities, the strategic plan is known mainly to management. In contrast, 28.6% of entities do not have a strategic plan. The presented results of the research can increase the effectiveness of activities in each area of the health care facility, continuous process improvement and rapid response to changes in the environment.

Race, Wealth, and Solid Waste Facilities in North Carolina

OpenAIRE

Norton, Jennifer M.; Wing, Steve; Lipscomb, Hester J.; Kaufman, Jay S.; Marshall, Stephen W.; Cravey, Altha J.

2007-01-01

Background Concern has been expressed in North Carolina that solid waste facilities may be disproportionately located in poor communities and in communities of color, that this represents an environmental injustice, and that solid waste facilities negatively impact the health of host communities. Objective Our goal in this study was to conduct a statewide analysis of the location of solid waste facilities in relation to community race and wealth. Methods We used census block groups to obtain ...

Cold Vacuum Drying Facility hazard analysis report

Energy Technology Data Exchange (ETDEWEB)

Krahn, D.E.

1998-02-23

This report describes the methodology used in conducting the Cold Vacuum Drying Facility (CVDF) hazard analysis to support the CVDF phase 2 safety analysis report (SAR), and documents the results. The hazard analysis was performed in accordance with DOE-STD-3009-94, Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, and implements the requirements of US Department of Energy (DOE) Order 5480.23, Nuclear Safety Analysis Reports.

Cold Vacuum Drying Facility hazard analysis report

International Nuclear Information System (INIS)

Krahn, D.E.

1998-01-01

This report describes the methodology used in conducting the Cold Vacuum Drying Facility (CVDF) hazard analysis to support the CVDF phase 2 safety analysis report (SAR), and documents the results. The hazard analysis was performed in accordance with DOE-STD-3009-94, Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, and implements the requirements of US Department of Energy (DOE) Order 5480.23, Nuclear Safety Analysis Reports

New Waste Calcining Facility (NWCF) Waste Streams

International Nuclear Information System (INIS)

K. E. Archibald

1999-01-01

This report addresses the issues of conducting debris treatment in the New Waste Calcine Facility (NWCF) decontamination area and the methods currently being used to decontaminate material at the NWCF

Liquid Metal Fast Breeder Reactor Program: Argonne facilities

International Nuclear Information System (INIS)

Stephens, S.V.

1976-09-01

The objective of the document is to present in one volume an overview of the Argonne National Laboratory test facilities involved in the conduct of the national LMFBR research and development program. Existing facilities and those under construction or authorized as of September 1976 are described. Each profile presents brief descriptions of the overall facility and its test area and data relating to its experimental and testing capability. The volume is divided into two sections: Argonne-East and Argonne-West. Introductory material for each section includes site and facility maps. The profiles are arranged alphabetically by title according to their respective locations at Argonne-East or Argonne-West. A glossary of acronyms and letter designations in common usage to describe organizations, reactor and test facilities, components, etc., involved in the LMFBR program is appended

Decommissioning plan depleted uranium manufacturing facility

International Nuclear Information System (INIS)

Bernhardt, D.E.; Pittman, J.D.; Prewett, S.V.

1987-01-01

Aerojet Ordnance Tennessee, Inc. (Aerojet) is decommissioning its California depleted uranium (DU) manufacturing facility. Aerojet has conducted manufacturing and research and development activities at the facility since 1977 under a State of California Source Materials License. The decontamination is being performed by a contractor selector for technical competence through competitive bid. Since the facility will be released for uncontrolled use it will be decontaminated to levels as low as reasonably achievable (ALARA). In order to fully apply the principles of ALARA, and ensure the decontamination is in full compliance with appropriate guides, Aerojet has retained Rogers and Associaties Engineering Corporation (RAE) to assist in the decommissioning. RAE has assisted in characterizing the facility and preparing contract bid documents and technical specifications to obtain a qualified decontamination contractor. RAE will monitor the decontamination work effort to assure the contractor's performance complies with the contract specifications and the decontamination plan. The specifications require a thorough cleaning and decontamination of the facility, not just sufficient cleaning to meet the numeric cleanup criteria

Assessment of the proposed decontamination and waste treatment facility at LLNL

International Nuclear Information System (INIS)

Cohen, J.J.

1987-01-01

To provide a centralized decontamination and waste treatment facility (DWTF) at LLNL, the construction of a new installation has been planned. Objectives for this new facility were to replace obsolete, structurally and environmentally sub-marginal liquid and solid waste process facilities and decontamination facility and to bring these facilities into compliance with existing federal, state and local regulations as well as DOE orders. In a previous study, SAIC conducted a preliminary review and evaluation of existing facilities at LLNL and cost effectiveness of the proposed DWTF. This document reports on a detailed review of specific aspects of the proposed DWTF

Hanford Facility Resource Conservation and Recovery Act Permit General Inspection Plan

International Nuclear Information System (INIS)

Beagles, D.S.

1995-02-01

This inspection plan describes the activities that shall be conducted for a general inspection of the Hanford Facility. RCRA includes a requirement that general facility inspections be conducted of the 100, 200 East, 200 West, 300, 400, and 1100 areas and the banks of the Columbia River. This plan meets the RCRA requirements and also provides for scheduling of inspections and defines general and specific items to be noted during the inspections

Enclosed Small and Medium Caliber Firing Experimental Facility

Data.gov (United States)

Federal Laboratory Consortium — This facility conducts completely instrumented terminal ballistics experimental tests with small and medium-caliber tungsten alloy penetrators against advanced armor...

Decommissioning of Facilities. General Safety Requirements. Pt. 6 (Spanish Edition)

International Nuclear Information System (INIS)

2017-01-01

Decommissioning is the last step in the lifetime management of a facility. It must also be considered during the design, construction, commissioning and operation of facilities. This publication establishes requirements for the safe decommissioning of a broad range of facilities: nuclear power plants, research reactors, nuclear fuel cycle facilities, facilities for processing naturally occurring radioactive material, former military sites, and relevant medical, industrial and research facilities. It addresses all the aspects of decommissioning that are required to ensure safety, aspects such as roles and responsibilities, strategy and planning for decommissioning, conduct of decommissioning actions and termination of the authorization for decommissioning. It is intended for use by those involved in policy development, regulatory control and implementation of decommissioning.

Decommissioning of Facilities. General Safety Requirements. Pt. 6 (Russian Edition)

International Nuclear Information System (INIS)

2015-01-01

Decommissioning is the last step in the lifetime management of a facility. It must also be considered during the design, construction, commissioning and operation of facilities. This publication establishes requirements for the safe decommissioning of a broad range of facilities: nuclear power plants, research reactors, nuclear fuel cycle facilities, facilities for processing naturally occurring radioactive material, former military sites, and relevant medical, industrial and research facilities. It addresses all the aspects of decommissioning that are required to ensure safety, aspects such as roles and responsibilities, strategy and planning for decommissioning, conduct of decommissioning actions and termination of the authorization for decommissioning. It is intended for use by those involved in policy development, regulatory control and implementation of decommissioning

Environmental Survey preliminary report, Pantex Facility, Amarillo, Texas

International Nuclear Information System (INIS)

1987-09-01

This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Pantex Facility, conducted November 3 through 14, 1986.The Survey is being conducted by an interdisciplinary team of environmental specialist, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Individual team components are outside experts being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the Pantex Facility. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at the Pantex Facility, and interviews with site personnel. The Survey team developed a Sampling and Analysis Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The Sampling and Analysis Plan will be executed by the Oak Ridge National Laboratory. When completed, the results will be incorporated into the Pantex Facility Environmental Survey Interim Report. The Interim Report will reflect the final determinations of the Survey for the Pantex Facility. 65 refs., 44 figs., 27 tabs

Environmental Survey preliminary report, Pantex Facility, Amarillo, Texas

Energy Technology Data Exchange (ETDEWEB)

1987-09-01

This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Pantex Facility, conducted November 3 through 14, 1986.The Survey is being conducted by an interdisciplinary team of environmental specialist, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Individual team components are outside experts being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the Pantex Facility. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at the Pantex Facility, and interviews with site personnel. The Survey team developed a Sampling and Analysis Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The Sampling and Analysis Plan will be executed by the Oak Ridge National Laboratory. When completed, the results will be incorporated into the Pantex Facility Environmental Survey Interim Report. The Interim Report will reflect the final determinations of the Survey for the Pantex Facility. 65 refs., 44 figs., 27 tabs.

Emergency preparedness exercises for nuclear facilities: Preparation, conduct and evaluation

International Nuclear Information System (INIS)

1985-01-01

This publication offers guidance for operating organizations and public authorities on planning, organizing and conducting exercises, preparing scenarios and evaluating the results of exercises in order to make full use of the experience gained in improving the response planning and preparedness for radiation emergencies. The training aspects associated with achieving an adequate level of emergency preparedness are explored and examples of accident scenarios are presented

Nonreactor nuclear facilities: Standards and criteria guide

International Nuclear Information System (INIS)

Brynda, W.J.; Scarlett, C.H.; Tanguay, G.E.; Lobner, P.R.

1986-09-01

This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE 5480.1A, Chapter V, ''Safety of Nuclear Facilities.'' The guidance and criteria provided is directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, conduct of operations, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines. 25 figs., 62 tabs

A facile approach to spinning multifunctional conductive elastomer fibres with nanocarbon fillers

International Nuclear Information System (INIS)

Seyedin, Shayan; Razal, Joselito M; Innis, Peter C; Wallace, Gordon G

2016-01-01

Electrically conductive elastomeric fibres prepared using a wet-spinning process are promising materials for intelligent textiles, in particular as a strain sensing component of the fabric. However, these fibres, when reinforced with conducting fillers, typically result in a compromise between mechanical and electrical properties and, ultimately, in the strain sensing functionality. Here we investigate the wet-spinning of polyurethane (PU) fibres with a range of conducting fillers such as carbon black (CB), single-walled carbon nanotubes (SWCNTs), and chemically converted graphene. We show that the electrical and mechanical properties of the composite fibres were strongly dependent on the aspect ratio of the filler and the interaction between the filler and the elastomer. The high aspect ratio SWCNT filler resulted in fibres with the highest electrical properties and reinforcement, while the fibres produced from the low aspect ratio CB had the highest stretchability. Furthermore, PU/SWCNT fibres presented the largest sensing range (up to 60% applied strain) and the most consistent and stable cyclic sensing behaviour. This work provides an understanding of the important factors that influence the production of conductive elastomer fibres by wet-spinning, which can be woven or knitted into textiles for the development of wearable strain sensors. (paper)

Radiation monitoring considerations for radiobiology facilities

International Nuclear Information System (INIS)

McClelland, T.W.; McFall, E.D.

1976-01-01

Battelle, Pacific Northwest Laboratories, conducts a wide variety of radiobiology and radioecology research in a number of facilities on the Hanford Reservation. Review of radiation monitoring problems associated with storage, plant and animal experiments, waste handling and sterile facilities shows that careful monitoring, strict procedural controls and innovative techniques are required to minimize occupational exposure and control contamination. Although a wide variety of radioactivity levels are involved, much of the work is with extremely low level materials. Monitoring low level work is mundane and often impractical but cannot be ignored in today's ever tightening controls

University multi-user facility survey-2010.

Science.gov (United States)

Riley, Melissa B

2011-12-01

Multi-user facilities serve as a resource for many universities. In 2010, a survey was conducted investigating possible changes and successful characteristics of multi-user facilities, as well as identifying problems in facilities. Over 300 surveys were e-mailed to persons identified from university websites as being involved with multi-user facilities. Complete responses were received from 36 facilities with an average of 20 years of operation. Facilities were associated with specific departments (22%), colleges (22%), and university research centers (8.3%) or were not affiliated with any department or college within the university (47%). The five most important factors to succeed as a multi-user facility were: 1) maintaining an experienced, professional staff in an open atmosphere; 2) university-level support providing partial funding; 3) broad client base; 4) instrument training programs; and 5) an effective leader and engaged strategic advisory group. The most significant problems were: 1) inadequate university financial support and commitment; 2) problems recovering full service costs from university subsidies and user fees; 3) availability of funds to repair and upgrade equipment; 4) inability to retain highly qualified staff; and 5) unqualified users dirtying/damaging equipment. Further information related to these issues and to fee structure was solicited. Overall, there appeared to be a decline in university support for facilities and more emphasis on securing income by serving clients outside of the institution and by obtaining grants from entities outside of the university.

Joint Actinide Shock Physics Experimental Research (JASPER) Facility Update

International Nuclear Information System (INIS)

Conrad, C. H.; Miller, J.; Cowan, M.; Martinez, M.; Whitcomb, B.

2003-01-01

The JASPER Facility utilizes a Two-Stage Light Gas Gun to conduct equation-of-state(EOS) experiments on plutonium and other special nuclear materials. The overall facility will be discussed with emphasis on the Two-Stage Light Gas Gun characteristics and control interfaces and containment. The containment systems that were developed for this project will be presented

Experimental facilities for gas-cooled reactor safety studies. Task group on Advanced Reactor Experimental Facilities (TAREF)

International Nuclear Information System (INIS)

2009-01-01

In 2007, the NEA Committee on the Safety of Nuclear Installations (CSNI) completed a study on Nuclear Safety Research in OECD Countries: Support Facilities for Existing and Advanced Reactors (SFEAR) which focused on facilities suitable for current and advanced water reactor systems. In a subsequent collective opinion on the subject, the CSNI recommended to conduct a similar exercise for Generation IV reactor designs, aiming to develop a strategy for ' better preparing the CSNI to play a role in the planned extension of safety research beyond the needs set by current operating reactors'. In that context, the CSNI established the Task Group on Advanced Reactor Experimental Facilities (TAREF) in 2008 with the objective of providing an overview of facilities suitable for performing safety research relevant to gas-cooled reactors and sodium fast reactors. This report addresses gas-cooled reactors; a similar report covering sodium fast reactors is under preparation. The findings of the TAREF are expected to trigger internationally funded CSNI projects on relevant safety issues at the key facilities identified. Such CSNI-sponsored projects constitute a means for efficiently obtaining the necessary data through internationally co-ordinated research. This report provides an overview of experimental facilities that can be used to carry out nuclear safety research for gas-cooled reactors and identifies priorities for organizing international co-operative programmes at selected facilities. The information has been collected and analysed by a Task Group on Advanced Reactor Experimental Facilities (TAREF) as part of an ongoing initiative of the NEA Committee on the Safety of Nuclear Installations (CSNI) which aims to define and to implement a strategy for the efficient utilisation of facilities and resources for Generation IV reactor systems. (author)

Dark matter search in a Beam-Dump eXperiment (BDX) at Jefferson Lab: an update on PR12-16-001

Energy Technology Data Exchange (ETDEWEB)

Battaglieri, M. [Istituto Nazionale di Fisica Nucleare (INFN), Genova (Italy); et. al.

2017-12-07

This document is an update to the proposal PR12-16-001 Dark matter search in a Beam-Dump eXperiment (BDX) at Jefferson Lab submitted to JLab-PAC44 in 2016 reporting progress in addressing questions raised regarding the beam-on backgrounds. The concerns are addressed by adopting a new simulation tool, FLUKA, and planning measurements of muon fluxes from the dump with its existing shielding around the dump. First, we have implemented the detailed BDX experimental geometry into a FLUKA simulation, in consultation with experts from the JLab Radiation Control Group. The FLUKA simulation has been compared directly to our GEANT4 simulations and shown to agree in regions of validity. The FLUKA interaction package, with a tuned set of biasing weights, is naturally able to generate reliable particle distributions with very small probabilities and therefore predict rates at the detector location beyond the planned shielding around the beam dump. Second, we have developed a plan to conduct measurements of the muon ux from the Hall-A dump in its current configuration to validate our simulations.

The guidelines for the humanisation of care facilities

Directory of Open Access Journals (Sweden)

Daniela Bosia

2015-04-01

Full Text Available This article outlines the structure and contents of the guidelines for the humanisation of care facilities, which were produced from the research project The Humanisation of Healthcare Facilities: the new Dimension of Hospital Architecture conducted by the Tesis Inter-university Research Centre at the University of Florence and by the DINSE Department of the Politecnico di Torino for the Ministry of Health. The research work used a requirement-based approach that analysed the activities and requirements expressed by certain different users. For example, the guidelines on certain areas of the analysed healthcare facilities have been outlined.

Business administration of PET facilities. A cost analysis of three facilities utilizing delivery FDG

International Nuclear Information System (INIS)

Mitsutake, Naohiro; Oku, Shinya; Fujii, Ryo; Furui, Yuji; Yasunaga, Hideo

2008-01-01

PET (positron emission tomography) has been proved to be a powerful imaging tool in clinical oncology. The number of PET facilities in Japan has remarkably increased over the last decade. Furthermore, the approval of delivery fluorodeoxyglucose (FDG) in 2005 resulted in a tremendous expansion of the PET institutions without a cyclotron facility. The aim of this study was to conduct a cost analysis of PET institutions that utilized delivery FDG. Three PET facilities using delivery FDG were investigated about the costs for PET service. Fixed costs included depreciation costs for construction and medical equipments such as positron camera. Variable costs consisted of costs for medical materials including delivery FDG. The break-even point was analyzed in each of three institutions. In the three hospitals (A, B and C), the annual number of PET scan was 1,591, 1,637 and 914, while cost per scan was accounted as 110,262 yen, 111,091 yen, and 134,192 yen, respectively. The break-even point was calculated to be 2,583, 2,679 and 2,081, respectively. PET facilities utilizing delivery FDG seemed to have difficulty in business administration. Such a situation suggests the possibility that the current supply of PET facilities might exceed actual demand for the service. The efficiency of resource allocation should be taken into consideration in the future health service researches on PET. (author)

Present status of decommissioning in the Musashi Reactor Facility (4)

International Nuclear Information System (INIS)

Uchiyama, Takafumi; Tanzawa, Tomio; Mitsuhashi, Ishi; Morishima, Kayoko; Matsumoto, Tetsuo

2012-01-01

The decommissioning of the Musashi reactor was decided in 2003. Permanent shutdown of the reactor and stopping the operational functions were conducted in 2004. Transportation of the spent fuels was finished in 2006. After 2007, the system and equipment stopping the functions were stored as installed in the reactor facility as radioactive wastes. After separating nonradioactive wastes such as concretes from radioactive wastes with a contamination test, stopping the functions of liquid waste management facility was performed with newly installed drainage facility for radioisotope use in 2010. Solid waste management facility was also dismantled and removed in the same way as liquid waste management facility in 2011. Radioactive wastes packed in containers were moved and stored in the reactor facility. (T. Tanaka)

Atmospheric dispersion modeling of hazardous air pollutant emissions from USDOE Oak Ridge Reservation Facilities. Volume 1, Independent Assessment conducted from April 1994 to December 1994

International Nuclear Information System (INIS)

Humphreys, M.P.

1995-01-01

Title 3 of the 1990 Clean Air Act (CAA) Amendments addresses the emissions of 189 hazardous air pollutants (HAPs) and mandates that EPA develop technology-based [Maximum Achievable Control Technology (MACT)] standards for the control of these pollutants from approximately 174 source categories. After implementation of technology-based standards, EPA is required to further evaluate ''residual risk'' from HAP emissions, and, if required, develop more stringent standards to protect human health and the environment with an ''adequate margin of safety''. Recognizing that EPA will be issuing risk-based regulations after MACT standards have been implemented, the US Department of Energy (DOE), Oak Ridge Operations Office (ORO) has conducted an evaluation of ambient air impacts of HAP emissions from its installations located on the Oak Ridge Reservation (ORR) near Oak Ridge, Tennessee. This report provides results of atmospheric dispersion modeling conducted to determine ambient air impacts of HAP emissions from facilities located on the ORR

JLAB Hurricane recovery

International Nuclear Information System (INIS)

A. Hutton; D. Arenius; J. Benesch; S. Chattopadhyay; E. F. Daly; O. Garza; R. Kazimi; R. Lauzi; L. Merminga; W. Merz; R. Nelson; W. Oren; M. Poelker; P. Powers; J. Preble; V. Ganni; C. R. Reece; R. Rimmer; M. Spata; S. Suhring

2004-01-01

Hurricane Isabel, originally a Category 5 storm, arrived at Jefferson Lab on September 18, 2003 with winds of only 75 mph, creating little direct damage to the infrastructure. However, electric power was lost for four days allowing the superconducting cryomodules to warm up and causing a total loss of the liquid helium. The subsequent recovery of the cryomodules and the impact of the considerable amount of opportunistic preventive maintenance provides important lessons for all accelerator complexes, not only those with superconducting elements. The details of how the recovery process was structured and the resulting improvement in accelerator availability will be discussed in detail

Theoretical Issues in Strangeness Production

International Nuclear Information System (INIS)

Laget, Jean-Marc

2000-01-01

After pioneering works on hypernuclei, strangeness production mechanisms have been studied in hadron collisions and photoreactions in the sixties. Recent experiments at SATURNE and COSY, in the hadronic sector, as well as ELSA and JLab, in the electromagnetic sector, have confirmed our basic ideas on the reaction mechanisms. In the near future, strangeness production at JLab, HERMES and COMPASS may prove to be a powerful tool to study hadronic matter

Some aspects of linacs as applied to the ISL benchmark facility

International Nuclear Information System (INIS)

Shepard, K.W.

1992-01-01

This paper considers several aspects of using linacs in a radioactive beam facility in terms of the Isospin Laboratory (ISL) Benchmark Facility (BMF) plan, described in the 1991 white paper for a possible radioactive-beam laboratory. The intention is not to review comprehensively the application of linacs to an ISL facility, but to compare in outline form several linac options for such a facility. Particular emphasis is given to the use of superconducting rf technology for the secondary beam accelerator. In what follows, first a possible normally-conducting light-ion linac for a primary beam accelerator is briefly outlined. Then the performance and cost of two options for a secondary beam accelerator are compared: a recent design for a normal-conducting cw linac, and an ATLAS-type superconducting linac. Finally, some of the problems which may be encountered at the entrance of a secondary beam linac are discussed

CHALLENGES IN SETTING UP QUALITY CONTROL IN DIAGNOSTIC RADIOLOGY FACILITIES IN NIGERIA.

Science.gov (United States)

Inyang, S O; Egbe, N O; Ekpo, E

2015-01-01

The Nigerian Nuclear Regulatory Authority (NNRA) was established to regulate and control the use of radioactive and radiation emitting sources in Nigeria. Quality control (QC) on diagnostic radiology equipment form part of the fundamental requirements for the authorization of diagnostic radiology facilities in the Country. Some quality control tests (output, exposure linearity and reproducibility) were measured on the x-ray machines in the facilities that took part in the study. Questionnaire was developed to evaluate the frequencies at which QC tests were conducted in the facilities and the challenges in setting up QC. Results show great variation in the values of the QC parameters measured. Inadequate cooperation by facilities management, lack of QC equipment and insufficient staff form the major challenges in setting up QC in the facilities under study. The responses on the frequencies at which QC tests should be conducted did not correspond to the recommended standards; indicating that personnel were not familiar with QC implementation and may require further training on QC.

Environmental analysis of the operation of the ERDA facilities in Oak Ridge

International Nuclear Information System (INIS)

McWherter, J.R.

1975-01-01

An analysis of the environmental effects of current ERDA operations in Oak Ridge is being conducted to establish a baseline for the consideration of the environmental effects of additional facilities or modified operations in the future. An extensive ecological survey has been conducted for about one year; social and economic data were obtained; and an archaeological survey of the area was made. The facilities were described and the effluents associated with operations were quantified to the extent practical. The effects of effluent releases to the environment are being analyzed. The social effects of the ERDA facilities in Oak Ridge are also being studied. (auth)

Improvement of Oil-Vapor Treatment Facility for Wolsong Unit 3,4

International Nuclear Information System (INIS)

Kim, Jeong Guk; Kwon, S. W.; Lee, H. S.

2009-11-01

With the purpose to minimize an oil-vapor discharge to the atmosphere and to be an environmentally friendly nuclear power plant by an improvement of mist eliminator for turbine lubricant system at Wolsong Nuclear Power Plant Unit 3,4, this project - project name : Improvement of Oil-vapor Treatment Facility for Wolsong Unit 3,4 - was conducted for six months (from Apr. 15, 2009 to Oct. 14, 2009). This Project contains Oil-vapor Source and Environmental Regulation, Analysis on the Present Oil-vapor Treatment Facility, Improvement of Oil-vapor Treatment Facility, Test Facility Design, Fabrication, Installation, Test Operation, Evaluation of the Facility

Risk assessment of CST-7 proposed waste treatment and storage facilities Volume I: Limited-scope probabilistic risk assessment (PRA) of proposed CST-7 waste treatment & storage facilities. Volume II: Preliminary hazards analysis of proposed CST-7 waste storage & treatment facilities

Energy Technology Data Exchange (ETDEWEB)

Sasser, K.

1994-06-01

In FY 1993, the Los Alamos National Laboratory Waste Management Group [CST-7 (formerly EM-7)] requested the Probabilistic Risk and Hazards Analysis Group [TSA-11 (formerly N-6)] to conduct a study of the hazards associated with several CST-7 facilities. Among these facilities are the Hazardous Waste Treatment Facility (HWTF), the HWTF Drum Storage Building (DSB), and the Mixed Waste Receiving and Storage Facility (MWRSF), which are proposed for construction beginning in 1996. These facilities are needed to upgrade the Laboratory`s storage capability for hazardous and mixed wastes and to provide treatment capabilities for wastes in cases where offsite treatment is not available or desirable. These facilities will assist Los Alamos in complying with federal and state requlations.

Spin observables in charged pion photo-production from polarized neutrons in solid HD at Jefferson Lab

Energy Technology Data Exchange (ETDEWEB)

Kageya, Tsuneo [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Ho, Dao [Carnegie Mellon Univ., Pittsburgh, PA (United States); Peng, Peng [Univ. of Virginia, Charlottesville, VA (United States); Klein, Franz [George Washington Univ., Washington, DC (United States); Sandorfi, Andrew M. [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States); Schumacher, Reinhard A. [Carnegie Mellon Univ., Pittsburgh, PA (United States)

2018-04-01

E asymmetries have been extracted from double-polarizationexperiments in Hall-B of the Thomas Jefferson National Accelerator Facility (JLab). Results have been obtained from the E06-101 (g14) experiment, using circularly polarized photon beams, longitudinally polarized Deuterons in solid HD targets, and the CEBAF Large Acceptance Spectrometer (CLAS). The results cover a range inW from 1.48 to 2.32 GeV. Three independent analyses, using distinctly different methods, have been combined to obtain the final values, which have been published recently. Partial wave analyses (PWA), which have had to rely on a sparse neutron data base, havebeen significantly changed with the inclusion of these g14 asymmetries.

Profiles of facilities used for FBR research and testing

International Nuclear Information System (INIS)

1976-12-01

This document contains a concise up-to date of supporting ''Liquid Metal Fast Breeder'' facilities submitted by countries (Federal Republic of Germany, Italy, France, Belgium, Netherlands, UK, USA, USSR and Japan) and international organizations. It has the purpose of providing an over-view of the facilities currently used or under construction and of the type of experiments that can be conducted therein

Quality Assurance Project Plan for Facility Effluent Monitoring Plan activities

International Nuclear Information System (INIS)

Frazier, T.P.

1994-01-01

This Quality Assurance Project Plan addresses the quality assurance requirements for the activities associated with the Facility Effluent Monitoring Plans, which are part of the overall Hanford Site Environmental Protection Plan. This plan specifically applies to the sampling and analysis activities and continuous monitoring performed for all Facility Effluent Monitoring Plan activities conducted by Westinghouse Hanford Company. It is generic in approach and will be implemented in conjunction with the specific requirements of the individual Facility Effluent Monitoring Plans

Near-Facility Environmental Monitoring Quality Assurance Project Plan

International Nuclear Information System (INIS)

MCKINNEY, S.M.

2000-01-01

This Quality Assurance Project Plan addresses the quality assurance requirements for the activities associated with the preoperational and near-facility environmental monitoring directed by Waste Management Technical Services and supersedes HNF-EP-0538-4. This plan applies to all sampling and monitoring activities performed by Waste Management Technical Services in implementing near-facility environmental monitoring at the Hanford Site. This Quality Assurance Project Plan is required by U.S. Department of Energy Order 5400.1 (DOE 1990) as a part of the Environmental Monitoring Plan (DOE-RL 1997) and is used to define: Environmental measurement and sampling locations used to monitor environmental contaminants near active and inactive facilities and waste storage and disposal sites; Procedures and equipment needed to perform the measurement and sampling; Frequency and analyses required for each measurement and sampling location; Minimum detection level and accuracy; Quality assurance components; and Investigation levels. Near-facility environmental monitoring for the Hanford Site is conducted in accordance with the requirements of U.S. Department of Energy Orders 5400.1 (DOE 1990), 5400.5 (DOE 1993), 5484.1 (DOE 1990), and 435.1 (DOE 1999), and DOE/EH-O173T (DOE 1991). It is Waste Management Technical Services' objective to manage and conduct near-facility environmental monitoring activities at the Hanford Site in a cost-effective and environmentally responsible manner that is in compliance with the letter and spirit of these regulations and other environmental regulations, statutes, and standards

Industrial Energy Audit Guidebook: Guidelines for Conducting an Energy Audit in Industrial Facilities

Energy Technology Data Exchange (ETDEWEB)

Hasanbeigi, Ali; Price, Lynn

2010-10-07

Various studies in different countries have shown that significant energy-efficiency improvement opportunities exist in the industrial sector, many of which are cost-effective. These energy-efficiency options include both cross-cutting as well as sector-specific measures. However, industrial plants are not always aware of energy-efficiency improvement potentials. Conducting an energy audit is one of the first steps in identifying these potentials. Even so, many plants do not have the capacity to conduct an effective energy audit. In some countries, government policies and programs aim to assist industry to improve competitiveness through increased energy efficiency. However, usually only limited technical and financial resources for improving energy efficiency are available, especially for small and medium-sized enterprises. Information on energy auditing and practices should, therefore, be prepared and disseminated to industrial plants. This guidebook provides guidelines for energy auditors regarding the key elements for preparing for an energy audit, conducting an inventory and measuring energy use, analyzing energy bills, benchmarking, analyzing energy use patterns, identifying energy-efficiency opportunities, conducting cost-benefit analysis, preparing energy audit reports, and undertaking post-audit activities. The purpose of this guidebook is to assist energy auditors and engineers in the plant to conduct a well-structured and effective energy audit.

Re-analysis of hydraulic tests conducted for well 4A

International Nuclear Information System (INIS)

Swanson, L.C.

1994-01-01

During 1992, a series of hydrologic characterization tests were conducted at the well 4A -- 4T test facility complex. Details concerning these tests are described in Swanson (1992). Two of the tests, a constant-rate discharge test conducted on March 30, 1992 and a slug interference test performed on April 15, 1992, are the focus of this report

Quality standards for bone conduction implants.

Science.gov (United States)

Gavilan, Javier; Adunka, Oliver; Agrawal, Sumit; Atlas, Marcus; Baumgartner, Wolf-Dieter; Brill, Stefan; Bruce, Iain; Buchman, Craig; Caversaccio, Marco; De Bodt, Marc T; Dillon, Meg; Godey, Benoit; Green, Kevin; Gstoettner, Wolfgang; Hagen, Rudolf; Hagr, Abdulrahman; Han, Demin; Kameswaran, Mohan; Karltorp, Eva; Kompis, Martin; Kuzovkov, Vlad; Lassaletta, Luis; Li, Yongxin; Lorens, Artur; Martin, Jane; Manoj, Manikoth; Mertens, Griet; Mlynski, Robert; Mueller, Joachim; O'Driscoll, Martin; Parnes, Lorne; Pulibalathingal, Sasidharan; Radeloff, Andreas; Raine, Christopher H; Rajan, Gunesh; Rajeswaran, Ranjith; Schmutzhard, Joachim; Skarzynski, Henryk; Skarzynski, Piotr; Sprinzl, Georg; Staecker, Hinrich; Stephan, Kurt; Sugarova, Serafima; Tavora, Dayse; Usami, Shin-Ichi; Yanov, Yuri; Zernotti, Mario; Zorowka, Patrick; de Heyning, Paul Van

2015-01-01

Bone conduction implants are useful in patients with conductive and mixed hearing loss for whom conventional surgery or hearing aids are no longer an option. They may also be used in patients affected by single-sided deafness. To establish a consensus on the quality standards required for centers willing to create a bone conduction implant program. To ensure a consistently high level of service and to provide patients with the best possible solution the members of the HEARRING network have established a set of quality standards for bone conduction implants. These standards constitute a realistic minimum attainable by all implant clinics and should be employed alongside current best practice guidelines. Fifteen items are thoroughly analyzed. They include team structure, accommodation and clinical facilities, selection criteria, evaluation process, complete preoperative and surgical information, postoperative fitting and assessment, follow-up, device failure, clinical management, transfer of care and patient complaints.

Experiments on the Nuclear Interactions of Pions and Electrons

International Nuclear Information System (INIS)

Ralph C. Minehart

2005-01-01

This is the final technical report. Yearly Progress Reports were submitted throughout the duration of the project. Along with our publications, these reports provide a detailed record of our accomplishments. This report largely consists of a summary of the technical activities carried out during last 2-1/2 years of the project, along with a list of papers published in the period from 2002-2005. Our work during this period involved the following: 1. Electro-production of excited states of the nucleon through the analysis of exclusive single pion production reactions induced by polarized electrons incident on both polarized and unpolarized nucleon targets. (JLab) 2. Measurement of proton and deuteron spin structure functions in and above the nucleon resonance region at low and moderate Q 2 , using inclusive electron-proton and electron deuteron scattering (JLAB). 3. Contributions to the PRIMEX experiment (JLab). 4. A precise measurement of the branching ratio for pion beta decay was carried out along with other members of the PIBETA collaboration (PSI). The first three, labeled JLab, were experiments made with the CLAS detector at the Thomas Jefferson Laboratory in Newport News, VA. The PIBETA experiment was carried out using a low energy pion beam at the Paul Scherrer Institute in Villigen, Switzerland

Results of Cavity Series Fabrication at Jefferson Laboratory for the Cryomodule 'R100'

International Nuclear Information System (INIS)

Marhauser, F.; Clemens, W.A.; Drury, M.A.; Forehand, D.; Henry, J.; Manning, S.; Overton, R.B.; Williams, R.S.

2011-01-01

A series production of eight superconducting RF cavities for the cryomodule R100 was conducted at JLab in 2010. The cavities underwent chemical post-processing prior to vertical high power testing and routinely exceeded the envisaged performance specifications. After cryomodule assembly, cavities were successfully high power acceptance tested. In this paper, we present the achievements paving the way for the first demonstration of 100 MV (and beyond) in a single cryomodule to be operated at CEBAF.

Joint Actinide Shock Physics Experimental Research (JASPER) Facility Overview

International Nuclear Information System (INIS)

Konrad, C.H.; Braddy, R.W.; Martinez, Mark

2001-01-01

The JASPER Facility will utilize a Two-Stage Light Gas Gun to conduct equation-of-state (EOS) experiments of plutonium and other special nuclear materials. The overall facility will be discussed with emphasis on the Two-Stage Light Gas Gun characteristics and mission. The primary and secondary containment systems that were developed for this project will be presented. Primary gun diagnostics and timing will also be discussed

Experimental studies of generalized parton distributions

International Nuclear Information System (INIS)

Kabuss, E.M.

2014-01-01

Generalized parton distributions (GPD) provide a new way to study the nucleon structure. Experimentally they can be accessed using hard exclusive processes such as deeply virtual Compton scattering and meson production. First insights to GPDs were already obtained from measurements at DESY, JLAB and CERN, while new ambitious studies are planned at the upgraded JLAB at 12 GeV and at CERN. Here, some emphasis will be put onto the planned COMPASS II programme. (author)

Documented Safety Analysis for the Waste Storage Facilities

Energy Technology Data Exchange (ETDEWEB)

Laycak, D

2008-06-16

This documented safety analysis (DSA) for the Waste Storage Facilities was developed in accordance with 10 CFR 830, Subpart B, 'Safety Basis Requirements', and utilizes the methodology outlined in DOE-STD-3009-94, Change Notice 3. The Waste Storage Facilities consist of Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area portion of the DWTF complex. These two areas are combined into a single DSA, as their functions as storage for radioactive and hazardous waste are essentially identical. The B695 Segment of DWTF is addressed under a separate DSA. This DSA provides a description of the Waste Storage Facilities and the operations conducted therein; identification of hazards; analyses of the hazards, including inventories, bounding releases, consequences, and conclusions; and programmatic elements that describe the current capacity for safe operations. The mission of the Waste Storage Facilities is to safely handle, store, and treat hazardous waste, transuranic (TRU) waste, low-level waste (LLW), mixed waste, combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL (as well as small amounts from other DOE facilities).

Virtual laboratories: Collaborative environments and facilities-on-line

Energy Technology Data Exchange (ETDEWEB)

Thomas, C.E. Jr. [Oak Ridge National Lab., TN (United States). I and C Div.; Cavallini, J.S.; Seweryniak, G.R.; Kitchens, T.A.; Hitchcock, D.A.; Scott, M.A.; Welch, L.C. [Dept. of Energy, Germantown, MD (United States). Mathematical Information, and Computational Sciences Div.; Aiken, R.J. [Dept. of Energy, Germantown, MD (United States). Mathematical Information, and Computational Sciences Div.]|[Lawrence Livermore National Lab., CA (United States); Stevens, R.L. [Argonne National Lab., IL (United States). Mathematics and Computer Sciences Div.

1995-07-01

The Department of Energy (DOE) has major research laboratories in a number of locations in the US, typically co-located with large research instruments or research facilities valued at tens of millions to even billions of dollars. Present budget exigencies facing the entire nation are felt very deeply at DOE, just as elsewhere. Advances over the last few years in networking and computing technologies make virtual collaborative environments and conduct of experiments over the internetwork structure a possibility. The authors believe that development of these collaborative environments and facilities-on-line could lead to a ``virtual laboratory`` with tremendous potential for decreasing the costs of research and increasing the productivity of their capital investment in research facilities. The majority of these cost savings would be due to increased productivity of their research efforts, better utilization of resources and facilities, and avoiding duplication of expensive facilities. A vision of how this might all fit together and a discussion of the infrastructure necessary to enable these developments is presented.

Risk assessment of CST-7 proposed waste treatment and storage facilities Volume I: Limited-scope probabilistic risk assessment (PRA) of proposed CST-7 waste treatment ampersand storage facilities. Volume II: Preliminary hazards analysis of proposed CST-7 waste storage ampersand treatment facilities

International Nuclear Information System (INIS)

Sasser, K.

1994-06-01

In FY 1993, the Los Alamos National Laboratory Waste Management Group [CST-7 (formerly EM-7)] requested the Probabilistic Risk and Hazards Analysis Group [TSA-11 (formerly N-6)] to conduct a study of the hazards associated with several CST-7 facilities. Among these facilities are the Hazardous Waste Treatment Facility (HWTF), the HWTF Drum Storage Building (DSB), and the Mixed Waste Receiving and Storage Facility (MWRSF), which are proposed for construction beginning in 1996. These facilities are needed to upgrade the Laboratory's storage capability for hazardous and mixed wastes and to provide treatment capabilities for wastes in cases where offsite treatment is not available or desirable. These facilities will assist Los Alamos in complying with federal and state requlations

Highly Conductive Cu 2– x S Nanoparticle Films through Room-Temperature Processing and an Order of Magnitude Enhancement of Conductivity via Electrophoretic Deposition

KAUST Repository

Otelaja, Obafemi O.; Ha, Don-Hyung; Ly, Tiffany; Zhang, Haitao; Robinson, Richard D.

2014-01-01

© 2014 American Chemical Society. A facile room-temperature method for assembling colloidal copper sulfide (Cu2-xS) nanoparticles into highly electrically conducting films is presented. Ammonium sulfide is utilized for connecting the nanoparticles

Quality Assurance Project Plan for Facility Effluent Monitoring Plan activities

International Nuclear Information System (INIS)

Nickels, J.M.

1991-06-01

This Quality Assurance Project Plan addresses the quality assurance requirements for the Facility Monitoring Plans of the overall site-wide environmental monitoring plan. This plan specifically applies to the sampling and analysis activities and continuous monitoring performed for all Facility Effluent Monitoring Plan activities conducted by Westinghouse Hanford Company. It is generic in approach and will be implemented in conjunction with the specific requirements of individual Facility Effluent Monitoring Plans. This document is intended to be a basic road map to the Facility Effluent Monitoring Plan documents (i.e., the guidance document for preparing Facility Effluent Monitoring Plans, Facility Effluent Monitoring Plan determinations, management plan, and Facility Effluent Monitoring Plans). The implementing procedures, plans, and instructions are appropriate for the control of effluent monitoring plans requiring compliance with US Department of Energy, US Environmental Protection Agency, state, and local requirements. This Quality Assurance Project Plan contains a matrix of organizational responsibilities, procedural resources from facility or site manuals used in the Facility Effluent Monitoring Plans, and a list of the analytes of interest and analytical methods for each facility preparing a Facility Effluent Monitoring Plan. 44 refs., 1 figs., 2 tabs

WASH and gender in health care facilities: The uncharted territory.

Science.gov (United States)

Kohler, Petra; Renggli, Samuel; Lüthi, Christoph

2017-11-08

Health care facilities in low- and middle-income countries are high-risk settings, and face special challenges to achieving sustainable water, sanitation, and hygiene (WASH) services. Our applied interdisciplinary research conducted in India and Uganda analyzed six dimensions of WASH services in selected health care facilities, including menstrual hygiene management. To be effective, WASH monitoring strategies in health care facilities must include gender sensitive measures. We present a novel strategy, showing that applied gender sensitive multitool assessments are highly productive in assessments of WASH services and facilities from user and provider perspectives. We discuss its potential for applications at scale and as an area of future research.

OXYGEN TRANSFER STUDIES AT THE MADISON METROPOLITAN SEWERAGE DISTRICT FACILITIES

Science.gov (United States)

Field studies at the Madison Metropolitan Sewerage District facilities were conducted over a 3-year period to obtain long-term data on the performance of fine pore aeration equipment in municipal wastewater. The studies were conducted on several basins in the East Plant containi...

A novel injection-locked amplitude-modulated magnetron at 1497 MHz

Energy Technology Data Exchange (ETDEWEB)

Neubauer, Michael [Muons Inc., Batavia, IL (United States); Wang, Haipeng [Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States)

2015-12-15

Thomas Jefferson National Accelerator Facility (JLab) uses low efficiency klystrons in the CEBAF machine. In the older portion they operate at 30% efficiency with a tube mean time between failure (MTBF) of five to six years. A highly efficient source (>55-60%) must provide a high degree of backwards compatibility, both in size and voltage requirements, to replace the klystron presently used at JLab, while providing energy savings. Muons, Inc. is developing a highly reliable, highly efficient RF source based upon a novel injection-locked amplitude modulated (AM) magnetron with a lower total cost of ownership, >80% efficiency, and MTBF of six to seven years. The design of the RF source is based upon a single injection-locked magnetron system at 8 kW capable of operating up to 13 kW, using the magnetron magnetic field to achieve the AM required for backwards compatibility to compensate for microphonics and beam loads. A novel injection-locked 1497 MHz 8 kW AM magnetron with a trim magnetic coil was designed and its operation numerically simulated during the Phase I project. The low-level RF system to control the trim field and magnetron anode voltage was designed and modeled for operation at the modulation frequencies of the microphonics. A plan for constructing a prototype magnetron and control system was developed.

The Australian National Proton Facility

International Nuclear Information System (INIS)

Jackson, M.; Rozenfeld, A.; Bishop, J.

2002-01-01

Full text: Protons have been used in the treatment of cancer since 1954 and over 30,000 patients have been treated around the world. Their precise dose distribution allows the treatment of small tumours in critical locations such as the base of skull and orbit and is an alternative to stereotactic radiotherapy in other sites. With the development of hospital-based systems in the 1990's, common tumours such as prostate, breast and lung cancer can now also be treated using simple techniques. The therapeutic ratio is improved as the dose to the tumour can be increased while sparing normal tissues. The well defined high dose region and low integral dose compared with photon treatments is a particular advantage in children and other situations where long-term survival is expected and when used in combination with chemotherapy. In January 2002, the NSW Health Department initiated a Feasibility Study for an Australian National Proton Facility. This Study will address the complex medical, scientific, engineering, commercial and legal issues required to design and build a proton facility in Australia. The Facility will be mainly designed for patient treatment but will also provide facilities for biological, physical and engineering research. The proposed facility will have a combination of fixed and rotating beams with an energy range of 70-250 MeV. Such a centre will enable the conduct of randomised clinical trials and a comparison with other radiotherapy techniques such as Intensity Modulated Radiation Therapy. Cost-utility comparisons with other medical treatments will also be made and further facilities developed if the expected benefit is confirmed. When patients are not being treated, the beam will be available for commercial and research purposes. This presentation will summarize the progress of the Study and discuss the important issues that need to be resolved before the Facility is approved and constructed

303-K Storage Facility closure plan

International Nuclear Information System (INIS)

1993-01-01

Recyclable scrap uranium with zircaloy-2 and copper silicon alloy, uranium-titanium alloy, beryllium/zircaloy-2 alloy, and zircaloy-2 chips and fines were secured in concrete billets (7.5-gallon containers) in the 303-K Storage Facility, located in the 300 Area. The beryllium/zircaloy-2 alloy and zircaloy-2 chips and fines are designated as mixed waste with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 303-K Storage Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act (RCRA) of 1976 and the Washington Administrative Code (WAC) Dangerous Waste Regulations, WAC 173-303-040. This closure plan presents a description of the 303-K Storage Facility, the history of materials and waste managed, and the procedures that will be followed to close the 303-K Storage Facility. The 303-K Storage Facility is located within the 300-FF-3 (source) and 300-FF-5 (groundwater) operable units, as designated in the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1992). Contamination in the operable units 300-FF-3 and 300-FF-5 is scheduled to be addressed through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 remedial action process. Therefore, all soil remedial action at the 304 Facility will be conducted as part of the CERCLA remedial action of operable units 300-FF-3 and 300-FF-5

A green and facile hydrothermal approach for the synthesis of high-quality semi-conducting Sb{sub 2}S{sub 3} thin films

Energy Technology Data Exchange (ETDEWEB)

Liu, Meng; Gong, Yongshuai; Li, Zhilin; Dou, Meiling, E-mail: douml@mail.buct.edu.cn; Wang, Feng, E-mail: wangf@mail.buct.edu.cn

2016-11-30

Highlights: • A green and facile hydrothermal approach for Sb{sub 2}S{sub 3} films was developed. • The film possessed a relatively ideal S/Sb atomic ratio and a compact surface. • The grain size of Sb{sub 2}S{sub 3} was increased by high temperature annealing. • The film annealed at 450 °C showed the improved optical and electrical performance. - Abstract: High-quality semi-conducting antimony sulfide (Sb{sub 2}S{sub 3}) thin films were directly deposited on the indium tin oxide (ITO) substrates by a green and facile one-step approach based on a hydrothermal reaction and post-annealing process without any assistance of complexing agents. The obtained Sb{sub 2}S{sub 3} films possessed a relatively ideal S/Sb atomic ratio and a compact and continuous surface as the grain size of Sb{sub 2}S{sub 3} was increased by high temperature annealing. The Sb{sub 2}S{sub 3} film annealed at 450 °C exhibited the improved optical and electrical performances, with a narrow band gap of 1.63 eV, an electrical resistivity of 1.3 × 10{sup 4} Ω cm, a carrier concentration of 7.3 × 10{sup 13} cm{sup −3} and a carrier mobility of 6.4 cm{sup 2} V{sup −1} s{sup −1}. This environmentally friendly synthetic route is promising for the preparation of high-quality Sb{sub 2}S{sub 3} films to be used as absorber layer materials for high-performance solar cells.

Evaluation verification facilities (EVF) at MINT: concept and implementation

International Nuclear Information System (INIS)

Mohamed Hairul Hasmoni; Abd Nassir Ibrahim; Ab Razak Hamzah

2003-01-01

EVF facilities and components available are described comprehensively. Objective of establishing EVF as a National Centre for non-destructive testing (NDT) are discussed for various activities of method and equipment validation, R and D on quantitative NDT technique, training and certification, and defect characterization. For a successful activity available at EVF, it is vital that industry participates through input of funding, sponsorship and knowledge sharing. The Malaysian Institute for Nuclear Technology Research (MINT) invested a lot in this facility and ready to share this facility under various mechanisms such as memorandum of understanding (MOU), memorandum of agreement (MOA), contract research or letter of agreement. The facility would be open to industry. Member of NDT community are welcomed to conduct trial and discuss particular areas of interest with others in the industry. Optimising the facility by utilising the facility available and adding new components would make EVF a national centre for NDT and centre of excellence. This paper reviews the concept and implementation of an Evaluation Verification Facility (EVF) at MINT. The types and designs of facilities available are described and characterised by usage NDT. (Author)

Detecting Development Pattern of Urban Business Facilities Using Reviews Data

Directory of Open Access Journals (Sweden)

JIANG Botao

2015-09-01

Full Text Available This paper reveals and utilizes the growing power of online customer reviews in the space and time context. The location of commercial facilities and online customer reviews offered by Dianping.com provide an important data source for the study of spatial and temporal dynamics of urban commercial facilities. The constraints of road network are taken into account towards computing the density of urban commercial facilities and associated online customer reviews, as well as their spatial distribution, temporal trend, and the coupling relationship between facility number and stratification level. This paper maps the spatial distribution of commercial facilities onto the nearby road network, reflecting the influences of the locations, number and satisfaction levels of other commercial facilities across various street types. Because more and more customers tend to make a final shopping decision by sorting through search results by ratings and feedback, the research conducted in this paper can provide the proof for quantitative evaluation of urban planning on commercial facility development.

Technological Advances, Human Performance, and the Operation of Nuclear Facilities

Science.gov (United States)

Corrado, Jonathan K.

Many unfortunate and unintended adverse industrial incidents occur across the United States each year, and the nuclear industry is no exception. Depending on their severity, these incidents can be problematic for people, the facilities, and surrounding environments. Human error is a contributing factor in many such incidents. This dissertation first explored the hypothesis that technological changes that affect how operators interact within the systems of the nuclear facilities exacerbate the cost of incidents caused by human error. I conducted a review of nuclear incidents in the United States from 1955 through 2010 that reached Level 3 (serious incident) or higher on the International Nuclear Events Scale (INES). The cost of each incident at facilities that had recently undergone technological changes affecting plant operators' jobs was compared to the cost of events at facilities that had not undergone changes. A t-test determined a statistically significant difference between the two groups, confirming the hypothesis. Next, I conducted a follow-on study to determine the impact of the incorporation of new technologies into nuclear facilities. The data indicated that spending more money on upgrades increased the facility's capacity as well as the number of incidents reported, but the incident severity was minor. Finally, I discuss the impact of human error on plant operations and the impact of evolving technology on the 21st-century operator, proposing a methodology to overcome these challenges by applying the systems engineering process.

Regulatory Guide on Conducting a Security Vulnerability Assessment

Energy Technology Data Exchange (ETDEWEB)

Ek, David R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2016-01-01

This document will provide guidelines on conducting a security vulnerability assessment at a facility regulated by the Radiation Protection Centre. The guidelines provide a performance approach assess security effectiveness. The guidelines provide guidance for a review following the objectives outlined in IAEA NSS#11 for Category 1, 2, & 3 sources.

Emission Facilities - Erosion & Sediment Control Facilities

Data.gov (United States)

NSGIC Education | GIS Inventory — An Erosion and Sediment Control Facility is a DEP primary facility type related to the Water Pollution Control program. The following sub-facility types related to...

Modified conductivity of polymer materials with proton beam

International Nuclear Information System (INIS)

Matsumoto, Shinji; Seki, Miharu; Shima, Kunihiro; Ishihara, Toyoyuki

2001-01-01

Ionic conductivity of polymer materials is of increasing interest in many scientific fields. Industrial applications seem to be promising. In the present investigation, we used proton bombardment to modify the characteristic properties of polymers, especially for improvement in conductivity and hardening gel polymers. Particle beam bombardment is known to produce many scissions by particle passages and new bonds by bridge connection. These effects may modify various properties in many ways. We examined the modification of conductivity in solid polymers composed of polyethylene oxide and polyurethane and the surface appearance of gel polymers with bombardment by a proton beam using the accelerator facility of Tsukuba University. The results indicated proton bombardment induced conductivity changes in various ways according to particle range and polymer properties. (author)

Personnel neutron dosimetry at Department of Energy facilities

International Nuclear Information System (INIS)

Brackenbush, L.W.; Endres, G.W.R.; Selby, J.M.; Vallario, E.J.

1980-08-01

This study assesses the state of personnel neutron dosimetry at DOE facilities. A survey of the personnel dosimetry systems in use at major DOE facilities was conducted, a literature search was made to determine recent advances in neutron dosimetry, and several dosimetry experts were interviewed. It was concluded that personnel neutron dosimeters do not meet current needs and that serious problems exist now and will increase in the future if neutron quality factors are increased and/or dose limits are lowered

Safety assessment for radioactive waste disposal facility

International Nuclear Information System (INIS)

Thanaletchumy Karuppiah; Mohd Abdul Wahab Yusof; Nik Marzuki Nik Ibrahim; Nurul Wahida Ahmad Khairuddin

2008-08-01

Safety assessments are used to evaluate the performance of a radioactive waste disposal facility and its impact on human health and the environment. This paper presents the overall information and methodology to carry out the safety assessment for a long term performance of a disposal system. A case study was also conducted to gain hands-on experience in the development and justification of scenarios, the formulation and implementation of models and the analysis of results. AMBER code using compartmental modeling approach was used to represent the migration and fate of contaminants in this training. This safety assessment is purely illustrative and it serves as a starting point for each development stage of a disposal facility. This assessment ultimately becomes more detail and specific as the facility evolves. (Author)

Facilities Performance Indicators Report, 2006-07

Science.gov (United States)

Glazner, Steve, Ed.

2008-01-01

The "Facilities Performance Indicators Survey" ("FPI") supersedes and builds upon the two major surveys APPA conducted in the past: the Comparative Costs and Staffing (CCAS) survey and the Strategic Assessment Model (SAM). The "FPI" covers all the materials collected in CCAS and SAM, along with some select new data points and improved survey…

Site Selection for Surplus Plutonium Disposition Facilities at the Savannah River Site

International Nuclear Information System (INIS)

Wike, L.D.

2000-01-01

A site selection study was conducted to evaluate locations for the proposed Surplus Plutonium Disposition Facilities. Facilities to be located include the Mixed Oxide (MOX) Fuel Fabrication Facility, the Pit Disassembly and Conversion Facility (PDCF), and the Plutonium Immobilization Project (PIP) facility. Objectives of the study include: (1) Confirm that the Department of Energy (DOE) selected locations for the MOX and PDCF were suitable based on selected siting criteria, (2) Recommend a site in the vicinity of F Area that is suitable for the PIP, and (3) Identify alternative suitable sites for one or more of these facilities in the event that further geotechnical characterization or other considerations result in disqualification of a currently proposed site

Ground test facility for nuclear testing of space reactor subsystems

International Nuclear Information System (INIS)

Quapp, W.J.; Watts, K.D.

1985-01-01

Two major reactor facilities at the INEL have been identified as easily adaptable for supporting the nuclear testing of the SP-100 reactor subsystem. They are the Engineering Test Reactor (ETR) and the Loss of Fluid Test Reactor (LOFT). In addition, there are machine shops, analytical laboratories, hot cells, and the supporting services (fire protection, safety, security, medical, waste management, etc.) necessary to conducting a nuclear test program. This paper presents the conceptual approach for modifying these reactor facilities for the ground engineering test facility for the SP-100 nuclear subsystem. 4 figs

Characterization of Iraq's remote nuclear facilities for decommissioning and waste management - 59167

International Nuclear Information System (INIS)

Al-Musawi, Fouad; Jarjies, Adnan; Miller, Ross A.

2012-01-01

The Government of Iraq (GOI) has undertaken efforts to decommission and dismantle former nuclear facilities. The GOI has only preliminary information on some of the former nuclear facilities. This paper will highlight the challenges involved in conducting inspections of the outlying former nuclear facilities in Iraq and present a brief summary of the results of those inspections. The facilities discussed in this paper are located at various sites throughout Iraq, from locations close to Baghdad to those in the north and far western desert areas. Some of the facilities, such as those at the Al Tuwaitha Nuclear Research Center have been visited and characterized. Other facilities, including the following, have not been visited or thoroughly characterized. - Al Jesira, Uranium feed stock production facility; - Adaya, Burial location for contaminated equipment; - Djerf al Naddah, Spent fuel storage facility; - Rashdiya, Centrifuge development center; - Al Qa'im, Uranium (yellowcake) production facility. The visits were conducted to develop an inventory of the buildings/structures that need to be included in decommissioning/dismantlement efforts. The number of buildings, type of construction, size and general condition of the buildings were noted. In addition, attempts were made to determine contamination levels on surfaces, equipment, rubble, etc. This information will be used to support the Iraqi decommissioning and dismantlement project. Because the facilities are scattered throughout the country of Iraq, significant planning and coordination was required to ensure personnel security. Teams consisting of individuals from the Iraqi Ministry of Science and Technology (MoST) and Americans were under military escort when traveling to and visiting the sites. Because of the security issues, time on the ground at each site was limited. This paper will highlight the challenges involved in conducting the inspections of the outlying former nuclear facilities In Iraq and

Sanford Underground Research Facility - The United State's Deep Underground Research Facility

Science.gov (United States)

Vardiman, D.

2012-12-01

/LIDAR), surveying instruments, and surveying benchmarks and optical survey points. Currently an array of single and multipoint extensometers monitors the Davis Campus. A facility-wide micro seismic monitoring system is anticipated to be deployed during the latter half of 2012. This system is designed to monitor minor events initiated within the historical mined out portions of the facility. The major science programs for the coming five years consist of the MAJORANA DEMONSTRATOR (MJD) neutrinoless double beta decay experiment; the Large Underground Xenon (LUX) dark matter search, the Center for Ultralow Background Experiments at DUSEL (CUBED), numerous geoscience installations, Long-Baseline Neutrino Experiment (LBNE), a nuclear astrophysics program involving a low energy underground particle accelerator, second and third generation dark matter experiments, and additional low background counting facilities. The Sanford Lab facility is an active, U.S. based, deep underground research facility dedicated to science, affording the science community the opportunity to conduct unprecedented scientific research in a broad range of physics, biology and geoscience fields at depth. SURF is actively interested in hosting additional research collaborations and provides resources for full facility design, cost estimation, excavation, construction and support management services.

3718-F Alkali Metal Treatment and Storage Facility Closure Plan

International Nuclear Information System (INIS)

1992-11-01

The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, as well as for activities associated with nuclear energy development. The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. The 3718-F Alkali Metal Treatment and Storage Facility (3718-F Facility), located in the 300 Area, was used to store and treat alkali metal wastes. Therefore, it is subject to the regulatory requirements for the storage and treatment of dangerous wastes. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610 (Ecology 1989) and 40 CFR 270.1. Closure also will satisfy the thermal treatment facility closure requirements of 40 CFR 265.381. This closure plan presents a description of the 3718-F Facility, the history of wastes managed, and the approach that will be followed to close the facility. Only hazardous constituents derived from 3718-F Facility operations will be addressed

Race, wealth, and solid waste facilities in North Carolina.

Science.gov (United States)

Norton, Jennifer M; Wing, Steve; Lipscomb, Hester J; Kaufman, Jay S; Marshall, Stephen W; Cravey, Altha J

2007-09-01

Concern has been expressed in North Carolina that solid waste facilities may be disproportionately located in poor communities and in communities of color, that this represents an environmental injustice, and that solid waste facilities negatively impact the health of host communities. Our goal in this study was to conduct a statewide analysis of the location of solid waste facilities in relation to community race and wealth. We used census block groups to obtain racial and economic characteristics, and information on solid waste facilities was abstracted from solid waste facility permit records. We used logistic regression to compute prevalence odds ratios for 2003, and Cox regression to compute hazard ratios of facilities issued permits between 1990 and 2003. The adjusted prevalence odds of a solid waste facility was 2.8 times greater in block groups with > or = 50% people of color compared with block groups with or = 100,000 dollars. Among block groups that did not have a previously permitted solid waste facility, the adjusted hazard of a new permitted facility was 2.7 times higher in block groups with > or = 50% people of color compared with block groups with waste facilities present numerous public health concerns. In North Carolina solid waste facilities are disproportionately located in communities of color and low wealth. In the absence of action to promote environmental justice, the continued need for new facilities could exacerbate this environmental injustice.

Conducting polymer nanostructures: template synthesis and applications in energy storage.

Science.gov (United States)

Pan, Lijia; Qiu, Hao; Dou, Chunmeng; Li, Yun; Pu, Lin; Xu, Jianbin; Shi, Yi

2010-07-02

Conducting polymer nanostructures have received increasing attention in both fundamental research and various application fields in recent decades. Compared with bulk conducting polymers, conducting polymer nanostructures are expected to display improved performance in energy storage because of the unique properties arising from their nanoscaled size: high electrical conductivity, large surface area, short path lengths for the transport of ions, and high electrochemical activity. Template methods are emerging for a sort of facile, efficient, and highly controllable synthesis of conducting polymer nanostructures. This paper reviews template synthesis routes for conducting polymer nanostructures, including soft and hard template methods, as well as its mechanisms. The application of conducting polymer mesostructures in energy storage devices, such as supercapacitors and rechargeable batteries, are discussed.

Conducting Polymer Nanostructures: Template Synthesis and Applications in Energy Storage

Directory of Open Access Journals (Sweden)

Lijia Pan

2010-07-01

Full Text Available Conducting polymer nanostructures have received increasing attention in both fundamental research and various application fields in recent decades. Compared with bulk conducting polymers, conducting polymer nanostructures are expected to display improved performance in energy storage because of the unique properties arising from their nanoscaled size: high electrical conductivity, large surface area, short path lengths for the transport of ions, and high electrochemical activity. Template methods are emerging for a sort of facile, efficient, and highly controllable synthesis of conducting polymer nanostructures. This paper reviews template synthesis routes for conducting polymer nanostructures, including soft and hard template methods, as well as its mechanisms. The application of conducting polymer mesostructures in energy storage devices, such as supercapacitors and rechargeable batteries, are discussed.

Educational Facility Evaluations of Primary Schools in Rural Honduras: Departments of Cortes and Meambar.

Science.gov (United States)

Council of Educational Facility Planners, International, Scottsdale, AZ.

A team of 11 educational facility planners and architects from the United States and Canada conducted a facility evaluation of schools in the rural areas of Meambar and Cortes, Honduras. Team members were all part of the Council of Educational Facility Planners, International and traveled to Honduras under the auspices of a Christian mission…

Performance objectives and criteria for conducting DOE environmental audits

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-01-01

This document contains the Performance Objectives and Criteria (POC) that have been developed for environmental audits and assessments conducted by the Office of the Assistant Secretary for Environment, Safety and Health. The Environmental POC can serve multiple purposes. Primarily, they are to serve as guidelines for the technical specialists conducted the audits and assessments, and for the team management. The POC can also serve as supporting documents for training of technical discipline specialists and Team Leaders and as bases for DOE programs and field offices and contractors conducting audit or assessment activities or improving environmental protection programs. It must be recognized that not all of the POC will necessarily apply to all DOE facilities. The users of this document must rely upon their knowledge of the facility and their professional judgment, or the judgment of qualified environmental professionals to determine the applicability of each POC. The POC cover eleven technical disciplines: air; surface water and drinking water quality; groundwater; waste management; toxic and chemical materials; radiation; quality assurance; inactive waste sites and releases; ecological and cultural resources; the National Environmental Policy Act (NEPA); and environmental management systems.

Performance objectives and criteria for conducting DOE environmental audits

International Nuclear Information System (INIS)

1994-01-01

This document contains the Performance Objectives and Criteria (POC) that have been developed for environmental audits and assessments conducted by the Office of the Assistant Secretary for Environment, Safety and Health. The Environmental POC can serve multiple purposes. Primarily, they are to serve as guidelines for the technical specialists conducted the audits and assessments, and for the team management. The POC can also serve as supporting documents for training of technical discipline specialists and Team Leaders and as bases for DOE programs and field offices and contractors conducting audit or assessment activities or improving environmental protection programs. It must be recognized that not all of the POC will necessarily apply to all DOE facilities. The users of this document must rely upon their knowledge of the facility and their professional judgment, or the judgment of qualified environmental professionals to determine the applicability of each POC. The POC cover eleven technical disciplines: air; surface water and drinking water quality; groundwater; waste management; toxic and chemical materials; radiation; quality assurance; inactive waste sites and releases; ecological and cultural resources; the National Environmental Policy Act (NEPA); and environmental management systems

Initial measurement of site boundary neutron dose and comparison with calculations

International Nuclear Information System (INIS)

Degtyarenko, P.; Dotson, D.; May, R.; Schwahn, S.; Stapleton, G.

1996-01-01

For most accelerators adequate side shielding can be provided at minimal cost to meet the most aggressive radiation protection regulations and, further, the likely requirement to increase shielding thickness still more at a later date can be done usually by heaping more earth or applying local shielding at minimal expense and inconvenience. This moderately happy state of affairs does not unfortunately hold true with roof shielding. The cost of roof shielding is largely predicated on the roof span and the necessary structural engineering requirements for its support. These measures can be extremely expensive and where one is dealing with the rather extensive unsupported spans typical of experimental halls devoted to experiments with high energy electron beams; it is necessary to specify the roof thickness as carefully as possible with the constant concern that adding more earth later is not likely to be possible without rebuilding the hall. Because of the nature of roof skyshine, and for most high energy accelerator facilities neutron skyshine, the effect of the radiation is likely to extend to the facility fence-line where one is concerned about the exposure of the general population. Very properly the dose limit for the general population is set at a rather low value (1 mSv y -1 ) and in order for the Jefferson Lab (JLab) to ensure strict compliance with this limit they have a design goal for the fence line of 0.1 mSv y -1 . However, because natural neutron backgrounds are low (30--40 microSv y -1 ) and the methods of detection and measurement permit rejection of background interference from photons, they can measure the JLab produced neutron radiation with good sensitivity and precision

Facility Decontamination and Decommissioning Program Surveillance and Maintenance Plan, Revision 2

Energy Technology Data Exchange (ETDEWEB)

Poderis, Reed J. [NSTec; King, Rebecca A. [NSTec

2013-09-30

This Surveillance and Maintenance (S&M) Plan describes the activities performed between deactivation and final decommissioning of the following facilities located on the Nevada National Security Site, as documented in the Federal Facility Agreement and Consent Order under the Industrial Sites program as decontamination and decommissioning sites: ? Engine Maintenance, Assembly, and Disassembly (EMAD) Facility: o EMAD Building (Building 25-3900) o Locomotive Storage Shed (Building 25-3901) ? Test Cell C (TCC) Facility: o Equipment Building (Building 25-3220) o Motor Drive Building (Building 25-3230) o Pump Shop (Building 25-3231) o Cryogenic Lab (Building 25-3232) o Ancillary Structures (e.g., dewars, water tower, piping, tanks) These facilities have been declared excess and are in various stages of deactivation (low-risk, long-term stewardship disposition state). This S&M Plan establishes and implements a solid, cost-effective, and balanced S&M program consistent with federal, state, and regulatory requirements. A graded approach is used to plan and conduct S&M activities. The goal is to maintain the facilities in a safe condition in a cost-effective manner until their final end state is achieved. This plan accomplishes the following: ? Establishes S&M objectives and framework ? Identifies programmatic guidance for S&M activities to be conducted by National Security Technologies, LLC, for the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) ? Provides present facility condition information and identifies hazards ? Identifies facility-specific S&M activities to be performed and their frequency ? Identifies regulatory drivers, NNSA/NFO policies and procedures, and best management practices that necessitate implementation of S&M activities ? Provides criteria and frequencies for revisions and updates ? Establishes the process for identifying and dispositioning a condition that has not been previously identified or

A facile approach to a silver conductive ink with high performance for macroelectronics

Science.gov (United States)

Tao, Yu; Tao, Yuxiao; Wang, Biaobing; Wang, Liuyang; Tai, Yanlong

2013-06-01

An unusual kind of transparent and high-efficiency organic silver conductive ink (OSC ink) was synthesized with silver acetate as silver carrier, ethanolamine as additive, and different kinds of aldehyde-based materials as reduction agents and was characterized by using a thermogravimetric analyzer, X-ray diffraction, a scanning electron microscope, and a four-point probe. The results show that different reduction agents all have an important influence on the conductive properties of the ink through a series of complex chemical reactions, and especially when formic acid or dimethylformamide was used as the reduction agent and sintered at 120°C for 30 s, the resistivity can be lowered to 6 to 9 μΩ·cm. Furthermore, formula mechanism, conductive properties, temperature, and dynamic fatigue properties were investigated systematically, and the feasibility of the OSC ink was also verified through the preparation of an antenna pattern.

The magnetohydrodynamics Coal-Fired Flow Facility

Energy Technology Data Exchange (ETDEWEB)

1991-07-01

In this quarterly technical progress report, UTSI summarizes the results of a multi-task research and development project directed toward the development of the technology for the commercialization of the steam bottoming plant for the MHD steam combined cycle power plant. The report covers the final test in a 2000-hour proof-of-concept (POC) test series on eastern coal, the plans and progress for the facility modifications and the conduct of the POC tests to be conducted with western coal. Results summarized in the report include chloride emissions from the particle removal (ESP/BH) processes, nitrogen and sulfur oxide emissions for various tests conditions, measurements of particulate control efficiency and management of the facility holding ponds during testing. Activities relating to corrosion and deposition probe measurements during testing and the fouling of heat transfer tubes and interaction with sootblowing cycles are summarized. The performance of both UTSI and Mississippi State University (MSU) advanced diagnostic systems is reported. Significant administrative and contractual actions are included. 2 refs., 28 figs., 7 tabs.

Federal facilities compliance act waste management

International Nuclear Information System (INIS)

Bowers, J.; Gates-Anderson, D.; Hollister, R.; Painter, S.

1999-01-01

Site Treatment Plans (STPs) developed through the Federal Facilities Compliance Act pose many technical and administrative challenges. Legacy wastes managed under these plans require Land Disposal Restriction (LDR) compliance through treatment and ultimate disposal. Although capacity has been defined for most of the Department of Energy wastes, many waste streams require further characterization and many need additional treatment and handling beyond LDR criteria to be able to dispose of the waste. At Lawrence Livermore National Laboratory (LLNL), the Hazardous Waste Management Division has developed a comprehensive Legacy Waste Program. The program directs work to manage low level and mixed wastes to ensure compliance with nuclear facility rules and its STP. This paper provides a survey of work conducted on these wastes at LLNL. They include commercial waste treatment and disposal, diverse forms of characterization, inventory maintenance and reporting, on-site treatment, and treatability studies. These activities are conducted in an integrated fashion to meet schedules defined in the STP. The processes managing wastes are dynamic due to required integration of administrative, regulatory, and technical concerns spanning the gamut to insure safe proper disposal

X-ray emission from National Ignition Facility indirect drive targets

International Nuclear Information System (INIS)

Anderson, A.T.; Managan, R.A.; Tobin, M.T.; Peterson, P.F.

1996-01-01

We have performed a series of 1-D numerical simulations of the x-ray emission from National Ignition Facility (NIF) targets. Results are presented in terms of total x-ray energy, pulse length, and spectrum. Scaling of x-ray emissions is presented for variations in both target yield and hohlraum thickness. Experiments conducted on the Nova facility provide some validation of the computational tools and methods

Modeling the Perceptions and Preferences of Pedestrians on Crossing Facilities

Directory of Open Access Journals (Sweden)

Hongwei Guo

2014-01-01

Full Text Available Pedestrian’s street-crossing behaviour has a significant effect on traffic performance and safety. The crossing behaviour is determined by human factors and environmental factors. Aiming at examining the pedestrian perceptions toward crossing facilities and preferences for crossing locations, an observational study of pedestrian crossing behaviour at urban street is conducted. The perceptions and preferences of pedestrians are collected using stated preference technique. A specific questionnaire is designed to conduct the stated preference survey. A multinomial logit model is proposed to describe the perceptions and preferences of pedestrians on crossing facilities and locations. The sensitivity analysis is performed to discuss the influence of various factors on crossing behaviour. Then the relationship between crossing locations and crossing distances is analyzed by a new proposed method. With the theoretical analysis, the engineering solutions considering pedestrian behaviour are suggested. The results are helpful to design human-centered crossing facilities in urban traffic.

Use of risk information to safety regulation. Reprocessing facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

A procedure of probabilistic risk assessment (PRA) for a reprocessing facility has been under the development aiming to utilize risk information for safety regulations in this project. Activities in the fiscal year 2012 are summarized in the paper. A major activity is a fundamental study on a concept of serious accidents, requirements of serious accident management, and a policy of utilizing risk information for fabrication and reprocessing facilities. Other than the activity a study on release and transport of aerial radioactive materials at a serious accident in a reprocessing facility has been conducted. The outline and results are provided in the chapter 1 and 2 respectively. (author)

Accelerator based research facility as an inter university centre

International Nuclear Information System (INIS)

Mehta, G.K.

1995-01-01

15 UD pelletron has been operating as a user facility from July 1991. It is being utilised by a large number of universities and other institutions for research in basic Nuclear Physics, Materials Science, Atomic Physics, Radiobiology and Radiation Chemistry. There is an on-going programme for augmenting the accelerator facilities by injecting Pelletron beams into superconducting linear accelerator modules. Superconducting niobium resonator is being developed in Argonne National Laboratory as a joint collaborative effort. All other things such as cryostats, rf instrumentation, cryogenic distribution system, computer control etc are being done indigenously. Research facilities, augmentation plans and the research being conducted by the universities in various disciplines are described. (author)

Wastewater treatment facilities: Energy efficient improvements and cogeneration

International Nuclear Information System (INIS)

Kunkle, R.; Gray, R.; Delzel, D.

1992-10-01

The Washington State Energy Office (WSEO) has worked with both the Bonneville Power Administration (BPA) and the US Department of Energy to provide technical and financial assistance to local governments. Based on a recent study conducted by Ecotope for WSEO, local governments spend an estimated $45 million on utility bills statewide. Water and wastewater facilities account for almost a third of this cost. As a result, WSEO decided to focus its efforts on the energy intensive water and wastewater sector. The ultimate goal of this project was to develop mechanisms to incorporate energy efficiency improvements into wastewater treatment facilities in retrofits and during upgrades, remodels, and new construction. Project activities included the following: The review of the existing regulatory environment for treatment system construction, A summary of financing options for efficiency improvements in treatment facilities, A literature review of energy efficiency opportunities in treatment plants, Survey and site visits to characterize existing facilities in Washington State, Estimates of the energy efficiency and cogeneration potential in the sector, and A case study to illustrate the implementation of an efficiency improvement in a treatment facility

Consolidating parenting skills in children’s facilities

Directory of Open Access Journals (Sweden)

Ivana Dokoupilová

2016-12-01

Full Text Available The content of this paper is a report on activities in children’s facilities and their ability to influence parenting skills in terms of institutional childcare at an early age. Children’s facilities (infant homes, children’s homes and children’s centres provide comprehensive care for children and parents in cases where, for various reasons, a child’s all-round development is disrupted or their life is in danger. The main purpose of these facilities is to provide adequate childcare as well as to support families when restoring basic functions. On the basis of a survey conducted in children’s facilities, the most frequent difficulties in exercising parenting skills are identified, and subsequently, information on the extent to which children’s facilities contribute to the development of parenting skills and help in the rehabilitation of a family is outlined.

The NRU blowdown test facility commissioning program

Energy Technology Data Exchange (ETDEWEB)

Walsworth, J A; Zanatta, R J; Yamazaki, A R; Semeniuk, D D; Wong, W; Dickson, L W; Ferris, C E; Burton, D H [Atomic Energy of Canada Ltd., Chalk River, ON (Canada). Chalk River Nuclear Labs.

1990-12-31

A major experimental program has been established at the Chalk River Nuclear Laboratories (CRL) that will provide essential data on the thermal and mechanical behaviour of nuclear fuel under abnormal reactor operating conditions and on the transient release, transport and deposition of fission product activity from severely degraded fuel. A number of severe fuel damage (SFD) experiments will be conducted within the Blowdown Test Facility (BTF) at CRL. A series of experiments are being conducted to commission this new facility prior to the SFD program. This paper describes the features and the commissioning program for the BTF. A development and testing program is described for critical components used on the reactor test section. In-reactor commissioning with a fuel assembly simulator commenced in 1989 June and preliminary results are given. The paper also outlines plans for future all-effects, in-reactor tests of CANDU-designed fuel. (author). 11 refs., 3 tabs., 7 figs.

Compact Ignition Tokamak conventional facilities optimization

International Nuclear Information System (INIS)

Commander, J.C.; Spang, N.W.

1987-01-01

A high-field ignition machine with liquid-nitrogen-cooled copper coils, designated the Compact Ignition Tokamak (CIT), is proposed for the next phase of the United States magnetically confined fusion program. A team of national laboratory, university, and industrial participants completed the conceptual design for the CIT machine, support systems and conventional facilities. Following conceptual design, optimization studies were conducted with the goal of improving machine performance, support systems design, and conventional facilities configuration. This paper deals primarily with the conceptual design configuration of the CIT conventional facilities, the changes that evolved during optimization studies, and the revised changes resulting from functional and operational requirements (F and ORs). The CIT conventional facilities conceptual design is based on two premises: (1) satisfaction of the F and ORs developed in the CIT building and utilities requirements document, and (2) the assumption that the CIT project will be sited at the Princeton Plasma Physics Laboratory (PPPL) in order that maximum utilization can be made of existing Tokamak Fusion Test Reactor (TFTR) buildings and utilities. The optimization studies required reevaluation of the F and ORs and a second look at TFTR buildings and utilities. Some of the high-cost-impact optimization studies are discussed, including the evaluation criteria for a change from the conceptual design baseline configuration. The revised conventional facilities configuration are described and the estimated cost impact is summarized

Written-in conductive patterns on robust graphene oxide biopaper by electrochemical microstamping.

Science.gov (United States)

Hu, Kesong; Tolentino, Lorenzo S; Kulkarni, Dhaval D; Ye, Chunhong; Kumar, Satish; Tsukruk, Vladimir V

2013-12-16

The silk road: By employing silk fibroin as a binder between graphene oxide films and aluminum foil for a facile, highly localized reduction process, conductive paper is reinvented. The flexible, robust biographene papers have high toughness and electrical conductivity. This electrochemical written-in approach is readily applicable for the fabrication of conductive patterned papers with complex circuitries. Copyright © 2013 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

The Valduc waste incineration facility starts operations (iris process)

International Nuclear Information System (INIS)

Chateauvieux, H.; Guiberteuau, P.; Longuet, T.; Lannaud, J.; Lorich, M.

1998-01-01

In the operation of its facilities the Valduc Research Center produces alpha-contaminated solid waste and thus decided to build an incineration facility to treat the most contaminated combustible waste. The process selected for waste incineration is the IRIS process developed by the CEA at the Marcoule Nuclear Research Center. The Valduc Center asked SGN to build the incineration facility. The facility was commissioned in late 1996, and inactive waste incineration campaigns were run in 1997. The operator conducted tests with calibrated radioactive sources to qualify the systems for measuring holdup of active material from outside the equipment. Chlorinated waste incineration test runs were performed using the phosphatizing process developed by the Marcoule Research Center. Inspections performed after these incineration runs revealed the complete absence of corrosion in the equipment. Active commissioning of the facility is scheduled for mid-1998. The Valduc incinerator is the first industrial application of the IRIS process. (author)

Emergency preparedness and response plan for nuclear facilities in Indonesia

International Nuclear Information System (INIS)

Nur Rahmah Hidayati; Pande Made Udiyani

2009-01-01

All nuclear facilities in Indonesia are owned and operated by the National Nuclear Energy Agency (BATAN). The programs and activities of emergency planning and preparedness in Indonesia are based on the existing nuclear facilities, i.e. research reactors, research reactor fuel fabrication plant, radioactive waste treatment installation and radioisotopes production installation. The assessment is conducted to learn of status of emergency preparedness and response plan for nuclear facilities in Indonesia and to support the preparation of future Nuclear Power Plant. The assessment is conducted by comparing the emergency preparedness and response system in Indonesia to the system in other countries such as Japan and Republic of Korea, since the countries have many Nuclear Power Plants and other nuclear facilities. As a result, emergency preparedness response plan for existing nuclear facility in Indonesia has been implemented in many activities such as environmental monitoring program, facility monitoring equipment, and the continuous exercise of emergency preparedness and response. However, the implementation need law enforcement for imposing the responsibility of the coordinators in National Emergency Preparedness Plan. It also needs some additional technical support systems which refer to the system in Japan or Republic of Korea. The systems must be completed with some real time monitors which will support the emergency preparedness and response organization. The system should be built in NPP site before the first NPP will be operated. The system should be connected to an Off Site Emergency Center under coordination of BAPETEN as the regulatory body which has responsibility to control of nuclear energy in Indonesia. (Author)

Buffet test in the National Transonic Facility

Science.gov (United States)

Young, Clarence P., Jr.; Hergert, Dennis W.; Butler, Thomas W.; Herring, Fred M.

1992-01-01

A buffet test of a commercial transport model was accomplished in the National Transonic Facility at the NASA Langley Research Center. This aeroelastic test was unprecedented for this wind tunnel and posed a high risk to the facility. This paper presents the test results from a structural dynamics and aeroelastic response point of view and describes the activities required for the safety analysis and risk assessment. The test was conducted in the same manner as a flutter test and employed onboard dynamic instrumentation, real time dynamic data monitoring, automatic, and manual tunnel interlock systems for protecting the model. The procedures and test techniques employed for this test are expected to serve as the basis for future aeroelastic testing in the National Transonic Facility. This test program was a cooperative effort between the Boeing Commercial Airplane Company and the NASA Langley Research Center.

Tritium burning in inertial electrostatic confinement fusion facility

Energy Technology Data Exchange (ETDEWEB)

Ohnishi, Masami, E-mail: onishi@kansai-u.ac.jp [Department of Science and Engineering, Kansai University, 3-3-35 Yamate-cho, Suita, Osaka 564-8680 (Japan); Yamamoto, Yasushi; Osawa, Hodaka [Department of Science and Engineering, Kansai University, 3-3-35 Yamate-cho, Suita, Osaka 564-8680 (Japan); Hatano, Yuji; Torikai, Yuji [Hydrogen Isotope Science Center, University of Toyama, Gofuku, Toyama 930-8555 (Japan); Murata, Isao [Faculty of Engineering Environment and Energy Department, Osaka University, 2-1 Yamadaoka, Suita, Osaka 565-0871 (Japan); Kamakura, Keita; Onishi, Masaaki; Miyamoto, Keiji; Konda, Hiroki [Department of Science and Engineering, Kansai University, 3-3-35 Yamate-cho, Suita, Osaka 564-8680 (Japan); Masuda, Kai [Institute of Advanced Energy, Kyoto University, Gokasho, Uji, Kyoto 611-0011 (Japan); Hotta, Eiki [Interdisciplinary Graduate School of Science and Engineering, Tokyo Institute of Technology, 4259 Nagatsuda-cho, Midori-ku, Yokohama 226-8503 (Japan)

2016-11-01

Highlights: • An experiment on tritium burning is conducted in an inertial electrostatic confinement fusion (IECF) facility. • A deuterium–tritium gas mixture with 93% deuterium and 7% tritium is used. • The neutron production rate is measured to be 5–8 times more than that of pure deuterium gas. • The neutron production rate of the D–T gas mixture in 1:1 ratio is expected to be more than 10{sup 8}(1/sec) in the present D–T experiment. - Abstract: An experiment on tritium burning is conducted to investigate the enhancement in the neutron production rate in an inertial electrostatic confinement fusion (IECF) facility. The facility is designed such that it is shielded from the outside for safety against tritium and a getter pump is used for evacuating the vacuum chamber and feeding the fuel gas. A deuterium–tritium gas mixture with 93% deuterium and 7% tritium is used, and its neutron production rate is measured to be 5–8 times more than that of pure deuterium gas. Moreover, the results show good agreement with those of a simplified theoretical estimation of the neutron production rate. After tritium burning, the exhausted fuel gas undergoes a tritium recovery procedure through a water bubbler device. The amount of gaseous tritium released by the developed IECF facility after tritium burning is verified to be much less than the threshold set by regulations.

Tritium burning in inertial electrostatic confinement fusion facility

International Nuclear Information System (INIS)

Ohnishi, Masami; Yamamoto, Yasushi; Osawa, Hodaka; Hatano, Yuji; Torikai, Yuji; Murata, Isao; Kamakura, Keita; Onishi, Masaaki; Miyamoto, Keiji; Konda, Hiroki; Masuda, Kai; Hotta, Eiki

2016-01-01

Highlights: • An experiment on tritium burning is conducted in an inertial electrostatic confinement fusion (IECF) facility. • A deuterium–tritium gas mixture with 93% deuterium and 7% tritium is used. • The neutron production rate is measured to be 5–8 times more than that of pure deuterium gas. • The neutron production rate of the D–T gas mixture in 1:1 ratio is expected to be more than 10"8(1/sec) in the present D–T experiment. - Abstract: An experiment on tritium burning is conducted to investigate the enhancement in the neutron production rate in an inertial electrostatic confinement fusion (IECF) facility. The facility is designed such that it is shielded from the outside for safety against tritium and a getter pump is used for evacuating the vacuum chamber and feeding the fuel gas. A deuterium–tritium gas mixture with 93% deuterium and 7% tritium is used, and its neutron production rate is measured to be 5–8 times more than that of pure deuterium gas. Moreover, the results show good agreement with those of a simplified theoretical estimation of the neutron production rate. After tritium burning, the exhausted fuel gas undergoes a tritium recovery procedure through a water bubbler device. The amount of gaseous tritium released by the developed IECF facility after tritium burning is verified to be much less than the threshold set by regulations.

Integrated Disposal Facility FY 2012 Glass Testing Summary Report

Energy Technology Data Exchange (ETDEWEB)

Pierce, Eric M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Kerisit, Sebastien N. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Krogstad, Eirik J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Burton, Sarah D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Bjornstad, Bruce N. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Freedman, Vicky L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Cantrell, Kirk J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Snyder, Michelle MV [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Crum, Jarrod V. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Westsik, Joseph H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2013-03-29

PNNL is conducting work to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility for Hanford immobilized low-activity waste (ILAW). Before the ILAW can be disposed, DOE must conduct a performance assessment (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program, PNNL is implementing a strategy, consisting of experimentation and modeling, to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. Key activities in FY12 include upgrading the STOMP/eSTOMP codes to do near-field modeling, geochemical modeling of PCT tests to determine the reaction network to be used in the STOMP codes, conducting PUF tests on selected glasses to simulate and accelerate glass weathering, developing a Monte Carlo simulation tool to predict the characteristics of the weathered glass reaction layer as a function of glass composition, and characterizing glasses and soil samples exhumed from an 8-year lysimeter test. The purpose of this report is to summarize the progress made in fiscal year (FY) 2012 and the first quarter of FY 2013 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of LAW glasses.

Large-coil-test-facility fault-tree analysis

International Nuclear Information System (INIS)

1982-01-01

An operating-safety study is being conducted for the Large Coil Test Facility (LCTF). The purpose of this study is to provide the facility operators and users with added insight into potential problem areas that could affect the safety of personnel or the availability of equipment. This is a preliminary report, on Phase I of that study. A central feature of the study is the incorporation of engineering judgements (by LCTF personnel) into an outside, overall view of the facility. The LCTF was analyzed in terms of 32 subsystems, each of which are subject to failure from any of 15 generic failure initiators. The study identified approximately 40 primary areas of concern which were subjected to a computer analysis as an aid in understanding the complex subsystem interactions that can occur within the facility. The study did not analyze in detail the internal structure of the subsystems at the individual component level. A companion study using traditional fault tree techniques did analyze approximately 20% of the LCTF at the component level. A comparison between these two analysis techniques is included in Section 7

Decommissioning of nuclear facilities using current criteria

International Nuclear Information System (INIS)

Shum, E.Y.; Swift, J.J.; Malaro, J.C.

1991-01-01

When a licensed nuclear facility ceases operation, the US Nuclear Regulatory Commission (NRC) is responsible for ensuring that the facility and its site are decontaminated to an acceptable level so that it is safe to release that facility and site for unrestricted public use. Currently, the NRC is developing decommissioning criteria based on reducing public doses from residual contamination in soils and structures at sites released for unrestricted use to as low as is reasonably achievable (ALARA). Plans are to quantify ALARA in terms of an annual total effective dose equivalent (TEDE) to an average member of the most highly exposed population group. The NRC is working on a regulatory guidance document to provide a technical basis for translating residual contamination levels to annual dose levels. Another regulatory guide is being developed to provide guidance to the licensee on how to conduct radiological surveys to demonstration compliance with the NRC decommissioning criteria. The methods and approaches used in these regulatory guides on the decommissioning of a nuclear facility are discussed in the paper

Biosecurity measures in 48 isolation facilities managing highly infectious diseases.

Science.gov (United States)

Puro, Vincenzo; Fusco, Francesco M; Schilling, Stefan; Thomson, Gail; De Iaco, Giuseppina; Brouqui, Philippe; Maltezou, Helena C; Bannister, Barbara; Gottschalk, René; Brodt, Hans-Rheinhard; Ippolito, Giuseppe

2012-06-01

Biosecurity measures are traditionally applied to laboratories, but they may also be usefully applied in highly specialized clinical settings, such as the isolation facilities for the management of patients with highly infectious diseases (eg, viral hemorrhagic fevers, SARS, smallpox, potentially severe pandemic flu, and MDR- and XDR-tuberculosis). In 2009 the European Network for Highly Infectious Diseases conducted a survey in 48 isolation facilities in 16 European countries to determine biosecurity measures for access control to the facility. Security personnel are present in 39 facilities (81%). In 35 facilities (73%), entrance to the isolation area is restricted; control methods include electronic keys, a PIN system, closed-circuit TV, and guards at the doors. In 25 facilities (52%), identification and registration of all staff entering and exiting the isolation area are required. Access control is used in most surveyed centers, but specific lacks exist in some facilities. Further data are needed to assess other biosecurity aspects, such as the security measures during the transportation of potentially contaminated materials and measures to address the risk of an "insider attack."

Seismic reevaluation of nuclear facilities worldwide: Overview and status

Energy Technology Data Exchange (ETDEWEB)

Campbell, R D; Hardy, G S; Ravindra, M K [EQE International, Irvine, CA (United States); Johnson, J J [EQE International, San Francisco, CA (United States); Hoy, A J [EQE International Ltd., Birchwood, Warrington (United Kingdom)

1995-07-01

Existing nuclear facilities throughout the world are being subjected to severe scrutiny of their safety in tile event of an earthquake. In the United States, there have been several licensing and safety review issues for which industry and regulatory agencies have cooperated to develop rational and economically feasible criteria for resolving the issues. Currently, all operating nuclear power plants in the United States are conducting an Individual Plant Examination of External Events, including earthquakes beyond tile design basis. About two-thirds of tile operating plants are conducting parallel programs for verifying, tile seismic adequacy of equipment for the design basis earthquake. The U.S. Department of Energy is also beginning to perform detailed evaluations of their facilities, many of which had little or no seismic design. Western European countries also have been reevaluating their older nuclear power plants for seismic events often adapting the criteria developed in the United States. With the change in tile political systems in Eastern Europe, there is a strong emphasis from their Western European neighbors to evaluate and Upgrade tile safely of their operating nuclear power plants. Finally, nuclear facilities in Asia are, also, being evaluated for seismic vulnerabilities. This paper focuses oil tile methodologies that have been developed for reevaluation of existing nuclear power plants and presents examples of the application of these methodologies to nuclear facilities worldwide. (author)

Seismic reevaluation of nuclear facilities worldwide: Overview and status

International Nuclear Information System (INIS)

Campbell, R.D.; Hardy, G.S.; Ravindra, M.K.; Johnson, J.J.; Hoy, A.J.

1995-01-01

Existing nuclear facilities throughout the world are being subjected to severe scrutiny of their safety in tile event of an earthquake. In the United States, there have been several licensing and safety review issues for which industry and regulatory agencies have cooperated to develop rational and economically feasible criteria for resolving the issues. Currently, all operating nuclear power plants in the United States are conducting an Individual Plant Examination of External Events, including earthquakes beyond tile design basis. About two-thirds of tile operating plants are conducting parallel programs for verifying, tile seismic adequacy of equipment for the design basis earthquake. The U.S. Department of Energy is also beginning to perform detailed evaluations of their facilities, many of which had little or no seismic design. Western European countries also have been reevaluating their older nuclear power plants for seismic events often adapting the criteria developed in the United States. With the change in tile political systems in Eastern Europe, there is a strong emphasis from their Western European neighbors to evaluate and Upgrade tile safely of their operating nuclear power plants. Finally, nuclear facilities in Asia are, also, being evaluated for seismic vulnerabilities. This paper focuses oil tile methodologies that have been developed for reevaluation of existing nuclear power plants and presents examples of the application of these methodologies to nuclear facilities worldwide. (author)

Health facility committees and facility management - exploring the nature and depth of their roles in Coast Province, Kenya

Directory of Open Access Journals (Sweden)

Kabare Margaret

2011-09-01

Full Text Available Abstract Background Community participation has been emphasized internationally as a way of enhancing accountability, as well as a means to enhance health goals in terms of coverage, access and effective utilization. In rural health facilities in Kenya, initiatives to increase community accountability have focused on Health Facility Committees (HFCs. In Coast Province the role of HFCs has been expanded with the introduction of direct funding of rural facilities. We explored the nature and depth of managerial engagement of HFCs at the facility level in two rural districts in this Coastal setting, and how this has contributed to community accountability Methods We conducted structured interviews with the health worker in-charge and with patients in 30 health centres and dispensaries. These data were supplemented with in-depth interviews with district managers, and with health workers and HFC members in 12 health centres and dispensaries. In-depth interviews with health workers and HFC members included a participatory exercise to stimulate discussion of the nature and depth of their roles in facility management. Results HFCs were generally functioning well and played an important role in facility operations. The breadth and depth of engagement had reportedly increased after the introduction of direct funding of health facilities which allowed HFCs to manage their own budgets. Although relations with facility staff were generally good, some mistrust was expressed between HFC members and health workers, and between HFC members and the broader community, partially reflecting a lack of clarity in HFC roles. Moreover, over half of exit interviewees were not aware of the HFC's existence. Women and less well-educated respondents were particularly unlikely to know about the HFC. Conclusions There is potential for HFCs to play an active and important role in health facility management, particularly where they have control over some facility level resources

Health facility committees and facility management - exploring the nature and depth of their roles in Coast Province, Kenya.

Science.gov (United States)

Goodman, Catherine; Opwora, Antony; Kabare, Margaret; Molyneux, Sassy

2011-09-22

Community participation has been emphasized internationally as a way of enhancing accountability, as well as a means to enhance health goals in terms of coverage, access and effective utilization. In rural health facilities in Kenya, initiatives to increase community accountability have focused on Health Facility Committees (HFCs). In Coast Province the role of HFCs has been expanded with the introduction of direct funding of rural facilities. We explored the nature and depth of managerial engagement of HFCs at the facility level in two rural districts in this Coastal setting, and how this has contributed to community accountability We conducted structured interviews with the health worker in-charge and with patients in 30 health centres and dispensaries. These data were supplemented with in-depth interviews with district managers, and with health workers and HFC members in 12 health centres and dispensaries. In-depth interviews with health workers and HFC members included a participatory exercise to stimulate discussion of the nature and depth of their roles in facility management. HFCs were generally functioning well and played an important role in facility operations. The breadth and depth of engagement had reportedly increased after the introduction of direct funding of health facilities which allowed HFCs to manage their own budgets. Although relations with facility staff were generally good, some mistrust was expressed between HFC members and health workers, and between HFC members and the broader community, partially reflecting a lack of clarity in HFC roles. Moreover, over half of exit interviewees were not aware of the HFC's existence. Women and less well-educated respondents were particularly unlikely to know about the HFC. There is potential for HFCs to play an active and important role in health facility management, particularly where they have control over some facility level resources. However, to optimise their contribution, efforts are needed to

Simulator Facility for Attitude Control and Energy Storage of Spacecraft

National Research Council Canada - National Science Library

Tsiotras, Panagiotis

2002-01-01

This report concerns a designed and built experimental facility that will allow the conduction of experiments for validating advanced attitude control algorithms for spacecraft in a weightless environment...

Feasibility Investigation for a Solar Power Generation Facility

Science.gov (United States)

Nathan, Lakshmi

2010-01-01

The Energy Policy Act of 2005 states that by fiscal year 2013, at least 7.5% of the energy consumed by the government must be renewable energy. In an effort to help meet this goal, Johnson Space Center (JSC) is considering installing a solar power generation facility. The purpose of this project is to conduct a feasibility investigation for such a facility. Because Kennedy Space Center (KSC) has a solar power generation facility, the first step in this investigation is to learn about KSC's facility and obtain information on how it was constructed. After collecting this information, the following must be determined: the amount of power desired, the size of the facility, potential locations for it, and estimated construction and maintenance costs. Contacts with JSC's energy provider must also be established to determine if a partnership would be agreeable to both parties. Lastly, all of this data must be analyzed to decide whether or not JSC should construct the facility. The results from analyzing the data collected indicate that a 200 kW facility would provide enough energy to meet 1% of JSC's energy demand. This facility would require less than 1 acre of land. In the map below, potential locations are shown in green. The solar power facility is projected to cost $2 M. So far, the information collected indicates that such a facility could be constructed. The next steps in this investigation include contacting JSC's energy provider, CenterPoint Energy, to discuss entering a partnership; developing a life cycle cost analysis to determine payback time; developing more detailed plans; and securing funding.

A Qualitative Analysis of Facilities Maintenance--A School Governance Function in South Africa

Science.gov (United States)

Xaba, M. I.

2012-01-01

I analysed school facilities maintenance, a school governance function in South Africa. Qualitative interviews were conducted with 13 principals and three deputy principals as coordinators of this function at their schools. The interviews were purposively and conveniently selected to gather data regarding school facilities maintenance and gain…

Audit of the Uranium Solidification Facility at the Savannah River Site

International Nuclear Information System (INIS)

1994-01-01

In the late 1980s, DOE decided to construct a Uranium Solidification Facility at the Savannah River Site to process liquid uranyl nitrate into powder. Since the need for weapons materials has been reduced, an audit was conducted to assess the need for this facility. The audit disclosed that DOE continued to construct the facility, because DOE's procedures did not ensure that projects of this type were periodically reassessed when significant program changes occurred. The audit identified more economical alternatives for processing existing quantities of liquid uranyl nitrate at the Savannah River Site

Ionomers for Ion-Conducting Energy Materials

Science.gov (United States)

Colby, Ralph

For ionic actuators and battery separators, it is vital to utilize single-ion conducting ionomers that avoid the detrimental polarization of other ions. Single-ion conducting ionomers are synthesized based on DFT calculations, with low glass transition temperatures (facile dynamics) to prepare ion-conducting membranes for battery separators that conduct Li+ or Na+. Characterization by X-ray scattering, dielectric spectroscopy, FTIR, NMR and linear viscoelasticity collectively develop a coherent picture of ionic aggregation and both counterion and polymer dynamics. 7Li NMR diffusion measurements find that diffusion is faster than expected by conductivity using the Nernst-Einstein equation, which means that the majority of Li diffusion occurs by ion pairs moving with the polymer segmental motion. Segmental motion only contributes to ionic conduction in the rare event that one of these ion pairs has an extra Li (a positive triple ion). This leads us to a new metric for ion-conducting soft materials, the product of the cation number density p0 and their diffusion coefficient D; p0D is the diffusive flux of lithium ions. This new metric has a maximum at intermediate ion content that corresponds to the overlap of ion pair polarizability volumes. At higher ion contents, the ion pairs interact strongly and form larger aggregation states that retard segmental motion of both mobile ion pairs and triple ions.

NCI-supported facility to conduct cancer trials breaks ground in Puerto Rico

Science.gov (United States)

The Puerto Rican government has allocated $196 million dollars to build a 287,000 sq. ft., 96-bed, cancer hospital in San Juan. The new hospital, which will provide cancer treatment and conduct clinical trials, is the first of its kind in the Caribbean.

The difficulties of conducting maternal death reviews in Malawi

Directory of Open Access Journals (Sweden)

van den Broek Nynke

2008-09-01

Full Text Available Abstract Background Maternal death reviews is a tool widely recommended to improve the quality of obstetric care and reduce maternal mortality. Our aim was to explore the challenges encountered in the process of facility-based maternal death review in Malawi, and to suggest sustainable and logically sound solutions to these challenges. Methods SWOT (strengths, weaknesses, opportunities and threats analysis of the process of maternal death review during a workshop in Malawi. Results Strengths: Availability of data from case notes, support from hospital management, and having maternal death review forms. Weaknesses: fear of blame, lack of knowledge and skills to properly conduct death reviews, inadequate resources and missing documentation. Opportunities: technical assistance from expatriates, support from the Ministry of Health, national protocols and high maternal mortality which serves as motivation factor. Threats: Cultural practices, potential lawsuit, demotivation due to the high maternal mortality and poor planning at the district level. Solutions: proper documentation, conducting maternal death review in a blame-free manner, good leadership, motivation of staff, using guidelines, proper stock inventory and community involvement. Conclusion Challenges encountered during facility-based maternal death review are provider-related, administrative, client related and community related. Countries with similar socioeconomic profiles to Malawi will have similar 'pull-and-push' factors on the process of facility-based maternal death reviews, and therefore we will expect these countries to have similar potential solutions.

The difficulties of conducting maternal death reviews in Malawi.

Science.gov (United States)

Kongnyuy, Eugene J; van den Broek, Nynke

2008-09-11

Maternal death reviews is a tool widely recommended to improve the quality of obstetric care and reduce maternal mortality. Our aim was to explore the challenges encountered in the process of facility-based maternal death review in Malawi, and to suggest sustainable and logically sound solutions to these challenges. SWOT (strengths, weaknesses, opportunities and threats) analysis of the process of maternal death review during a workshop in Malawi. Strengths: Availability of data from case notes, support from hospital management, and having maternal death review forms. Weaknesses: fear of blame, lack of knowledge and skills to properly conduct death reviews, inadequate resources and missing documentation. Opportunities: technical assistance from expatriates, support from the Ministry of Health, national protocols and high maternal mortality which serves as motivation factor. Threats: Cultural practices, potential lawsuit, demotivation due to the high maternal mortality and poor planning at the district level. Solutions: proper documentation, conducting maternal death review in a blame-free manner, good leadership, motivation of staff, using guidelines, proper stock inventory and community involvement. Challenges encountered during facility-based maternal death review are provider-related, administrative, client related and community related. Countries with similar socioeconomic profiles to Malawi will have similar 'pull-and-push' factors on the process of facility-based maternal death reviews, and therefore we will expect these countries to have similar potential solutions.

Safeguards at NRC licensed facilities: Are we doing enough

International Nuclear Information System (INIS)

Asselstine, J.K.

1986-01-01

Safeguards at the Nuclear Regulatory Commission (NRC) facilities are discussed in this paper. The NRC is pursuing a number of initiatives in the safeguards area. The Commission is conducting a reassessment of its safeguards design basis threat statements to consider the possible implications of an explosive-laden vehicle for U.S. nuclear safeguards and to examine the comparability of safeguards features at NRC-licensed and DOE facilities. The Commission is also completing action on measures to protect against the sabotage threat from an insider at NRC-licensed facilities, and is examining the potential safety implications of safeguards measures. Finally, the NRC has developed measures to reduce the theft potential for high-enriched uranium

ADA Compliance and Accessibility of Fitness Facilities in Western Wisconsin.

Science.gov (United States)

Johnson, Marquell J; Stoelzle, Hannah Y; Finco, Kristi L; Foss, Sadie E; Carstens, Katie

2012-01-01

The study expands the research on fitness facility accessibility by determining how compliant fitness facilities in rural western Wisconsin were with Title III of the Americans with Disabilities Act (ADA). Comparisons were made with 4 other studies that were conducted in different geographical regions. The study also examined fitness professionals' disability knowledge and awareness. An ADA fitness facility compliance instrument and a fitness professional disability awareness survey were used. Direct observation and physical measurements were taken during on-site visits to 16 of 36 eligible fitness facilities in rural western Wisconsin. Ten fitness professionals from participating facilities completed an online survey. Frequencies were used to analyze the results. None of the participating facilities were in 100% compliance with ADA. Customer service desk (84%) and path of travel throughout the facility (72%) were the highest compliance areas. Telephone (6%) and locker rooms (32%) were the lowest compliance areas. No fitness professional was trained in wheelchair transfers and very few had received training in providing services to individuals with disabilities. Fitness facility accessibility remains a concern nationally. Continued efforts need to be made to raise the awareness of ADA compliance among fitness professionals across the United States, especially in rural areas where fitness facility availability is limited.

Silver Flakes and Silver Dendrites for Hybrid Electrically Conductive Adhesives with Enhanced Conductivity

Science.gov (United States)

Ma, Hongru; Li, Zhuo; Tian, Xun; Yan, Shaocun; Li, Zhe; Guo, Xuhong; Ma, Yanqing; Ma, Lei

2018-03-01

Silver dendrites were prepared by a facile replacement reaction between silver nitrate and zinc microparticles of 20 μm in size. The influence of reactant molar ratio, reaction solution volume, silver nitrate concentration, and reaction time on the morphology of dendrites was investigated systematically. It was found that uniform tree-like silver structures are synthesized under the optimal conditions. Their structure can be described as a trunk, symmetrical branches, and leaves, which length scales of 5-10, 1-2 μm, and 100-300 nm, respectively. All features were systematically characterized by scanning electron microscopy, transmission electron microscopy (TEM), high-resolution TEM, and x-ray powder diffraction. A hybrid fillers system using silver flakes and dendrites as electrically conductive adhesives (ECAs) exhibited excellent overall performance. This good conductivity can be attributed mainly to the synergy between the silver microflakes (5-20 μm sized irregular sheet structures) and dendrites, allowing more conductive pathways to be formed between the fillers. In order to further optimize the overall electrical conductivity, various mixtures of silver microflakes and silver dendrites were tested in ECAs, with results indicating that the highest conductivity was shown when the amounts of silver microflakes, silver dendrites and the polymer matrix were 69.4 wt.% (20.82 vol.%), 0.6 wt.% (0.18 vol.%), and 30.0 wt.% (79.00 vol.%), respectively. The corresponding mass ratio of silver flakes to silver dendrites was 347:3. The resistivity of ECAs reached as low as 1.7 × 10-4 Ω cm.

Safe waste management practices in beryllium facilities

International Nuclear Information System (INIS)

Bhat, P.N.; Soundararajan, S.; Sharma, D.N.

2012-01-01

Beryllium, an element with the atomic symbol Be, atomic number 4, has very high stiffness to weight ratio and low density. It has good electrical conductive properties with low coefficient of thermal expansion. These properties make the metal beryllium very useful in varied technological endeavours, However, beryllium is recognised as one of the most toxic metals. Revelation of toxic effects of beryllium resulted in institution of stringent health and safety practices in beryllium handling facilities. The waste generated in such facilities may contain traces of beryllium. Any such waste should be treated as toxic waste and suitable safe waste management practices should be adopted. By instituting appropriate waste management practice and through a meticulously incorporated safety measures and continuous surveillance exercised in such facilities, total safety can be ensured. This paper broadly discusses health hazards posed by beryllium and safe methods of management of beryllium bearing wastes. (author)

Mixed and Low-Level Waste Treatment Facility project

International Nuclear Information System (INIS)

1992-04-01

Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. The engineering studies, initiated in July 1991, identified 37 mixed waste streams, and 55 low-level waste streams. This report documents the waste stream information and potential treatment strategies, as well as the regulatory requirements for the Department of Energy-owned treatment facility option. The total report comprises three volumes and two appendices. This report consists of Volume 1, which explains the overall program mission, the guiding assumptions for the engineering studies, and summarizes the waste stream and regulatory information, and Volume 2, the Waste Stream Technical Summary which, encompasses the studies conducted to identify the INEL's waste streams and their potential treatment strategies

On the effectiveness of the Federal Reserve's new liquidity facilities

OpenAIRE

Tao Wu

2008-01-01

This paper examines the effectiveness of the new liquidity facilities that the Federal Reserve established in response to the recent financial crisis. I develop a no-arbitrage based affine term structure model with default risk and conduct a thorough factor analysis of the counterparty default risk among major financial institutions and the underlying mortgage default risk. The new facilities' effectiveness is examined, by first separately examining their effects in relieving financial instit...

Use of antibiotics in paediatric long-term care facilities.

Science.gov (United States)

Murray, M T; Johnson, C L; Cohen, B; Jackson, O; Jones, L K; Saiman, L; Larson, E L; Neu, N

2018-06-01

Adult long-term care (LTC) facilities have high rates of antibiotic use, raising concerns about antimicrobial resistance. Few studies have examined antibiotic use in paediatric LTC facilities. To describe antibiotic use in three paediatric LTC facilities and to describe the factors associated with use. A retrospective cohort study was conducted from September 2012 to December 2015 in three paediatric LTC facilities. Medical records were reviewed for demographics, healthcare-associated infections (HAIs), antimicrobial use and diagnostic testing. Logistic regression was used to identify predictors for antibiotic use. The association between susceptibility testing results and appropriate antibiotic coverage was determined using Chi-squared test. Fifty-eight percent (413/717) of residents had at least one HAI, and 79% (325/413) of these residents were treated with at least one antibiotic course, totalling 2.75 antibiotic courses per 1000 resident-days. Length of enrolment greater than one year, having a neurological disorder, having a tracheostomy, and being hospitalized at least once during the study period were significantly associated with receiving antibiotics when controlling for facility (all P facilities is widespread. There is further need to assess antibiotic use in paediatric LTC facilities. Evaluation of the adverse outcomes associated with inappropriate antibiotic use, including the prevalence of resistant organisms in paediatric LTC facilities, is critical. Copyright © 2017 The Healthcare Infection Society. Published by Elsevier Ltd. All rights reserved.

45 CFR 2490.150 - Program accessibility: Existing facilities.

Science.gov (United States)

2010-10-01

... 45 Public Welfare 4 2010-10-01 2010-10-01 false Program accessibility: Existing facilities. 2490.150 Section 2490.150 Public Welfare Regulations Relating to Public Welfare (Continued) JAMES MADISON... ACTIVITIES CONDUCTED BY THE JAMES MADISON MEMORIAL FELLOWSHIP FOUNDATION § 2490.150 Program accessibility...

Test program element II blanket and shield thermal-hydraulic and thermomechanical testing, experimental facility survey

Energy Technology Data Exchange (ETDEWEB)

Ware, A.G.; Longhurst, G.R.

1981-12-01

This report presents results of a survey conducted by EG and G Idaho to determine facilities available to conduct thermal-hydraulic and thermomechanical testing for the Department of Energy Office of Fusion Energy First Wall/Blanket/Shield Engineering Test Program. In response to EG and G queries, twelve organizations (in addition to EG and G and General Atomic) expressed interest in providing experimental facilities. A variety of methods of supplying heat is available.

Test program element II blanket and shield thermal-hydraulic and thermomechanical testing, experimental facility survey

International Nuclear Information System (INIS)

Ware, A.G.; Longhurst, G.R.

1981-12-01

This report presents results of a survey conducted by EG and G Idaho to determine facilities available to conduct thermal-hydraulic and thermomechanical testing for the Department of Energy Office of Fusion Energy First Wall/Blanket/Shield Engineering Test Program. In response to EG and G queries, twelve organizations (in addition to EG and G and General Atomic) expressed interest in providing experimental facilities. A variety of methods of supplying heat is available

Use of nuclear facilities at Argonne-West to support new environmental missions

International Nuclear Information System (INIS)

Black, D.B.; Dwight, C.C.; Lineberry, M.J.

1994-08-01

At Argonne National Laboratory-West, facilities that were originally constructed to support the development of liquid-metal reactor technology are being used to meet the environmental and waste management need of the US Department of Energy. These needs include waste characterization, waste testing, and waste treatment technology development. Waste characterization and repackaging activities are being performed in the Hot Fuel Examination Facility for the Waste Isolation Pilot Plant (WIPP) Experimental Test Program. Characterization activities include sampling the gas in actual waste containers, categorizing waste contents for their gas generation potential, and extracting solid samples. A new waste testing project will utilize the Zero Powered Physics Reactor facility. In the workroom of these facility, laboratory gas generation experiments will be conducted with contact-handled transuranic waste. Both the characterization and waste testing activities are part of the effort to prepare the WIPP performance assessment. Waste treatment demonstrations have or will be conducted at the Transient Reactor Test facility and involve private sector participants. The demonstrations involve the development of thermal treatment for materials containing residual amounts of plutonium using plasma-arc technology. The success of these new programs is largely due to experience gained from past missions in such areas as radiological control and nuclear safety

Economic analysis of a centralized LLRW storage facility in New York State

International Nuclear Information System (INIS)

Spath, J.P.; Voelk, H.; Brodie, H.

1994-01-01

In response to the possibility of no longer having access to out-of-State disposal facilities, the New York State Energy Research and Development Authority (Energy Authority) was directed by the New York State Legislature (1990-91 State Operation Budget Appropriations) to conduct a low-level radioactive waste (LLRW) storage study. One of the objectives of this study was to investigate the economic viability of establishing a separate Centralized Storage Facility for Class A LLRW from medical and academic institutions. This resulted in the conceptual design of a nominal Centralized Storage Facility capable of storing 100,000 cubic feet of dry-solid and liquid wastes and freezer storage capacity of 20,000 cubic feet for biological wastes. The facility itself includes office and laboratory space as well as receipt, inspection, and health physics monitoring stations. The Conceptual Design was initially developed to define the scope and detail of the cost parameters to be evaluated. It established a basis for conducting comparisons of the cost of four alternative project approaches and the sensitivity of unit storage costs to siting-related costs. In estimating costs of a Centralized Storage Facility, four cases were used varying assumptions with respect to parameters such as volume projections and freezer capacity; siting costs; and site acquisition costs

A Methodology for Base Camp Site Selection and Facility Layout

National Research Council Canada - National Science Library

Snyder, Frank

2002-01-01

..., and disaster relief missions throughout the world. To maintain a deployed force conducting such potentially lengthy operations, semi-permanent basecamps are required to provide the needed unit and soldier support facilities...

Conductive cooling of high-power RIB targets

International Nuclear Information System (INIS)

Talbert, W.L.; Drake, D.M.; Wilson, M.T.; Lenz, J.W.; Hsu, H.-H.

2002-01-01

A short review is presented of target cooling approaches suggested for targets irradiated by intense high-energy proton beams to produce radioactive species for use in a broad range of physics studies. This work reports on conductive cooling approaches for operation at temperatures lower than effective for radiative cooling. The possibilities for conductive cooling are discussed, and a prototype test target is described. This target was constructed for an experiment, designed to validate the numerical analysis approaches, at the TRIUMF/ISAC facility. Fabrication issues and the results of the experiment are presented, followed by a discussion of the implications of the experiment outcome for future development of targets to produce intense beams of radioactive ions

Determination of hydraulic conductivity coefficient in NSD site, Serpong, based on in-situ permeability test method

International Nuclear Information System (INIS)

Heri Syaeful; Sucipta

2013-01-01

In line with the increase of amount of radioactive waste, PTLR-BATAN plans to build the Near Surface Disposal (NSD) facility, especially in the preliminary stages is the Demo Plant of NSD facility. NSD is a low to medium level radioactive waste storage concept. Most important aspect in the site study for planning NSD is hydrogeological aspect especially related to the migration of radionuclides to the environment. In the study of radionuclide migration, a preliminary parameter which is required to know is the hydraulic conductivity in order to deliver the soil and rock hydraulic conductivity values in the site then conducted the in-situ permeability test. Based on the test, obtained soil and rock hydraulic conductivity values ranging from 10 -6 to 10 -2 cm/sec. The greatest hydraulic conductivity value located in the gravelly silt soil units which is in the site, constitute as aquifer, with depth ranging from 8 - 24 m, with hydraulic conductivity value reached 10 -2 cm/sec. (author)

An indoor air quality study of an alligator (Alligator mississippiensis) holding facility.

Science.gov (United States)

Wilson, S C; Holder, H W; Martin, J M; Brasel, T L; Andriychuk, L A; Wu, C; Straus, D C; Aguilar, R

2006-06-01

An environmental microbiologic investigation was conducted in an alligator (Alligator mississippiensis) holding facility in a zoo in the southeastern U.S. The facility had housed five alligators between March 1999 and February 2005. In the exhibit, one alligator died and all experienced poor health. It was hypothesized that environmental microbial contamination was associated with these issues. Samples were collected for fungal identification and quantification, microcystin analysis, and airborne mycotoxins. Analyses of air and water were conducted and an examination of the heating, ventilation, and air-conditioning system (HVAC) for design, maintenance, and operating issues was made. Two control sites, a facility for false gharials (Tomistoma schlegelii) and an off-site alligator breeding facility, were also tested. Morbidity and mortality records were examined for all sites. Results showed that, compared to the control sites, the test alligator facility and its HVAC system were extensively contaminated with a range of fungi. Nearly all sampled surfaces featured fungal growth. There were also significantly higher counts of Penicillium/Aspergillus-like and Chrysosporium-like spores in the air (P conditioned and mold-contaminated air being introduced to the facility. Morbidity records revealed solitary pulmonary disorders over time in three alligators, with one dying as a result. The other two alligators suffered from general malaise and a range of nonspecific symptoms. The control facilities had no morbidity or mortality issues. In conclusion, although no causal links could be demonstrated because of the nature of the morbidity data, environmental mold contamination appeared to be associated with the history of morbidity and mortality in the alligator exhibit.

Experimental Results Obtained with Air Liquide Cold Compression System CERN LHC and SNS Projects

CERN Document Server

Delcayre, F; Hamber, F; Hilbert, B; Monneret, E; Toia, J L

2006-01-01

Large scale collider facilities will make intensive use of superconducting magnets, operating below 2.0 K. This dictates high‐capacity refrigeration systems operating below 2.0 K. These systems, making use of cryogenic centrifugal compressors in a series arrangement with room temperature screw compressors will be coupled to a refrigerator, providing a certain power at 4.5 K. A first Air Liquide Cold Compression System (CCS) unit was built and delivered to CERN in 2001. Installed at the beginning of 2002, it was commissioned and tested successfully during year 2002. A series of four sets of identical CCS were then tested in 2004. Another set of four cryogenic centrifugal compressors (CCC) has been delivered to Thomas Jefferson National Accelerator Facility (JLAB) for the Spallation Neutron Source (SNS) in 2002. These compressors were tested and commissioned from December 2004 to July 2005. The experimental results obtained with these systems will be presented and discussed: the characteristics of the CCC wil...

SNS Diagnostics

International Nuclear Information System (INIS)

Shea, T.J.; Cameron, P.; Doolittle, L.; Power, J.

2000-01-01

The Spallation Neutron Source (SNS) Project is a collaborative effort to build the next generation neutron science facility at Oak Ridge, TN. The facility will deliver a 2 MW proton beam to a liquid mercury target. Neutrons from this target will be moderated and sent to several state-of-the-art instruments. Six national laboratories are involved in SNS construction. Berkeley (LBNL) will build the front end that produces a 2.5 MeV, 52 mA H-beam. Los Alamos (LANL) is responsible for the 1 GeV linac with a superconducting section provided by Thomas Jefferson (JLab). Brookhaven (BNL) is building the transfer lines and accumulator ring. Oak Ridge (ORNL) and Argonne (ANL) have responsibility for the target and instruments. All activities are coordinated by the SNS project office at Oak Ridge. The high beam power, a desired availability of 95%, and an aggressive commissioning schedule lead to some interesting challenges in beam diagnostics

QCD analysis of p-bar N->{gamma}*{pi} in the scaling limit

Energy Technology Data Exchange (ETDEWEB)

Pire, B. [CPhT, Ecole Polytechnique, F-91128 Palaiseau (France); Szymanowski, L. [Soltan Institute for Nuclear Studies, Warsaw (Poland) and Universite de Liege, B-4000 Liege (Belgium)]. E-mail: lech@nuclth02.phys.ulg.ac.be

2005-08-25

We study the scaling regime of nucleon-antinucleon annihilation into a deeply virtual photon and a meson, p-bar N->{gamma}*{pi}, in the forward kinematics, where vertical bar t vertical bar Q{sup 2}{approx}s. We obtain the leading twist amplitude in the kinematical region where it factorizes into an antiproton distribution amplitude, a short-distance matrix element related to nucleon form factor and the long-distance dominated transition distribution amplitudes which describe the nucleon to meson transition. We give the Q{sup 2} evolution equation for these transition distribution amplitudes. The scaling of the cross section of this process may be tested at the proposed GSI intense antiproton beam facility FAIR with the PANDA or PAX detectors. We comment on related processes such as {pi}N->N{sup '}{gamma}* and {gamma}*N->N{sup '}{pi} which may be experimentally studied at intense meson beams facilities and at JLab or Hermes, respectively.

Documented Safety Analysis for the Waste Storage Facilities March 2010

Energy Technology Data Exchange (ETDEWEB)

Laycak, D T

2010-03-05

This Documented Safety Analysis (DSA) for the Waste Storage Facilities was developed in accordance with 10 CFR 830, Subpart B, 'Safety Basis Requirements,' and utilizes the methodology outlined in DOE-STD-3009-94, Change Notice 3. The Waste Storage Facilities consist of Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area portion of the DWTF complex. These two areas are combined into a single DSA, as their functions as storage for radioactive and hazardous waste are essentially identical. The B695 Segment of DWTF is addressed under a separate DSA. This DSA provides a description of the Waste Storage Facilities and the operations conducted therein; identification of hazards; analyses of the hazards, including inventories, bounding releases, consequences, and conclusions; and programmatic elements that describe the current capacity for safe operations. The mission of the Waste Storage Facilities is to safely handle, store, and treat hazardous waste, transuranic (TRU) waste, low-level waste (LLW), mixed waste, combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL (as well as small amounts from other DOE facilities).

ART Attrition across Health Facilities Implementing Option B+ in Haiti.

Science.gov (United States)

Myrtil, Martine Pamphile; Puttkammer, Nancy; Gloyd, Stephen; Robinson, Julia; Yuhas, Krista; Domercant, Jean Wysler; Honoré, Jean Guy; Francois, Kesner

2018-01-01

Describing factors related to high attrition is important in order to improve the implementation of the Option B+ strategy in Haiti. We conducted a retrospective cohort study to describe the variability of antiretroviral therapy (ART) retention across health facilities among pregnant and lactating women and assess for differences in ART retention between Option B+ clients and other ART patients. There were 1989 Option B+ clients who initiated ART in 45 health facilities. The percentage of attrition varied from 9% to 81% across the facilities. The largest health facilities had 38% higher risk of attrition (relative risk [RR]: 1.38, 95% confidence interval [CI]: 1.08-1.77, P = .009). Private institutions had 18% less risk of attrition (RR: 0.82, 95% CI: 0.70-0.96, P = .020). Health facilities located in the West department and the South region had lower risk of attrition. Being on treatment in a large or public health facility or a facility located in the North region was a significant risk factor associated with high attrition among Option B+ clients. The implementation of the Option B+ strategy must be reevaluated in order to effectively eliminate mother-to-child HIV transmission.

A qualitative analysis of facilities maintenance - a school governance function in South Africa

Directory of Open Access Journals (Sweden)

M I Xaba

2012-01-01

Full Text Available I analysed school facilities maintenance, a school governance function in South Africa. Qualitative interviews were conducted with 13 principals and three deputy principals as coordinators of this function at their schools. The interviews were purposively and conveniently selected to gather data regarding school facilities maintenance and gain insight into the challenges this function presents to schools and their governing bodies. Findings indicate that schools generally do not have organisational structures for planned facilities maintenance, nor do they have policies on facilities maintenance. Evidence of facilities maintenance at schools mainly relates to concerns with facilities repairs, (mostly "as the need arises" and general campus cleanliness; mostly with emergency and corrective forms of maintenance as opposed to crucial preventive maintenance. Therefore, there is a need for interim facilities maintenance committees and, in the long term, a whole-school approach to facilities maintenance that makes facilities maintenance a strategic lever for school functionality.

Safety assessment for facilities and activities. General safety requirements. Pt. 4

International Nuclear Information System (INIS)

2009-01-01

The Safety Fundamentals publication, Fundamental Safety Principles, establishes principles for ensuring the protection of workers, the public and the environment, now and in the future, from harmful effects of ionizing radiation. The objective of this Safety Requirements publication is to establish the generally applicable requirements to be fulfilled in safety assessment for facilities and activities, with special attention paid to defence in depth, quantitative analyses and the application of a graded approach to the ranges of facilities and of activities that are addressed. The publication also addresses the independent verification of the safety assessment that needs to be carried out by the originators and users of the safety assessment. This publication is intended to provide a consistent and coherent basis for safety assessment across all facilities and activities, which will facilitate the transfer of good practices between organizations conducting safety assessments and will assist in enhancing the confidence of all interested parties that an adequate level of safety has been achieved for facilities and activities. The requirements, which are derived from the Fundamental Safety Principles, relate to any human activity that may cause people to be exposed to radiation risks arising from facilities and activities, as follows: Facilities includes: (a) Nuclear power plants; (b) Other reactors (such as research reactors and critical assemblies); (c) Enrichment facilities and fuel fabrication facilities; (d) Conversion facilities used to generate UF 6 ; (e) Storage and reprocessing plants for irradiated fuel; (f) Facilities for radioactive waste management where radioactive waste is treated, conditioned, stored or disposed of; (g) Any other places where radioactive materials are produced, processed, used, handled or stored; (h) Irradiation facilities for medical, industrial, research and other purposes, and any places where radiation generators are installed; (i

Safety Assessment for Facilities and Activities. General Safety Requirements. Pt. 4

International Nuclear Information System (INIS)

2009-01-01

The Safety Fundamentals publication, Fundamental Safety Principles, establishes principles for ensuring the protection of workers, the public and the environment, now and in the future, from harmful effects of ionizing radiation. The objective of this Safety Requirements publication is to establish the generally applicable requirements to be fulfilled in safety assessment for facilities and activities, with special attention paid to defence in depth, quantitative analyses and the application of a graded approach to the ranges of facilities and of activities that are addressed. The publication also addresses the independent verification of the safety assessment that needs to be carried out by the originators and users of the safety assessment. This publication is intended to provide a consistent and coherent basis for safety assessment across all facilities and activities, which will facilitate the transfer of good practices between organizations conducting safety assessments and will assist in enhancing the confidence of all interested parties that an adequate level of safety has been achieved for facilities and activities. The requirements, which are derived from the Fundamental Safety Principles, relate to any human activity that may cause people to be exposed to radiation risks arising from facilities and activities, as follows: Facilities includes: (a) Nuclear power plants; (b) Other reactors (such as research reactors and critical assemblies); (c) Enrichment facilities and fuel fabrication facilities; (d) Conversion facilities used to generate UF6; (e) Storage and reprocessing plants for irradiated fuel; (f) Facilities for radioactive waste management where radioactive waste is treated, conditioned, stored or disposed of; (g) Any other places where radioactive materials are produced, processed, used, handled or stored; (h) Irradiation facilities for medical, industrial, research and other purposes, and any places where radiation generators are installed; (i

Safety Assessment for Facilities and Activities. General Safety Requirements. Pt. 4

International Nuclear Information System (INIS)

2010-01-01

The Safety Fundamentals publication, Fundamental Safety Principles, establishes principles for ensuring the protection of workers, the public and the environment, now and in the future, from harmful effects of ionizing radiation. The objective of this Safety Requirements publication is to establish the generally applicable requirements to be fulfilled in safety assessment for facilities and activities, with special attention paid to defence in depth, quantitative analyses and the application of a graded approach to the ranges of facilities and of activities that are addressed. The publication also addresses the independent verification of the safety assessment that needs to be carried out by the originators and users of the safety assessment. This publication is intended to provide a consistent and coherent basis for safety assessment across all facilities and activities, which will facilitate the transfer of good practices between organizations conducting safety assessments and will assist in enhancing the confidence of all interested parties that an adequate level of safety has been achieved for facilities and activities. The requirements, which are derived from the Fundamental Safety Principles, relate to any human activity that may cause people to be exposed to radiation risks arising from facilities and activities, as follows: Facilities includes: (a) Nuclear power plants; (b) Other reactors (such as research reactors and critical assemblies); (c) Enrichment facilities and fuel fabrication facilities; (d) Conversion facilities used to generate UF6; (e) Storage and reprocessing plants for irradiated fuel; (f) Facilities for radioactive waste management where radioactive waste is treated, conditioned, stored or disposed of; (g) Any other places where radioactive materials are produced, processed, used, handled or stored; (h) Irradiation facilities for medical, industrial, research and other purposes, and any places where radiation generators are installed; (i

Safety Assessment for Facilities and Activities. General Safety Requirements. Pt. 4

International Nuclear Information System (INIS)

2009-01-01

The Safety Fundamentals publication, Fundamental Safety Principles, establishes principles for ensuring the protection of workers, the public and the environment, now and in the future, from harmful effects of ionizing radiation.? read more The objective of this Safety Requirements publication is to establish the generally applicable requirements to be fulfilled in safety assessment for facilities and activities, with special attention paid to defence in depth, quantitative analyses and the application of a graded approach to the ranges of facilities and of activities that are addressed. The publication also addresses the independent verification of the safety assessment that needs to be carried out by the originators and users of the safety assessment. This publication is intended to provide a consistent and coherent basis for safety assessment across all facilities and activities, which will facilitate the transfer of good practices between organizations conducting safety assessments and will assist in enhancing the confidence of all interested parties that an adequate level of safety has been achieved for facilities and activities. The requirements, which are derived from the Fundamental Safety Principles, relate to any human activity that may cause people to be exposed to radiation risks arising from facilities and activities, as follows: Facilities includes: (a) Nuclear power plants; (b) Other reactors (such as research reactors and critical assemblies); (c) Enrichment facilities and fuel fabrication facilities; (d) Conversion facilities used to generate UF6; (e) Storage and reprocessing plants for irradiated fuel; (f) Facilities for radioactive waste management where radioactive waste is treated, conditioned, stored or disposed of; (g) Any other places where radioactive materials are produced, processed, used, handled or stored; (h) Irradiation facilities for medical, industrial, research and other purposes, and any places where radiation generators are

42 CFR 90.7 - Decision to conduct health effects study.

Science.gov (United States)

2010-10-01

... occurred, and any possible health effects resulting from such exposure. (b) Should ATSDR decide, in its... 42 Public Health 1 2010-10-01 2010-10-01 false Decision to conduct health effects study. 90.7... ASSESSMENTS AND HEALTH EFFECTS STUDIES OF HAZARDOUS SUBSTANCES RELEASES AND FACILITIES ADMINISTRATIVE...

Analyze the Air Force Methods for Facility Sustainment and Restoration

National Research Council Canada - National Science Library

Cole, Ronald

2003-01-01

...) and try to capitalize on industry standard practices to improve the AF methods. Industry has conducted extensive research devoted to the development of predictive models to estimate facility maintenance or sustainment requirements...

Strategic planning and marketing research for older, inner-city health care facilities: a case study.

Science.gov (United States)

Wood, V R; Robertson, K R

1992-01-01

Numerous health care facilities, located in downtown metropolitan areas, now find themselves surrounded by a decaying inner-city environment. Consumers may perceive these facilities as "old," and catering to an "urban poor" consumer. These same consumers may, therefore, prefer to patronize more modern facilities located in suburban areas. This paper presents a case study of such a health care facility and how strategic planning and marketing research were conducted in order to identify market opportunities and new strategic directions.

5 CFR 1636.150 - Program accessibility: Existing facilities.

Science.gov (United States)

2010-01-01

... fundamental alteration in the nature of a program or activity or in undue financial and administrative burdens... facilities. 1636.150 Section 1636.150 Administrative Personnel FEDERAL RETIREMENT THRIFT INVESTMENT BOARD ENFORCEMENT OF NONDISCRIMINATION ON THE BASIS OF HANDICAP IN PROGRAMS OR ACTIVITIES CONDUCTED BY THE FEDERAL...

49 CFR 28.150 - Program accessibility: Existing facilities.

Science.gov (United States)

2010-10-01

... 49 Transportation 1 2010-10-01 2010-10-01 false Program accessibility: Existing facilities. 28.150 Section 28.150 Transportation Office of the Secretary of Transportation ENFORCEMENT OF NONDISCRIMINATION ON THE BASIS OF HANDICAP IN PROGRAMS OR ACTIVITIES CONDUCTED BY THE DEPARTMENT OF TRANSPORTATION § 28...

Performance assessment for a hypothetical low-level waste disposal facility

International Nuclear Information System (INIS)

Smith, C.S.; Rohe, M.J.; Ritter, P.D.

1997-01-01

Disposing of low-level waste (LLW) is a concern for many states throughout the United States. A common disposal method is below-grade concrete vaults. Performance assessment analyses make predictions of contaminant release, transport, ingestion, inhalation, or other routes of exposure, and the resulting doses for various disposal methods such as the below-grade concrete vaults. Numerous assumptions are required to simplify the processes associated with the disposal facility to make predictions feasible. In general, these assumptions are made conservatively so as to underestimate the performance of the facility. The objective of this report is to describe the methodology used in conducting a performance assessment for a hypothetical waste facility located in the northeastern United States using real data as much as possible. This report consists of the following: (a) a description of the disposal facility and site, (b) methods used to analyze performance of the facility, (c) the results of the analysis, and (d) the conclusions of this study

Performance assessment for a hypothetical low-level waste disposal facility

Energy Technology Data Exchange (ETDEWEB)

Smith, C.S.; Rohe, M.J.; Ritter, P.D. [and others

1997-01-01

Disposing of low-level waste (LLW) is a concern for many states throughout the United States. A common disposal method is below-grade concrete vaults. Performance assessment analyses make predictions of contaminant release, transport, ingestion, inhalation, or other routes of exposure, and the resulting doses for various disposal methods such as the below-grade concrete vaults. Numerous assumptions are required to simplify the processes associated with the disposal facility to make predictions feasible. In general, these assumptions are made conservatively so as to underestimate the performance of the facility. The objective of this report is to describe the methodology used in conducting a performance assessment for a hypothetical waste facility located in the northeastern United States using real data as much as possible. This report consists of the following: (a) a description of the disposal facility and site, (b) methods used to analyze performance of the facility, (c) the results of the analysis, and (d) the conclusions of this study.

Massachusetts Large Blade Test Facility Final Report

Energy Technology Data Exchange (ETDEWEB)

Rahul Yarala; Rob Priore

2011-09-02

Project Objective: The Massachusetts Clean Energy Center (CEC) will design, construct, and ultimately have responsibility for the operation of the Large Wind Turbine Blade Test Facility, which is an advanced blade testing facility capable of testing wind turbine blades up to at least 90 meters in length on three test stands. Background: Wind turbine blade testing is required to meet international design standards, and is a critical factor in maintaining high levels of reliability and mitigating the technical and financial risk of deploying massproduced wind turbine models. Testing is also needed to identify specific blade design issues that may contribute to reduced wind turbine reliability and performance. Testing is also required to optimize aerodynamics, structural performance, encourage new technologies and materials development making wind even more competitive. The objective of this project is to accelerate the design and construction of a large wind blade testing facility capable of testing blades with minimum queue times at a reasonable cost. This testing facility will encourage and provide the opportunity for the U.S wind industry to conduct more rigorous testing of blades to improve wind turbine reliability.

Standard protocol for demographic and epidemiological survey to be carried out for nuclear facilities

International Nuclear Information System (INIS)

Joshi, M.L.; Datta, D.; Singh, Jitendra; Sardhi, I.V.; Verma, P.C.

2007-11-01

This document presents the standard procedures for conducting demographic and epidemiological studies for nuclear facilities. These studies are required to be carried out to prepare baseline data, the impact of the facility and the risk factors for the population residing in the vicinity of facility. This document includes the basic elements of these type surveys, their methodology and statistical analysis of the data collected during demographic and epidemiological surveillance. (author)

Standard protocol for demographic and epidemiological survey to be carried out for nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Joshi, M L; Datta, D; Singh, Jitendra; Sardhi, I V; Verma, P C [Health Physics Division, Bhabha Atomic Research Centre, Mumbai (India)

2007-11-15

This document presents the standard procedures for conducting demographic and epidemiological studies for nuclear facilities. These studies are required to be carried out to prepare baseline data, the impact of the facility and the risk factors for the population residing in the vicinity of facility. This document includes the basic elements of these type surveys, their methodology and statistical analysis of the data collected during demographic and epidemiological surveillance. (author)

The CLAS12 Torus Detector Magnet at Jefferson Laboratory

Energy Technology Data Exchange (ETDEWEB)

Luongo, Cesar [Jefferson Lab; Ballard, Joshua [Jefferson Lab; Biallas, George [Jefferson Lab; Elouadrhiri, Latifa [Jefferson Lab; Fair, Ruben [Jefferson Lab; Ghoshal, Probir [Jefferson Lab; Kashy, Dave [Jefferson Lab; Legg, Robert [Jefferson Lab; Pastor, Orlando [Jefferson Lab; Rajput-Ghoshal, Renuka [Jefferson Lab; Rode, Claus [Jefferson Lab; Wiseman, Mark [Jefferson Lab; Young, Glenn [Jefferson Lab; Elementi, Luciano [Fermilab; Krave, Steven [Fermilab; Makarov, Alexander [Fermilab; Nobrega, Fred [Fermilab; Velev, George [Fermilab

2015-12-17

The CLAS12 Torus is a toroidal superconducting magnet, which is part of the detector for the 12-GeV accelerator upgrade at Jefferson Laboratory (JLab). The coils were wound/fabricated by Fermilab, with JLab responsible for all other parts of the project scope, including design, integration, cryostating the individual coils, installation, cryogenics, I&C, etc. This paper provides an overview of the CLAS12 Torus magnet features and serves as a status report of its installation in the experimental hall. Completion and commissioning of the magnet is expected in 2016.

White Mountain Research Station: 25 years of high-altitude research. [organization and functions of test facility for high altitude research

Science.gov (United States)

Pace, N.

1973-01-01

The organization and functions of a test facility for conducting research projects at high altitudes are discussed. The projects conducted at the facility include the following: (1) bird physiology, (2) cardiorespiratory physiology, (3) endocrinological studies, (4) neurological studies, (5) metabolic studies, and (6) geological studies.

Exploring Psychological and Aesthetic Approaches of Bio-Retention Facilities in the Urban Open Space

Directory of Open Access Journals (Sweden)

Suyeon Kim

2017-11-01

Full Text Available Over the last decades, a number of bio-retention facilities have been installed in urban areas for flood control and green amenity purposes. As urban amenity facilities for citizens, bio-retentions have a lot potential; however, the literature on bio-retentions focused mostly on physiochemical aspects like water quality and runoffs. Hence, this paper aims to explore psychological aspects of bio-retentions such as perceptions and landscape aesthetic value for visitors. In order to achieve this purpose, the study employed on-site interviews and questionnaires in the chosen three case studies as research methodology. For the 3 different locations of bio-retention facilities, interviews and questionnaires were carried out. The surveys of 100 bio-retention users were conducted, investigating their general perceptions and landscape aesthetics of the bio-retention facilities. The paper found that only 34% of the interviewees recognised bio-detention facilities, illustrating that most visitors were not aware of such facilities and were unable to distinguish the differences between bio-retention and conventional gardens. On the other hand, the majority of interviewees strongly supported the concept and function of bio-retentions, especially those who recognised the differences in planting species with conventional urban open spaces. Such main findings also encourage further studies of seeking quantitative values by conducting a correlation analysis between the functions and aesthetics of bio-retention facilities.

Sampling and Analysis Plan for the 221-U Facility

International Nuclear Information System (INIS)

Rugg, J.E.

1998-02-01

This sampling and analysis plan (SAP) presents the rationale and strategy for the sampling and analysis activities proposed to be conducted to support the evaluation of alternatives for the final disposition of the 221-U Facility. This SAP will describe general sample locations and the minimum number of samples required. It will also identify the specific contaminants of potential concern (COPCs) and the required analysis. This SAP does not define the exact sample locations and equipment to be used in the field due to the nature of unknowns associated with the 221-U Facility

Overview of high intensity proton accelerator facility, J-PARC

International Nuclear Information System (INIS)

Ikeda, Y.

2010-01-01

The J-PARC project of high intensity proton accelerator research complex, conducted jointly by JAERI and KEK, has been completed with demonstration of all beam productions in 2009 as the facility construction phase, and the operation started to offer the secondary beams of neutron, muon, kaon, and neutrino, to the advanced scientific experimental research aiming at making breakthroughs in materials and life science, nuclear and elementary physics, etc. This text describes the overview of the J-PARC present status with emphasis of a performance toward to 1MW power as user facilities. (author)

Building Excellence: How Helping Charters Access Facilities Can Improve Opportunity for Idaho Kids

Science.gov (United States)

Robson, Kelly; Squire, Juliet

2016-01-01

To better understand charter leaders' experiences acquiring facilities, the authors conducted a survey of all charter school leaders in the state of Idaho. The leaders of 26 brick-and-mortar charter schools responded, representing 65 percent of all such charter schools in the state. The survey gathered a number of facilities-related data points,…

Hydraulic conductivity of some bentonites in artificial seawater

International Nuclear Information System (INIS)

Komine, Hideo; Murakami, Satoshi; Yasuhara, Kazuya

2011-01-01

A high-level radioactive waste disposal facility might be built in a coastal area in Japan from the viewpoint of feasible transportation of waste. Therefore, it is important to investigate the effects of seawater on a bentonite-based buffer. This study investigated the influence of seawater on hydraulic conductivity of three common sodium-types of bentonite and one calcium-type bentonite by the laboratory experiments. >From the results of laboratory experiment, this study discussed the influence of seawater on hydraulic conductivity of bentonites from the viewpoints of kinds of bentonite such as exchangeable-cation type and montmorillonite content and dry density of bentonite-based buffer. (author)

3718-F Alkali Metal Treatment and Storage Facility Closure Plan. Revision 1

Energy Technology Data Exchange (ETDEWEB)

None

1992-11-01

The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, as well as for activities associated with nuclear energy development. The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. The 3718-F Alkali Metal Treatment and Storage Facility (3718-F Facility), located in the 300 Area, was used to store and treat alkali metal wastes. Therefore, it is subject to the regulatory requirements for the storage and treatment of dangerous wastes. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610 (Ecology 1989) and 40 CFR 270.1. Closure also will satisfy the thermal treatment facility closure requirements of 40 CFR 265.381. This closure plan presents a description of the 3718-F Facility, the history of wastes managed, and the approach that will be followed to close the facility. Only hazardous constituents derived from 3718-F Facility operations will be addressed.

Pentaquark Searches at Jlab

Energy Technology Data Exchange (ETDEWEB)

Rossi, Patrizia

2007-01-01

Since LEPS collaboration reported the first evidence for a S=+1 baryon resonance in early 2003 with a mass of 1.54 GeV, dubbed Θ+, more than ten experiments have confirmed this exotic state, among these two carried out at Jefferson Laboratory. At the same time, there are a number of experiments, mostly at high energies, that report null results. To try to clarify this situation, during the past year, The CLAS Collaboration at Jefferson Laboratory has undertaken a second generation high-statistics experimental program to search for exotics baryons. Here the preliminary results from these experiments are reported.

Pentaquark Searches at JLab

International Nuclear Information System (INIS)

Rossi, P.

2007-01-01

Since LEPS collaboration reported the first evidence for a S=+1 baryon resonance in early 2003 with a mass of 1.54 GeV, dubbed Θ + , more than ten experiments have confirmed this exotic state, among these two carried out at Jefferson Laboratory. At the same time, there are a number of experiments, mostly at high energies, that report null results. To try to clarify this situation, during the past year, The CLAS Collaboration at Jefferson Laboratory has undertaken a second generation high-statistics experimental program to search for exotics baryons. Here the preliminary results from these experiments are reported

The proposed irradiation facility and applications

International Nuclear Information System (INIS)

Singson, C.C.; Navarro, Q.O.

As early as 1972, the Philippine Atomic Energy Commission proposed the setting up of a radiation facility for the sterilization of medical products. A result of a market survey with the assistance of an IAEA expert was conducted to determine the market potential for such venture. With the Food Terminal, Inc. (FTI) a government agro-industrial fair which explored the economic benefits of project, encouraging results have been obtained with finances from FAO and IAEA. The proposed pilot plant will serve as a multi purpose facility for the sterilization of medical and laboratory products, irradiation of food and agricultural produce and manufacture of wood plastic compositions for the textile and furniture industries. With the benefits derived from the said project, it is hoped that its early installation be pushed through. (author)

Analysis of factors related to man-induced hazard for nuclear facilities

International Nuclear Information System (INIS)

Lee, Young Soon; Jung, Jea Hee; Lee, Keun O; Son, Ki Sang; Wang, Sang Chul; Lee, Chang Jin; Ku, Min Ho; Park, Nam Young

2003-03-01

This study is to show a guide for installing hazardous facilities adjoined atomic power plant after finding out how much these facilities could impact to the atomic plant. Nuclear power plant is an important facility which is closely connected with public life, industrial activity, and the conduct of public business, so it should not be damaged. Therefore, if there are hazardous and harmful facilities near the plant, then they must be evaluated by the size, the type, and the shape. First of all, any factors that could cause man induced accident must be investigated. And they must be exactly evaluated from how much it will damage the plant facilities. The purpose of this study is to set a technical standard for the installation of these facilities by evaluating the man induced accident. Also, it is to make out the evaluation methods by investigating the hazardous facilities which are placed near the plant. Our country is now using CFR standard : reg. guide and IAEA safety series. However, not only the standard of technology which is related to man induced accident but also the evaluation methods for facilities are not yet layed down. As It was mentioned above, we should evaluate these facilities adequately, and these methods must be made out

Analysis of factors related to man-induced hazard for nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Lee, Young Soon; Jung, Jea Hee; Lee, Keun O; Son, Ki Sang; Wang, Sang Chul; Lee, Chang Jin; Ku, Min Ho; Park, Nam Young [Seoul National Univ. of Technology, Seoul (Korea, Republic of)

2003-03-15

This study is to show a guide for installing hazardous facilities adjoined atomic power plant after finding out how much these facilities could impact to the atomic plant. Nuclear power plant is an important facility which is closely connected with public life, industrial activity, and the conduct of public business, so it should not be damaged. Therefore, if there are hazardous and harmful facilities near the plant, then they must be evaluated by the size, the type, and the shape. First of all, any factors that could cause man induced accident must be investigated. And they must be exactly evaluated from how much it will damage the plant facilities. The purpose of this study is to set a technical standard for the installation of these facilities by evaluating the man induced accident. Also, it is to make out the evaluation methods by investigating the hazardous facilities which are placed near the plant. Our country is now using CFR standard : reg. guide and IAEA safety series. However, not only the standard of technology which is related to man induced accident but also the evaluation methods for facilities are not yet layed down. As It was mentioned above, we should evaluate these facilities adequately, and these methods must be made out.

Dance Facilities.

Science.gov (United States)

Ashton, Dudley, Ed.; Irey, Charlotte, Ed.

This booklet represents an effort to assist teachers and administrators in the professional planning of dance facilities and equipment. Three chapters present the history of dance facilities, provide recommended dance facilities and equipment, and offer some adaptations of dance facilities and equipment, for elementary, secondary and college level…

Facilities inventory protection for nuclear facilities

International Nuclear Information System (INIS)

Schmitt, F.J.

1989-01-01

The fact that shut-down applications have been filed for nuclear power plants, suggests to have a scrutinizing look at the scopes of assessment and decision available to administrations and courts for the protection of facilities inventories relative to legal and constitutional requirements. The paper outlines the legal bases which need to be observed if purposeful calculation is to be ensured. Based on the different actual conditions and legal consequences, the author distinguishes between 1) the legal situation of facilities licenced already and 2) the legal situation of facilities under planning during the licencing stage. As indicated by the contents and restrictions of the pertinent provisions of the Atomic Energy Act and by the corresponding compensatory regulation, the object of the protection of facilities inventor in the legal position of the facility owner within the purview of the Atomic Energy Act, and the licensing proper. Art. 17 of the Atomic Energy Act indicates the legislators intent that, once issued, the licence will be the pivotal point for regulations aiming at protection and intervention. (orig./HSCH) [de

105-DR Large Sodium Fire Facility closure plan

International Nuclear Information System (INIS)

1993-05-01

The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, and activities associated with nuclear energy development. The 105-DR Large Sodium Fire Facility (LSFF), which was in operation from about 1972 to 1986, was a research laboratory that occupied the former ventilation supply room on the southwest side of the 105-DR Reactor facility. The LSFF was established to provide a means of investigating fire and safety aspects associated with large sodium or other metal alkali fires in the liquid metal fast breeder reactor (LMFBR) facilities. The 105-DR Reactor facility was designed and built in the 1950's and is located in the 100-D Area of the Hanford Site. The building housed the 105-DR defense reactor, which was shut down in 1964. The LSFF was initially used only for engineering-scale alkali metal reaction studies. In addition, the Fusion Safety Support Studies program sponsored intermediate-size safety reaction tests in the LSFF with lithium and lithium lead compounds. The facility has also been used to store and treat alkali metal waste, therefore the LSFF is subject to the regulatory requirements for the storage and treatment of dangerous waste. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610. This closure plan presents a description of the facility, the history of waste managed, and the procedures that will be followed to close the LSFF as an Alkali Metal Treatment Facility. No future use of the LSFF is expected

Combustion Dynamics Facility: April 1990 workshop working group reports

Energy Technology Data Exchange (ETDEWEB)

Kung, A.H.; Lee, Y.T.

1990-04-01

This document summarizes results from a workshop held April 5--7, 1990, on the proposed Combustion Dynamics Facility (CDF). The workshop was hosted by the Lawrence Berkeley Laboratory (LBL) and Sandia National Laboratories (SNL) to provide an opportunity for potential users to learn about the proposed experimental and computational facilities, to discuss the science that could be conducted with such facilities, and to offer suggestions as to how the specifications and design of the proposed facilities might be further refined to address the most visionary scientific opportunities. Some 130 chemical physicists, combustion chemists, and specialists in UV synchrotron radiation sources and free-electron lasers (more than half of whom were from institutions other than LBL and SNL) attended the five plenary sessions and participated in one or more of the nine parallel working group sessions. Seven of these sessions were devoted to broadening and strengthening the scope of CDF scientific opportunities and to detail the experimental facilities required to realize these opportunities. Two technical working group sessions addressed the design and proposed performance of two of the major CDF experimental facilities. These working groups and their chairpersons are listed below. A full listing of the attendees of the workshop is given in Appendix A. 1 tab.

12 CFR 410.150 - Program accessibility: Existing facilities.

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 4 2010-01-01 2010-01-01 false Program accessibility: Existing facilities. 410.150 Section 410.150 Banks and Banking EXPORT-IMPORT BANK OF THE UNITED STATES ENFORCEMENT OF NONDISCRIMINATION ON THE BASIS OF HANDICAP IN PROGRAMS OR ACTIVITIES CONDUCTED BY EXPORT-IMPORT BANK OF THE UNITED...

Highly Conductive and Reliable Copper-Filled Isotropically Conductive Adhesives Using Organic Acids for Oxidation Prevention

Science.gov (United States)

Chen, Wenjun; Deng, Dunying; Cheng, Yuanrong; Xiao, Fei

2015-07-01

The easy oxidation of copper is one critical obstacle to high-performance copper-filled isotropically conductive adhesives (ICAs). In this paper, a facile method to prepare highly reliable, highly conductive, and low-cost ICAs is reported. The copper fillers were treated by organic acids for oxidation prevention. Compared with ICA filled with untreated copper flakes, the ICA filled with copper flakes treated by different organic acids exhibited much lower bulk resistivity. The lowest bulk resistivity achieved was 4.5 × 10-5 Ω cm, which is comparable to that of commercially available Ag-filled ICA. After 500 h of 85°C/85% relative humidity (RH) aging, the treated ICAs showed quite stable bulk resistivity and relatively stable contact resistance. Through analyzing the results of x-ray diffraction, x-ray photoelectron spectroscopy, and thermogravimetric analysis, we found that, with the assistance of organic acids, the treated copper flakes exhibited resistance to oxidation, thus guaranteeing good performance.

Mapping the Characteristics of Critical Care Facilities: Assessment, Distribution, and Level of Critical Care Facilities from Central India.

Science.gov (United States)

Saigal, Saurabh; Sharma, Jai Prakash; Pakhare, Abhijit; Bhaskar, Santosh; Dhanuka, Sanjay; Kumar, Sanjay; Sabde, Yogesh; Bhattacharya, Pradip; Joshi, Rajnish

2017-10-01

In low- and middle-income countries such as India, where health systems are weak, the number of available Critical Care Unit (Intensive Care Unit [ICU]) beds is expected to be low. There is no study from the Indian subcontinent that has reported the characteristics and distribution of existing ICUs. We performed this study to understand the characteristics and distribution of ICUs in Madhya Pradesh (MP) state of Central India. We also aimed to develop a consensus scoring system and internally validate it to define levels of care and to improve health system planning and to strengthen referral networks in the state. We obtained a list of potential ICU facilities from various sources and then performed a cross-sectional survey by visiting each facility and determining characteristics for each facility. We collected variables with respect to infrastructure, human resources, equipment, support services, procedures performed, training courses conducted, and in-place policies or standard operating procedure documents. We identified a total of 123 ICUs in MP. Of 123 ICUs, 35 were level 1 facilities, 74 were level 2 facilities, and only 14 were level 3 facilities. Overall, there were 0.17 facilities per 100,000 population (95* confidence interval [CI] 0.14-0.20 per 100,000 populations). There were a total of 1816 ICU beds in the state, with an average of 2.5 beds per 100,000 population (95* CI 2.4-2.6 per 100,000 population). Of the total number of ICU beds, 250 are in level 1, 1141 are in level 2, and 425 are in level 3 facilities. This amounts to 0.34, 1.57, and 0.59 ICU beds per 100,000 population for levels 1, 2, and 3, respectively. This study could just be an eye opener for our healthcare authorities at both state and national levels to estimate the proportion of ICU beds per lac population. Similar mapping of intensive care services from other States will generate national data that is hitherto unknown.

The Impact of Pollution Prevention on Toxic Environmental Releases from U.S. Manufacturing Facilities.

Science.gov (United States)

Ranson, Matthew; Cox, Brendan; Keenan, Cheryl; Teitelbaum, Daniel

2015-11-03

Between 1991 and 2012, the facilities that reported to the U.S. Environmental Protection Agency's Toxic Release Inventory (TRI) Program conducted 370,000 source reduction projects. We use this data set to conduct the first quasi-experimental retrospective evaluation of how implementing a source reduction (pollution prevention) project affects the quantity of toxic chemicals released to the environment by an average industrial facility. We use a differences-in-differences methodology, which measures how implementing a source reduction project affects a facility's releases of targeted chemicals, relative to releases of (a) other untargeted chemicals from the same facility, or (b) the same chemical from other facilities in the same industry. We find that the average source reduction project causes a 9-16% decrease in releases of targeted chemicals in the year of implementation. Source reduction techniques vary in effectiveness: for example, raw material modification causes a large decrease in releases, while inventory control has no detectable effect. Our analysis suggests that in aggregate, the source reduction projects carried out in the U.S. since 1991 have prevented between 5 and 14 billion pounds of toxic releases.

Work control in separations facilities

International Nuclear Information System (INIS)

Olson, L.D.

1990-01-01

The topic addressed in this technical review is the development and implementation of a work control program in one of the chemical separations facilities at the Savannah River Site (SRS) in Aiken, SC. This program will be used as a pilot for the Nuclear Materials Processing Division at the site. The SRS Work Control Pilot program is based on the Institute of Nuclear Power Operations (INPO) good practices and guidelines for the conduct of maintenance and complies with SRS quality assurance and DOE orders on maintenance management. The program follows a ten-step process for control of maintenance and maintenance-related activities in a chemical separations facility. The program took the existing maintenance planning and scheduling system and upgraded it to comply with all INPO work control and related guidelines for histories, post-maintenance testing and scheduling. The development process of adapting a nuclear-related- based plan to a batch/continuous chemical separations plant was a challenge. There were many opportunities to develop improvements in performance while being creative and realistic in applying reactor maintenance technology to chemical plant maintenance. This pilot program for work control in a nonreactor nuclear facility will provide valuable information for applying a controlled maintenance process to a multiphase chemical operating plant environment

EMAT Evaluation of Thin Conductive Sheets

Directory of Open Access Journals (Sweden)

Ivo Cap

2006-01-01

Full Text Available At present a non-destructive testing of conducting materials becomes very important one in connection with monitoring and control of strategic technical facilities, e.g. nuclear power plants. There are more methods of material testing and evaluation and every of them has its advantages and disadvantages. Recently the electromagnetic methods are in increasing interest. There are many ways of conducting material testing. One of them often used utilises investigation of eddy currents induced in the surface layer by means of a proper coil. The arrangement is very simple and inexpensive but it offers only local information on cracks and other inhomogeneities in the thin surface layer. On the other hand there exist a method based on an electromagnetic – acoustic transducer (EMAT, which is able to generate and detect acoustic wave in a conducting body in a contact-less way. The present paper deals with a survey of EMATs for investigation of thin metalliclayers by means of Lamb waves. The new design of generation coil is presented.

Hanford Site near-facility environmental monitoring data report for calendar year 1998

Energy Technology Data Exchange (ETDEWEB)

DIEDIKER, L.P.

1999-07-29

This document summarizes the results of the U.S. Department of Energy's Near-Facility Environmental Monitoring program conducted by Waste Management Federal Services of Hanford, Inc. for Fluor Daniel Hanford, Inc. for 1998 in the 100,200/600, and 300/400 Areas of the Hanford Site, in southcentral Washington State. Surveillance activities included sampling and analyses of ambient air, surface water, groundwater, soil, sediments, and biota. Also, external radiation measurements and radiological surveys were taken at waste disposal sites, radiologically controlled areas, and roads. These activities were conducted to assess and control the effects of nuclear facilities and waste sites on the local environment. In addition, diffuse sources were monitored to determine compliance with federal, state, and/or local regulations. In general, although effects from nuclear facilities can still be observed on the Hanford Site and radiation levels are slightly elevated when compared to offsite locations, the differences are less than in previous years.

Hanford Site near-facility environmental monitoring data report for calendar year 1998

International Nuclear Information System (INIS)

DIEDIKER, L.P.

1999-01-01

This document summarizes the results of the U.S. Department of Energy's Near-Facility Environmental Monitoring program conducted by Waste Management Federal Services of Hanford, Inc. for Fluor Daniel Hanford, Inc. for 1998 in the 100,200/600, and 300/400 Areas of the Hanford Site, in southcentral Washington State. Surveillance activities included sampling and analyses of ambient air, surface water, groundwater, soil, sediments, and biota. Also, external radiation measurements and radiological surveys were taken at waste disposal sites, radiologically controlled areas, and roads. These activities were conducted to assess and control the effects of nuclear facilities and waste sites on the local environment. In addition, diffuse sources were monitored to determine compliance with federal, state, and/or local regulations. In general, although effects from nuclear facilities can still be observed on the Hanford Site and radiation levels are slightly elevated when compared to offsite locations, the differences are less than in previous years

303-K Storage Facility closure plan. Revision 2

Energy Technology Data Exchange (ETDEWEB)

1993-12-15

Recyclable scrap uranium with zircaloy-2 and copper silicon alloy, uranium-titanium alloy, beryllium/zircaloy-2 alloy, and zircaloy-2 chips and fines were secured in concrete billets (7.5-gallon containers) in the 303-K Storage Facility, located in the 300 Area. The beryllium/zircaloy-2 alloy and zircaloy-2 chips and fines are designated as mixed waste with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 303-K Storage Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act (RCRA) of 1976 and the Washington Administrative Code (WAC) Dangerous Waste Regulations, WAC 173-303-040. This closure plan presents a description of the 303-K Storage Facility, the history of materials and waste managed, and the procedures that will be followed to close the 303-K Storage Facility. The 303-K Storage Facility is located within the 300-FF-3 (source) and 300-FF-5 (groundwater) operable units, as designated in the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1992). Contamination in the operable units 300-FF-3 and 300-FF-5 is scheduled to be addressed through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 remedial action process. Therefore, all soil remedial action at the 304 Facility will be conducted as part of the CERCLA remedial action of operable units 300-FF-3 and 300-FF-5.

Design and study of photomultiplier pulse-shaping amplifier powered by the current flowing through a voltage divider

International Nuclear Information System (INIS)

Vladimir Popov

2003-01-01

A new version of Photomultiplier Tube (PMT) pulse amplifier, entirely powered by the current flowing through the base voltage divider, was designed and tested. This amplifier was designed for application in the JLAB G0 Experiment E00-006 as a part of high voltage base for XP2262 Photonis PMT. According to JLAB G0 experiment requirement, these PMT's operate with plastic scintillators at high counting rate (about MHz). Tests in JLAB experimental Hall C indicate that low energy gamma background cause up to 0.1 mA of PMT average anode current (without amplifier). At this radiation condition, PMT gain decreases by 50% within about 1 month of operation. The amplifier needs to reduce PMT anode current and to shape PMT anode pulse prior to sending it through a long cable line (more then 400 ft of RG-213 and RG-58 coax cables). Shaping of the PMT output pulse helps to reduce attenuation effect of the long cable line without significant reduction of timing accuracy. The results of this study of designed amplifier and PMT plus amplifier system are presented

W-1 Sodium Loop Safety Facility experiment centerline fuel thermocouple performance

International Nuclear Information System (INIS)

Meyers, S.C.; Henderson, J.M.

1980-05-01

The W-1 Sodium Loop Safety Facility (SLSF) experiment is the fifth in a series of experiments sponsored by the Department of Energy (DOE) as part of the National Fast Breeder Reactor (FBR) Safety Assurance Program. The experiments are being conducted under the direction of Argonne National Laboratory (ANL) and Hanford Engineering Development Laboratory (HEDL). The irradiation phase of the W-1 SLSF experiment was conducted between May 27 and July 20, 1979, and terminated with incipient fuel pin cladding failure during the final boiling transient. Experimental hardware and facility performed as designed, allowing completion of all planned tests and test objectives. This paper focuses on high temperature in-fuel thermocouples and discusses their development, fabrication, and performance in the W-1 experiment

Engineering evaluation/cost analysis for the 105-DR and 105-F Reactor facilities and ancillary facilities

International Nuclear Information System (INIS)

Coenenberg, E.T.

1998-01-01

This document presents the results of an engineering evaluation/cost analysis (EE/CA) that was conducted to evaluate alternatives to address final disposition of the 105-DR and 105-F Reactor Buildings (subsequently referred to as facilities), including the fuel storage basins (FSB) and below-grade portions of the reactors, excluding the reactor blocks. The reactor blocks will remain in a safe storage mode for up to 75 years as identified in the Record the Decision (ROD) (58 FR 48509) for the Environmental Impact Statement (EIS), Decommissioning of Eight Surplus Production Reactors at the Hanford Site, Richland, Washington (DOE 1992a). This EE/CA also addresses final disposition of four ancillary facilities: 116-D and 116-DR Exhaust Air Stacks, 117-DR Exhaust Filter Building, and 119-DR Exhaust Air Sample Building. The 105-DR and 105-F facilities are located in the 100-D and 100-F Areas of the Hanford Site. In November 1989, the 100 Area of the Hanford Site was placed on the U.S. Environmental Protection Agency's (EPA) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). The 100 Area NPL includes the 100-D Area (which includes the 100-DR site) and the 100-F Area, which are in various stages of the remediation process. It has been determined by DOE that hazardous substances in the 105-DR, 105-F, and the four ancillary facilities may present a potential threat to human health or the environment, and that a non-time critical removal action at these facilities is warranted. To help determine the most appropriate action, DOE, in cooperation with the Washington State Department of Ecology (Ecology) and the EPA, has prepared this EE/CA. The scope of the evaluation includes the 105-DR and 105-F facilities and the four ancillary facilities. The 116-DR and 117-DR facilities are located within the boundaries of the 105-DR Large Sodium Fire Facility Treatment, Storage, and Disposal (TSD) unit, which is

High-Level Waste Vitrification Facility Feasibility Study

Energy Technology Data Exchange (ETDEWEB)

D. A. Lopez

1999-08-01

A ''Settlement Agreement'' between the Department of Energy and the State of Idaho mandates that all radioactive high-level waste now stored at the Idaho Nuclear Technology and Engineering Center will be treated so that it is ready to be moved out of Idaho for disposal by a compliance date of 2035. This report investigates vitrification treatment of the high-level waste in a High-Level Waste Vitrification Facility based on the assumption that no more New Waste Calcining Facility campaigns will be conducted after June 2000. Under this option, the sodium-bearing waste remaining in the Idaho Nuclear Technology and Engineering Center Tank Farm, and newly generated liquid waste produced between now and the start of 2013, will be processed using a different option, such as a Cesium Ion Exchange Facility. The cesium-saturated waste from this other option will be sent to the Calcine Solids Storage Facilities to be mixed with existing calcine. The calcine and cesium-saturated waste will be processed in the High-Level Waste Vitrification Facility by the end of calendar year 2035. In addition, the High-Level Waste Vitrification Facility will process all newly-generated liquid waste produced between 2013 and the end of 2035. Vitrification of this waste is an acceptable treatment method for complying with the Settlement Agreement. This method involves vitrifying the waste and pouring it into stainless-steel canisters that will be ready for shipment out of Idaho to a disposal facility by 2035. These canisters will be stored at the Idaho National Engineering and Environmental Laboratory until they are sent to a national geologic repository. The operating period for vitrification treatment will be from the end of 2015 through 2035.

High-Level Waste Vitrification Facility Feasibility Study

International Nuclear Information System (INIS)

D. A. Lopez

1999-01-01

A ''Settlement Agreement'' between the Department of Energy and the State of Idaho mandates that all radioactive high-level waste now stored at the Idaho Nuclear Technology and Engineering Center will be treated so that it is ready to be moved out of Idaho for disposal by a compliance date of 2035. This report investigates vitrification treatment of the high-level waste in a High-Level Waste Vitrification Facility based on the assumption that no more New Waste Calcining Facility campaigns will be conducted after June 2000. Under this option, the sodium-bearing waste remaining in the Idaho Nuclear Technology and Engineering Center Tank Farm, and newly generated liquid waste produced between now and the start of 2013, will be processed using a different option, such as a Cesium Ion Exchange Facility. The cesium-saturated waste from this other option will be sent to the Calcine Solids Storage Facilities to be mixed with existing calcine. The calcine and cesium-saturated waste will be processed in the High-Level Waste Vitrification Facility by the end of calendar year 2035. In addition, the High-Level Waste Vitrification Facility will process all newly-generated liquid waste produced between 2013 and the end of 2035. Vitrification of this waste is an acceptable treatment method for complying with the Settlement Agreement. This method involves vitrifying the waste and pouring it into stainless-steel canisters that will be ready for shipment out of Idaho to a disposal facility by 2035. These canisters will be stored at the Idaho National Engineering and Environmental Laboratory until they are sent to a national geologic repository. The operating period for vitrification treatment will be from the end of 2015 through 2035

Stretchable and semitransparent conductive hybrid hydrogels for flexible supercapacitors.

Science.gov (United States)

Hao, Guang-Ping; Hippauf, Felix; Oschatz, Martin; Wisser, Florian M; Leifert, Annika; Nickel, Winfried; Mohamed-Noriega, Nasser; Zheng, Zhikun; Kaskel, Stefan

2014-07-22

Conductive polymers showing stretchable and transparent properties have received extensive attention due to their enormous potential in flexible electronic devices. Here, we demonstrate a facile and smart strategy for the preparation of structurally stretchable, electrically conductive, and optically semitransparent polyaniline-containing hybrid hydrogel networks as electrode, which show high-performances in supercapacitor application. Remarkably, the stability can extend up to 35,000 cycles at a high current density of 8 A/g, because of the combined structural advantages in terms of flexible polymer chains, highly interconnected pores, and excellent contact between the host and guest functional polymer phase.

Medical facility statistics in Japan.

Science.gov (United States)

Hamajima, Nobuyuki; Sugimoto, Takuya; Hasebe, Ryo; Myat Cho, Su; Khaing, Moe; Kariya, Tetsuyoshi; Mon Saw, Yu; Yamamoto, Eiko

2017-11-01

Medical facility statistics provide essential information to policymakers, administrators, academics, and practitioners in the field of health services. In Japan, the Health Statistics Office of the Director-General for Statistics and Information Policy at the Ministry of Health, Labour and Welfare is generating these statistics. Although the statistics are widely available in both Japanese and English, the methodology described in the technical reports are primarily in Japanese, and are not fully described in English. This article aimed to describe these processes for readers in the English-speaking world. The Health Statistics Office routinely conduct two surveys called the Hospital Report and the Survey of Medical Institutions. The subjects of the former are all the hospitals and clinics with long-term care beds in Japan. It comprises a Patient Questionnaire focusing on the numbers of inpatients, admissions, discharges, and outpatients in one month, and an Employee Questionnaire, which asks about the number of employees as of October 1. The Survey of Medical Institutions consists of the Dynamic Survey, which focuses on the opening and closing of facilities every month, and the Static Survey, which focuses on staff, facilities, and services as of October 1, as well as the number of inpatients as of September 30 and the total number of outpatients during September. All hospitals, clinics, and dental clinics are requested to submit the Static Survey questionnaire every three years. These surveys are useful tools for collecting essential information, as well as providing occasions to implicitly inform facilities of the movements of government policy.

Recent progress in ignition fusion research on the National Ignition Facility

International Nuclear Information System (INIS)

Leeper, Ramon J.

2011-01-01

This paper will review the ignition fusion research program that is currently being carried out on the National Ignition Facility (NIF) located at Lawrence Livermore National Laboratory. This work is being conducted under the auspices of the National Ignition Campaign (NIC) that is a broad collaboration of national laboratories and universities that together have developed a detailed research plan whose goal is ignition in the laboratory. The paper will begin with a description of the NIF facility and associated experimental facilities. The paper will then focus on the ignition target and hohlraum designs that will be tested in the first ignition attempts on NIF. The next topic to be introduced will be a description of the diagnostic suite that has been developed for the initial ignition experiments on NIF. The paper will then describe the experimental results that were obtained in experiments conducted during the fall of 2009 on NIF. Finally, the paper will end with a description of the detailed experimental plans that have been developed for the first ignition campaign that will begin later this year. (author)

Measurements of Polarization Transfers in Real Compton Scattering by a proton target at JLAB. A new source of information on the 3D shape of the nucleon

Energy Technology Data Exchange (ETDEWEB)

Fanelli, Cristiano V. [Sapienza Univ. of Rome (Italy)

2015-03-01

In this thesis work, results of the analysis of the polarization transfers measured in real Compton scattering (RCS) by the Collaboration E07-002 at the Je fferson Lab Hall-C are presented. The data were collected at large scattering angle (theta_cm = 70deg) and with a polarized incident photon beam at an average energy of 3.8 GeV. Such a kind of experiments allows one to understand more deeply the reaction mechanism, that involves a real photon, by extracting both Compton form factors and Generalized Parton Distributions (GPDs) (also relevant for possibly shedding light on the total angular momentum of the nucleon). The obtained results for the longitudinal and transverse polarization transfers K_LL and K_LT, are of crucial importance, since they confirm unambiguously the disagreement between experimental data and pQCD prediction, as it was found in E99-114 experiment, and favor the Handbag mechanism. The E99-114 and E07-002 results can contribute to attract new interest on the great yield of the Compton scattering by a nucleon target, as demonstrated by the recent approval of an experimental proposal submitted to the Jefferson Lab PAC 42 for a Wide-angle Compton Scattering experiment, at 8 and 10 GeV Photon Energies. The new experiments approved to run with the updated 12 GeV electron beam at JLab, are characterized by much higher luminosities, and a new GEM tracker is under development to tackle the challenging backgrounds. Within this context, we present a new multistep tracking algorithm, based on (i) a Neural Network (NN) designed for a fast and efficient association of the hits measured by the GEM detector which allows the track identification, and (ii) the application of both a Kalman filter and Rauch-Tung-Striebel smoother to further improve the track reconstruction. The full procedure, i.e. NN and filtering, appears very promising, with high performances in terms of both association effciency and reconstruction accuracy, and these preliminary results will

Definition of a protocol for conducting energy audits in cattle facilities: implementation in small and medium farms; Definicion de un protocolo para la realizacion de auditorias energeticas en instalaciones ganaderas: aplicacion en pequenas y medianas explotaciones

Energy Technology Data Exchange (ETDEWEB)

Navas, Luis M; Hernandez, Pablo; Guimaraes, Adriana C; Sanzi, Juan F; Gonzalez, Fernando; Ruiz, Gonzalo [Universidad de Valladolid (UVa), Palencia (Spain). Escuela Tecnica Superior de Ingenierias Agrarias. Dept. de Ingenieria Agricola y Forestal; Baptista, Fatima; Cruz, Vasco F. da , [Universidade de Evora (UEv), Evora (Portugal). Dept. de Engenharia Rural

2010-07-01

The present task shows the results of a project developed in Spain under the sponsorship of the Instituto para la Diversificacion y Ahorro de la Energia (IDAE), Ente Regional de la Energia de Castilla y Leon (EREN) and the Union de Pequenos Agricultores (UPA) which was implemented in the region of Castilla y Leon, an area with a predominantly agricultural and livestock production that aimed the establishment of a protocol for conducting energy audits in livestock facilities, focusing mainly those of small and medium size. The purpose of the protocol was to develop a methodology for the systematic characterization and formulation of proposals for improvement of the following elements: Construction features, power supplies, lighting, electric motors, heating, cooling and ventilation, renewable energies, energy utilization facilities of livestock waste and measuring and control equipment. The protocol was validated by conducting energy audits in 15 farms: 5 dairy cows, 5 sheep milk, 3 fattening pigs and 2 broilers. The results obtained showed that the proposed energy efficiency measures, which are characterized by their simple and usually cost effective deployment results an average energy savings consumption of 18%, which is manifested in a average cost reduction of 24.28%. (author)

A facile method to synthesize polypyrrole nanoparticles in the presence of natural organic phosphate

Energy Technology Data Exchange (ETDEWEB)

Yang, Chao; Mo, Haodao [State Key Laboratory Breeding Base of Nonferrous Metals and Specific Materials Processing, College of Material Science and Engineering, Guilin University of Technology, Guilin 541004 (China); Zang, Limin, E-mail: D14S004@akita-pu.ac.jp [Department of Machine Intelligence and Systems Engineering, Faculty of Systems Engineering, Akita Prefectural University, Yurihonjo City, Akita 015-0055 (Japan); Qiu, Jianhui; Sakai, Eiichi; Wu, Xueli [Department of Machine Intelligence and Systems Engineering, Faculty of Systems Engineering, Akita Prefectural University, Yurihonjo City, Akita 015-0055 (Japan)

2014-09-15

The conductive polymers with unique nanostructures have attracted intense interest due to their potential application. Here the well-defined polypyrrole nanoparticles were facile fabricated via the facile chemical oxidative polymerization of pyrrole with high feeding ratio of phytic acid. Phytic acid is a renewable resource and a natural carbohydrate compound with a vast number of phosphate groups from plant which was used as the template and dopant for the nanostructured conductive polymer for the first time. The samples exhibit the well-defined nanoparticles observed by scanning electron microscope (SEM) and atomic force microscope (AFM). The PPy nanoparticles were achieved and outstanding electrical conductivity as high as 5263 S m{sup −1} was obtained with the feeding mass ratio of phytic acid: pyrrole=3:7. Furthermore, the polypyrrole nanoparticles were characterized with Fourier transform infrared (FTIR), thermogravimetric analysis (TGA), and electrical conductivity techniques.

Engineering and technology in the deconstruction of nuclear materials production facilities

International Nuclear Information System (INIS)

Kingsley, R.S.; Reynolds, W.E.; Heffner, D.C.

1996-01-01

Technology and equipment exist to support nuclear facility deactivation, decontamination, and decommissioning. In reality, this statement is not surprising because the nuclear industry has been decontaminating and decommissioning production plants for decades as new generations of production technology were introduced. Since the 1950s, the Babcock and Wilcox Company (B ampersand W) has operated a number of nuclear materials processing facilities to manufacture nuclear fuel for the commercial power industry and the U.S. Navy. These manufacturing facilities included a mixed oxide (PuO 2 -UO 2 ) nuclear fuel manufacturing plant, low- and high-enriched uranium (HEU/LEU) chemical and fuel plants, and fuel assembly plants. In addition, B ampersand W designed and build a major nuclear research center in Lynchburg, Virginia, to support these nuclear fuel manufacturing activities and to conduct nuclear power research. These nuclear research facilities included two research reactors, a hot-cell complex for nuclear materials research, four critical experiment facilities, and a plutonium fuels research and development facility. This article describes the B ampersand W deactivation, decomtanimation, and decommisioning program

Hazards assessment for the Waste Experimental Reduction Facility

Energy Technology Data Exchange (ETDEWEB)

Calley, M.B.; Jones, J.L. Jr.

1994-09-19

This report documents the hazards assessment for the Waste Experimental Reduction Facility (WERF) located at the Idaho National Engineering Laboratory, which is operated by EG&G Idaho, Inc., for the US Department of Energy (DOE). The hazards assessment was performed to ensure that this facility complies with DOE and company requirements pertaining to emergency planning and preparedness for operational emergencies. DOE Order 5500.3A requires that a facility-specific hazards assessment be performed to provide the technical basis for facility emergency planning efforts. This hazards assessment was conducted in accordance with DOE Headquarters and DOE Idaho Operations Office (DOE-ID) guidance to comply with DOE Order 5500.3A. The hazards assessment identifies and analyzes hazards that are significant enough to warrant consideration in a facility`s operational emergency management program. This hazards assessment describes the WERF, the area surrounding WERF, associated buildings and structures at WERF, and the processes performed at WERF. All radiological and nonradiological hazardous materials stored, used, or produced at WERF were identified and screened. Even though the screening process indicated that the hazardous materials could be screened from further analysis because the inventory of radiological and nonradiological hazardous materials were below the screening thresholds specified by DOE and DOE-ID guidance for DOE Order 5500.3A, the nonradiological hazardous materials were analyzed further because it was felt that the nonradiological hazardous material screening thresholds were too high.

Facilities & Leadership

Data.gov (United States)

Department of Veterans Affairs — The facilities web service provides VA facility information. The VA facilities locator is a feature that is available across the enterprise, on any webpage, for the...

Microscope-Based Fluid Physics Experiments in the Fluids and Combustion Facility on ISS

Science.gov (United States)

Doherty, Michael P.; Motil, Susan M.; Snead, John H.; Malarik, Diane C.

2000-01-01

At the NASA Glenn Research Center, the Microgravity Science Program is planning to conduct a large number of experiments on the International Space Station in both the Fluid Physics and Combustion Science disciplines, and is developing flight experiment hardware for use within the International Space Station's Fluids and Combustion Facility. Four fluids physics experiments that require an optical microscope will be sequentially conducted within a subrack payload to the Fluids Integrated Rack of the Fluids and Combustion Facility called the Light Microscopy Module, which will provide the containment, changeout, and diagnostic capabilities to perform the experiments. The Light Microscopy Module is planned as a fully remotely controllable on-orbit microscope facility, allowing flexible scheduling and control of experiments within International Space Station resources. This paper will focus on the four microscope-based experiments, specifically, their objectives and the sample cell and instrument hardware to accommodate their requirements.

Facility model for the Los Alamos Plutonium Facility

International Nuclear Information System (INIS)

Coulter, C.A.; Thomas, K.E.; Sohn, C.L.; Yarbro, T.F.; Hench, K.W.

1986-01-01

The Los Alamos Plutonium Facility contains more than sixty unit processes and handles a large variety of nuclear materials, including many forms of plutonium-bearing scrap. The management of the Plutonium Facility is supporting the development of a computer model of the facility as a means of effectively integrating the large amount of information required for material control, process planning, and facility development. The model is designed to provide a flexible, easily maintainable facility description that allows the faciltiy to be represented at any desired level of detail within a single modeling framework, and to do this using a model program and data files that can be read and understood by a technically qualified person without modeling experience. These characteristics were achieved by structuring the model so that all facility data is contained in data files, formulating the model in a simulation language that provides a flexible set of data structures and permits a near-English-language syntax, and using a description for unit processes that can represent either a true unit process or a major subsection of the facility. Use of the model is illustrated by applying it to two configurations of a fictitious nuclear material processing line

Design of the target area for the National Ignition Facility

International Nuclear Information System (INIS)

Foley, R.J.; Karpenko, V.P.; Adams, C.H.

1997-01-01

The preliminary design of the target area for the National Ignition Facility has been completed. The target area is required to meet a challenging set of engineering system design requirements and user needs. The target area must provide the appropriate conditions before, during, and after each shot. The repeated introduction of large amounts of laser energy into the chamber and subsequent target emissions represent new design challenges for ICF facility design. Prior to each shot, the target area must provide the required target illumination, target chamber vacuum, diagnostics, and optically stable structures. During the shot, the impact of the target emissions on the target chamber, diagnostics, and optical elements is minimized and the workers and public are protected from excessive prompt radiation doses. After the shot, residual radioactivation is managed to allow the required accessibility. Diagnostic data is retrieved, operations and maintenance activities are conducted, and the facility is ready for the next shot. The target area subsystems include the target chamber, target positioner, structural systems, target diagnostics, environmental systems, and the final optics assembly. The engineering design of the major elements of the target area requires a unique combination of precision engineering, structural analysis, opto-mechanical design, random vibration suppression, thermal stability, materials engineering, robotics, and optical cleanliness. The facility has been designed to conduct both x- ray driven targets and to be converted at a later date for direct drive experiments. The NIF has been configured to provide a wide range of experimental environments for the anticipated user groups of the facility. The design status of the major elements of the target area is described

Testing of the West Valley Vitrification Facility transfer cart control system

International Nuclear Information System (INIS)

Halliwell, J.W.; Bradley, E.C.

1995-01-01

Oak Ridge National Laboratory (ORNL) has designed and tested the control system for the West Valley Demonstration Project Vitrification Facility transfer cart. The transfer cart will transfer canisters of vitrified high-level waste remotely within the Vitrification Facility. The control system operates the cart under battery power by wireless control. The equipment includes cart-mounted control electronics, battery charger, control pendants, engineer's console, and facility antennas. Testing was performed in several phases of development: (1) prototype equipment was built and tested during design, (2) board-level testing was then performed at ORNL during fabrication, and (3) system-level testing was then performed by ORNL at the fabrication subcontractor's facility for the completed cart system. These tests verified (1) the performance of the cart relative to design requirements and (2) operation of various built-in cart features. The final phase of testing is planned to be conducted during installation at the West Valley Vitrification Facility

Tests and studies of USSR materials at the US coal burning MHD facility UTSI-2

Energy Technology Data Exchange (ETDEWEB)

Telegin, G P; Romanov, A I; Rekov, A I; Spiridonov, E G; Barodina, T I; Vysotsky, D A

1978-10-01

In accordance with the overall program of the US--USSR cooperation in the field of MHD power generation tests of Soviet electrode materials were conducted at the coal burning MHD facility UTSI-2 of the University of Tennessee Space Institute. The main purposes of the tests are evaluation of electrode materials behavior in the channel of the MHD generator operating with combustion products of coal containing ionizing alkali seed, study of thermal and physical stability of materials in the presence of corrosive slag, study of electrophysical characteristics of electrode materials when they are subjected to the passage of current through the plasma-slag-electrode system. Tests were conducted on electrodes made of silicon carbide doped with titanium and LaCrO/sub 3/--Cr cermet. Results are reported on the phase and chemical composition and structure of these two materials, their thermophysical and electrophysical properties, and the electrode fabrication methods. The MHD facility UTSI-2, where the tests were conducted is one of few utilizing actual coal as the fuel. A description of this facility is given, and its main operating parameters and the methods used to conduct electrode tests with and without an applied current are described.

Absolute measurement of the DT primary neutron yield on the National Ignition Facility

Directory of Open Access Journals (Sweden)

Leeper R.J.

2013-11-01

Full Text Available The measurement of the absolute neutron yield produced in inertial confinement fusion target experiments conducted on the National Ignition Facility (NIF is essential in benchmarking progress towards the goal of achieving ignition on this facility. This paper describes three independent diagnostic techniques that have been developed to make accurate and precise DT neutron yield measurements on the NIF.

Usability: managing facilities for social outcomes

DEFF Research Database (Denmark)

Alexander, Keith; Blakstad, Siri; Hansen, Geir

2013-01-01

The paper argues for the development of usability concepts, methodologies and tools, in considering the effects of the built environment from a user, organisational and community perspective, in order to have a positive influence on social outcomes. Since it was formed over ten years ago, the CIB W......111 on Usability has been exploring concepts, methods and tools, developed in the evaluation of all kinds of consumer products, applied to the built environment. In the most recent phase of this work, conducted over the past three years, an international network of partners has collaborated to focus...... properties of a workplace, they could better manage and design the facilities for improved social outcomes. Interpretation and analysis of the built environment (and support services) based on how it is socially constructed will enable integration of organisational use and the facilities provided to arrive...

Model Regulations for Decommissioning of Facilities

International Nuclear Information System (INIS)

2017-07-01

The IAEA has systematic programmes to provide Member States with the guidance, services and training necessary for establishing a legal and regulatory framework, including the planning and implementation of decommissioning. The model regulations provided in this publication cover all aspects of the planning, conduct and termination of the decommissioning of facilities and management of the associated waste, in accordance with the relevant requirements of the IAEA safety standards. They provide a framework for establishing regulatory requirements and conditions of authorization to be incorporated into individual authorizations for the decommissioning of specific facilities. The model regulations also establish criteria to be used for assessing compliance with regulatory requirements. The publication will be of assistance to Member States in appraising the adequacy of their existing regulations and regulatory guides, and serves as a reference for those Member States developing regulations for the first time.

Economic evaluation of pharmacist-led medication reviews in residential aged care facilities.

Science.gov (United States)

Hasan, Syed Shahzad; Thiruchelvam, Kaeshaelya; Kow, Chia Siang; Ghori, Muhammad Usman; Babar, Zaheer-Ud-Din

2017-10-01

Medication reviews is a widely accepted approach known to have a substantial impact on patients' pharmacotherapy and safety. Numerous options to optimise pharmacotherapy in older people have been reported in literature and they include medication reviews, computerised decision support systems, management teams, and educational approaches. Pharmacist-led medication reviews are increasingly being conducted, aimed at attaining patient safety and medication optimisation. Cost effectiveness is an essential aspect of a medication review evaluation. Areas covered: A systematic searching of articles that examined the cost-effectiveness of medication reviews conducted in aged care facilities was performed using the relevant databases. Pharmacist-led medication reviews confer many benefits such as attainment of biomarker targets for improved clinical outcomes, and other clinical parameters, as well as depict concrete financial advantages in terms of decrement in total medication costs and associated cost savings. Expert commentary: The cost-effectiveness of medication reviews are more consequential than ever before. A critical evaluation of pharmacist-led medication reviews in residential aged care facilities from an economical aspect is crucial in determining if the time, effort, and direct and indirect costs involved in the review rationalise the significance of conducting medication reviews for older people in aged care facilities.

Safeguards at NRC licensed facilities: Are we doing enough

International Nuclear Information System (INIS)

Asselstine, J.K.

1986-01-01

The Nuclear Regulatory Commission is pursuing a number of initiatives in the safeguards area. The Commission is conducting a reassessment of its safeguards design basis threat statements to consider the possible implications of an explosive-laden vehicle for U.S. nuclear safeguards and to examine the comparability of safeguards features at NRC-licensed and DOE facilities. The Commission is also completing action on measures to protect against the sabotage threat from an insider at NRC-licensed facilities, and is examining the potential safety implications of safeguards measures. Finally, the NRC has developed measures to reduce the theft potential for high-enriched uranium

ROSA-IV Large Scale Test Facility (LSTF) system description for second simulated fuel assembly

International Nuclear Information System (INIS)

1990-10-01

The ROSA-IV Program's Large Scale Test Facility (LSTF) is a test facility for integral simulation of thermal-hydraulic response of a pressurized water reactor (PWR) during small break loss-of-coolant accidents (LOCAs) and transients. In this facility, the PWR core nuclear fuel rods are simulated using electric heater rods. The simulated fuel assembly which was installed during the facility construction was replaced with a new one in 1988. The first test with this second simulated fuel assembly was conducted in December 1988. This report describes the facility configuration and characteristics as of this date (December 1988) including the new simulated fuel assembly design and the facility changes which were made during the testing with the first assembly as well as during the renewal of the simulated fuel assembly. (author)

Conducting an audit to improve the facilitation of emergency maternal and newborn referral in northern Ghana.

Science.gov (United States)

Awoonor-Williams, John Koku; Bailey, Patricia E; Yeji, Francis; Adongo, Ayire Emmanuel; Baffoe, Peter; Williams, Afua; Mercer, Sarah

2015-10-01

Ghana Health Service conducted an audit to strengthen the referral system for pregnant or recently pregnant women and newborns in northern Ghana. The audit took place in 16 facilities with two 3-month cycles of data collection in 2011. Midwife-led teams tracked 446 referred women until they received definitive treatment. Between the two audit cycles, teams identified and implemented interventions to address gaps in referral services. During this time period, we observed important increases in facilitating referral mechanisms, including a decrease in the dependence on taxis in favour of national or facility ambulances/vehicles; an increase in health workers escorting referrals to the appropriate receiving facility; greater use of referral slips and calling ahead to alert receiving facilities and higher feedback rates. As referral systems require attention from multiple levels of engagement, on the provider end we found that regional managers increasingly resolved staffing shortages; district management addressed the costliness and lack of transport and increased midwives' ability to communicate with pregnant women and drivers; and that facility staff increasingly adhered to guidelines and facilitating mechanisms. By conducting an audit of maternal and newborn referrals, the Ghana Health Service identified areas for improvement that service providers and management at multiple levels addressed, demonstrating a platform for problem solving that could be a model elsewhere.

Security Culture in Physical Protection of Nuclear Material and Facility

International Nuclear Information System (INIS)

Susyanta-Widyatmaka; Koraag, Venuesiana-Dewi; Taswanda-Taryo

2005-01-01

In nuclear related field, there are three different cultures: safety, safeguards and security culture. Safety culture has established mostly in nuclear industries, meanwhile safeguards and security culture are relatively new and still developing. The latter is intended to improve the physical protection of material and nuclear facility. This paper describes concept, properties and factors affecting security culture and interactions among these cultures. The analysis indicates that anybody involving in nuclear material and facility should have strong commitment and awareness of such culture to establish it. It is concluded that the assessment of security culture outlined in this paper is still preliminary for developing and conduction rigorous security culture implemented in a much more complex facility such as nuclear power plant

Defense Waste Processing Facility -- Radioactive operations -- Part 3 -- Remote operations

International Nuclear Information System (INIS)

Barnes, W.M.; Kerley, W.D.; Hughes, P.D.

1997-01-01

The Savannah River Site's Defense Waste Processing Facility (DWPF) near Aiken, South Carolina is the nation's first and world's largest vitrification facility. Following a ten year construction period and nearly three years of non-radioactive testing, the DWPF began radioactive operations in March 1996. Radioactive glass is poured from the joule heated melter into the stainless steel canisters. The canisters are then temporarily sealed, decontaminated, resistance welded for final closure, and transported to an interim storage facility. All of these operations are conducted remotely with equipment specially designed for these processes. This paper reviews canister processing during the first nine months of radioactive operations at DWPF. The fundamental design consideration for DWPF remote canister processing and handling equipment are discussed as well as interim canister storage

Review and assessment of nuclear facilities by the regulatory body. Safety guide

International Nuclear Information System (INIS)

2004-01-01

The purpose of this Safety Guide is to provide recommendations for regulatory bodies on reviewing and assessing the various safety related submissions made by the operator of a nuclear facility at different stages (siting, design, construction, commissioning, operation and decommissioning or closure) in the facility's lifetime to determine whether the facility complies with the applicable safety objectives and requirements. This Safety Guide covers the review and assessment of submissions in relation to the safety of nuclear facilities such as: enrichment and fuel manufacturing plants. Nuclear power plants. Other reactors such as research reactors and critical assemblies. Spent fuel reprocessing plants. And facilities for radioactive waste management, such as treatment, storage and disposal facilities. This Safety Guide also covers issues relating to the decommissioning of nuclear facilities, the closure of waste disposal facilities and site rehabilitation. Objectives, management, planning and organizational matters relating to the review and assessment process are presented in Section 2. Section 3 deals with the bases for decision making and conduct of the review and assessment process. Section 4 covers aspects relating to the assessment of this process. The Appendix provides a generic list of topics to be covered in the review and assessment process

Review and assessment of nuclear facilities by the regulatory body. Safety guide

International Nuclear Information System (INIS)

2005-01-01

The purpose of this Safety Guide is to provide recommendations for regulatory bodies on reviewing and assessing the various safety related submissions made by the operator of a nuclear facility at different stages (siting, design, construction, commissioning, operation and decommissioning or closure) in the facility's lifetime to determine whether the facility complies with the applicable safety objectives and requirements. This Safety Guide covers the review and assessment of submissions in relation to the safety of nuclear facilities such as: enrichment and fuel manufacturing plants. Nuclear power plants. Other reactors such as research reactors and critical assemblies. Spent fuel reprocessing plants. And facilities for radioactive waste management, such as treatment, storage and disposal facilities. This Safety Guide also covers issues relating to the decommissioning of nuclear facilities, the closure of waste disposal facilities and site rehabilitation. Objectives, management, planning and organizational matters relating to the review and assessment process are presented in Section 2. Section 3 deals with the bases for decision making and conduct of the review and assessment process. Section 4 covers aspects relating to the assessment of this process. The Appendix provides a generic list of topics to be covered in the review and assessment process

Summary Report - Inspections of DoD Facilities and Military Housing and Audits of Base Operations and Support Services Contracts

Science.gov (United States)

2016-10-14

drinking water quality, radon, pest management, mold, and radiation. In addition, during the Japan and Korea inspections, we evaluated the management...Components responsible for facilities management conduct such analyses and use the results of these root cause analyses to improve facility management...water quality, radon, mold, pest infestation, lead-based paint, asbestos, and radiation) requirements. These inspections should be conducted by

A probabilistic risk assessment of the LLNL Plutonium facility's evaluation basis fire operational accident

International Nuclear Information System (INIS)

Brumburgh, G.

1994-01-01

The Lawrence Livermore National Laboratory (LLNL) Plutonium Facility conducts numerous involving plutonium to include device fabrication, development of fabrication techniques, metallurgy research, and laser isotope separation. A Safety Analysis Report (SAR) for the building 332 Plutonium Facility was completed rational safety and acceptable risk to employees, the public, government property, and the environment. This paper outlines the PRA analysis of the Evaluation Basis Fire (EDF) operational accident. The EBF postulates the worst-case programmatic impact event for the Plutonium Facility

The cascad spent fuel dry storage facility

International Nuclear Information System (INIS)

Guay, P.; Bonnet, C.

1991-01-01

France has a wide variety of experimental spent fuels different from LWR spent fuel discharged from commercial reactors. Reprocessing such fuels would thus require the development and construction of special facilities. The French Atomic Energy Commission (CEA) has consequently opted for long-term interim storage of these spent fuels over a period of 50 years. Comparative studies of different storage concepts have been conducted on the basis of safety (mainly containment barriers and cooling), economic, modular design and operating flexibility criteria. These studies have shown that dry storage in a concrete vault cooled by natural convection is the best solution. A research and development program including theoretical investigations and mock-up tests confirmed the feasibility of cooling by natural convection and the validity of design rules applied for fuel storage. A facility called CASCAD was built at the CEA's Cadarache Nuclear Research Center, where it has been operational since mid-1990. This paper describes the CASCAD facility and indicates how its concept can be applied to storage of LWR fuel assemblies

A Novel Method of Fabricating Flexible Transparent Conductive Large Area Graphene Film

International Nuclear Information System (INIS)

Fan Tian-Ju; Yuan Chun-Qiu; Tang Wei; Tong Song-Zhao; Huang Wei; Min Yong-Gang; Liu Yi-Dong; Epstein, Arthur J.

2015-01-01

We fabricate flexible conductive and transparent graphene films on position-emission-tomography substrates and prepare large area graphene films by graphite oxide sheets with the new technical process. The multi-layer graphene oxide sheets can be chemically reduced by HNO 3 and HI to form a highly conductive graphene film on a substrate at lower temperature. The reduced graphene oxide sheets show a high conductivity sheet with resistance of 476 Ω/sq and transmittance of 76% at 550 nm (6 layers). The technique used to produce the transparent conductive graphene thin film is facile, inexpensive, and can be tunable for a large area production applied for electronics or touch screens. (paper)

A simulation based research on chance constrained programming in robust facility location problem

Directory of Open Access Journals (Sweden)

Kaijun Leng

2017-03-01

Full Text Available Since facility location decisions problem include long-term character and potential parameter variations, it is important to consider uncertainty in its modeling. This paper examines robust facility location problem considering supply uncertainty, in which we assume the supply of the facility in the actual operation is not equal to the supply initially established, the supply is subject to random fluctuation. The chance constraints are introduced when formulating the robust facility location model to make sure the system operate properly with a certain probability while the supply fluctuates. The chance constraints are approximated safely by using Hoeffding’s inequality and the problem is transformed to a general deterministic linear programming. Furthermore, how the facility location cost change with confidence level is investigated through a numerical example. The sensitivity analysis is conducted for important parameters of the model and we get the main factors that affect the facility location cost.

Progress at LAMPF (Los Alamos Meson Physics Facility), January--December 1989

Energy Technology Data Exchange (ETDEWEB)

Poelakker, K. (ed.)

1990-12-01

This report contains brief papers on research conducted at the lampf facility in the following areas: nuclear and particle physics; astrophysics; atomic and molecular physics; materials science; nuclear chemistry; radiation effects and radioisotope production.

Progress at LAMPF [Los Alamos Meson Physics Facility], January--December 1989

International Nuclear Information System (INIS)

Poelakker, K.

1990-12-01

This report contains brief papers on research conducted at the lampf facility in the following areas: nuclear and particle physics; astrophysics; atomic and molecular physics; materials science; nuclear chemistry; radiation effects and radioisotope production

Report of questionnaire result concerning the radiation control in medicare facilities

International Nuclear Information System (INIS)

Nakamura, Yutaka

2009-01-01

Radiation control in Japanese medicare facilities is regulated generally by multiple laws of radiation and the Committee has investigated their actual radiation control practice through questionnaire, of which result and its analysis are described here. The questionnaire on web (Committee's homepage) was conducted in the period Apr., 13-May, 1, 2009, by asking to medical radiology personnel (MRP) with 20 items, mainly about personnel working for radiation medicare (RM), monitoring of their external dose, notice of exposure dose to individual person, archiving of the dose record, and questions about the Law Concerning Prevention from Radiation Hazard due to Radioisotopes, Etc.; was answered by 378 facilities where 15,281 persons in total worked for RM (41/facility in average); and the facilities were under regulation by 1 (Medical, 39%) and 2 (Medical and for Prevention, 61%) laws. Major findings were: 71% of facilities had no clear rule to select MRP; 98% trusted dosimetry outside; in 76%, personnel participating in RM had pocket dosimeter as well; 70% investigated the exposure history at personnel employment; to personnel whose dose could exceed or exceeded 20 mSv/y, 45% transferred the person to other work site, 34% issued warning and 21% had no such personnel; 73% felt the necessity of qualified expert for radiation control; 81% conducted education and training to MRP; 54% used radiation-generating equipments, 27%, unsealed radioisotopes and 19%, sealed ones; and 77% felt the radiation control should be unified in the Medical Law. Based on the findings, the Committee discussed and commented about definition and selection of MRP, dosimetry and its record of MRP having multiple, increasing works, uncertainty of the exact number of MRP in Japan, and desirable unification of radiation control practice in the medicare facility into the Medical Law if amended in future. (K.T.)

Hanford Facility Annual Dangerous Waste Report Calendar Year 2002

International Nuclear Information System (INIS)

FR-EEMAN, D.A.

2003-01-01

Hanford CY 2002 dangerous waste generation and management forms. The Hanford Facility Annual Dangerous Waste Report (ADWR) is prepared to meet the requirements of Washington Administrative Code Sections 173-303-220, Generator Reporting, and 173-303-390, Facility Reporting. In addition, the ADWR is required to meet Hanford Facility RCRA Permit Condition I.E.22, Annual Reporting. The ADWR provides summary information on dangerous waste generation and management activities for the Calendar Year for the Hanford Facility EPA ID number assigned to the Department of Energy for RCRA regulated waste, as well as Washington State only designated waste and radioactive mixed waste. The Solid Waste Information and Tracking System (SWITS) database is utilized to collect and compile the large array of data needed for preparation of this report. Information includes details of waste generated on the Hanford Facility, waste generated offsite and sent to Hanford for management, and other waste management activities conducted at Hanford, including treatment, storage, and disposal. Report details consist of waste descriptions and weights, waste codes and designations, and waste handling codes. In addition, for waste shipped to Hanford for treatment and/or disposal, information on manifest numbers, the waste transporter, the waste receiving facility, and the original waste generators are included. In addition to paper copies, electronic copies of the report are also transmitted to the regulatory agency

Detecting New Pedestrian Facilities from VGI Data Sources

Science.gov (United States)

Zhong, S.; Xie, Z.

2017-12-01

Pedestrian facility (e.g. footbridge, pedestrian crossing and underground passage) information is an important basic data of location based service (LBS) for pedestrians. However, timely updating pedestrian facility information challenges due to facilities change frequently. Previous pedestrian facility information collecting and updating tasks are mainly completed by highly trained specialized persons. However, this conventional approach has several disadvantages such as high cost, long update cycle and so on. Volunteered Geographic Information (VGI) has proven efficiency to provide new, free and fast growing spatial data. Pedestrian trajectory, which can be seen as measurements of real pedestrian road, is one of the most valuable information of VGI data. Although the accuracy of the trajectories is not too high, due to the large number of measurements, an improvement of quality of the road information can be achieved. Thus, we develop a method for detecting new pedestrian facilities based on the current road network and pedestrian trajectories. Specifically, 1) by analyzing speed, distance and direction, those outliers of pedestrian trajectories are removed, 2) a road network matching algorithm is developed for eliminating redundant trajectories, and 3) a space-time cluster algorithm is adopted for detecting new walking facilities. The performance of the method is evaluated with a series of experiments conducted on a part of the road network of Heifei and a large number of real pedestrian trajectories, and verified the results by using Tencent Street map. The results show that the proposed method is able to detecting new pedestrian facilities from VGI data accurately. We believe that the proposed method provides an alternative way for general road data acquisition, and can improve the quality of LBS for pedestrians.

Neutron/photon/electron shielding study for a laser-fusion facility

International Nuclear Information System (INIS)

Thompson, W.L.

1977-01-01

A Monte Carlo shielding study encompassing neutron, photon, and electron transport has been conducted for the High Energy Gas Laser Facility at the Los Alamos Scientific Laboratory. This paper describes the application of the Monte Carlo technique and several variance reduction schemes to the study. The calculations involve a geometry which is complicated in all three dimensions, a very intense 14 MeV neutron source, skyshine and deep penetrations. The facility design with 1.83 m concrete walls and a 1.52 m concrete roof is based on these calculations

Animal facilities

International Nuclear Information System (INIS)

Fritz, T.E.; Angerman, J.M.; Keenan, W.G.; Linsley, J.G.; Poole, C.M.; Sallese, A.; Simkins, R.C.; Tolle, D.

1981-01-01

The animal facilities in the Division are described. They consist of kennels, animal rooms, service areas, and technical areas (examining rooms, operating rooms, pathology labs, x-ray rooms, and 60 Co exposure facilities). The computer support facility is also described. The advent of the Conversational Monitor System at Argonne has launched a new effort to set up conversational computing and graphics software for users. The existing LS-11 data acquisition systems have been further enhanced and expanded. The divisional radiation facilities include a number of gamma, neutron, and x-ray radiation sources with accompanying areas for related equipment. There are five 60 Co irradiation facilities; a research reactor, Janus, is a source for fission-spectrum neutrons; two other neutron sources in the Chicago area are also available to the staff for cell biology studies. The electron microscope facilities are also described

Secondary containment systems for bulk oil storage facilities

International Nuclear Information System (INIS)

Carr, B.A.

1996-01-01

The United States Environmental Protection Agency has conducted site inspections at several onshore bulk oil above ground storage facilities, to ensure that owners follow the spill prevention, control and countermeasure regulations. The four violations which were most frequently cited at these facilities were: (1) lack of a spill prevention plan, (2) lack of appropriate containment equipment to prevent discharged oil from reaching a navigable water course, (3) inadequate secondary containment structures, and (4) lack of an adequate quick drainage system in the facility tank loading/unloading area. Suggestions for feasible designs which would improve the impermeability of secondary containment for above ground storage tanks (AST) included the addition of a liner, retrofitting the bottom of an AST with a second steel plate, using a geosynthetic liner on top of the original bottom, installing a leak detection system in the interstitial space between the steel plates, or installing an under-tank liner with a leak detection system during construction of a new AST. 2 refs

Facilities Performance Indicators Report 2013-14: Tracking Your Facilities Vital Signs

Science.gov (United States)

APPA: Association of Higher Education Facilities Officers, 2015

2015-01-01

This paper features an expanded Web-based "Facilities Performance Indicators (FPI) Report." The purpose of APPA: Association of Higher Education Facilities Officers (APPA's) Facilities Performance Indicators is to provide a representative set of statistics about facilities in educational institutions. "The Facilities Performance…

LAFD: TA-55 General Facility Familiarization Tour, Course #55261

Energy Technology Data Exchange (ETDEWEB)

Rutherford, Victor Stephen [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Miller, Joshua [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Mason, Robert Clifford [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2018-01-10

Los Alamos National Laboratory (LANL) will conduct familiarization tours for personnel of the Los Alamos County Fire Department (LAFD) at the TA-55 General Facility. These familiarization tours are official LANL business; the purpose of these tours is to orient LAFD firefighters to the facility so that they can respond efficiently and quickly to a variety of emergency situations. This orientation includes, among other topics, ingress and egress of the area and buildings, layout and organization of the facility, evacuation procedures and assembly points, and areas of concern within the various buildings at the facility. LAFD firefighters have the skills and abilities to perform firefighting operations and other emergency response tasks that cannot be provided by LANL personnel who have the required clearance level. This handout provides details of the information, along with maps and diagrams, to be presented during the familiarization tours. The handout will be distributed to the trainees at the time of the tour. A corresponding checklist will also be used as guidance during the familiarization tours to ensure that all required information is presented to LAFD personnel.

LAFD: TA-16 HE Facility Familiarization Tour, OJT 55258

Energy Technology Data Exchange (ETDEWEB)

Rutherford, Victor Stephen [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-05-31

Los Alamos National Laboratory (LANL) will conduct familiarization tours for personnel of the Los Alamos County Fire Department (LAFD) at TA-16 high explosives (HE) facilities. These familiarization tours are official LANL business; the purpose of these tours is to orient LAFD firefighters to the facility so that they can respond efficiently and quickly to a variety of emergency situations. This orientation includes, among other topics, ingress and egress of the area and buildings, layout and organization of the facility, evacuation procedures and assembly points, and areas of concern within the various buildings at the facility. LAFD firefighters have the skills and abilities to perform firefighting operations and other emergency response tasks that cannot be provided by LANL personnel who have the required clearance. This handout provides details of the information, along with maps and diagrams, to be presented during the familiarization tours. The handout will be distributed to the trainees at the time of the tour. A corresponding checklist will also be used as guidance during the familiarization tours to ensure that all required information is presented to LAFD personnel.

Construction Cost Growth for New Department of Energy Nuclear Facilities

Energy Technology Data Exchange (ETDEWEB)

Kubic, Jr., William L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2014-05-25

Cost growth and construction delays are problems that plague many large construction projects including the construction of new Department of Energy (DOE) nuclear facilities. A study was conducted to evaluate cost growth of large DOE construction projects. The purpose of the study was to compile relevant data, consider the possible causes of cost growth, and recommend measures that could be used to avoid extreme cost growth in the future. Both large DOE and non-DOE construction projects were considered in this study. With the exception of Chemical and Metallurgical Research Building Replacement Project (CMRR) and the Mixed Oxide Fuel Fabrication Facility (MFFF), cost growth for DOE Nuclear facilities is comparable to the growth experienced in other mega construction projects. The largest increase in estimated cost was found to occur between early cost estimates and establishing the project baseline during detailed design. Once the project baseline was established, cost growth for DOE nuclear facilities was modest compared to non-DOE mega projects.

Hot helium flow test facility summary report

International Nuclear Information System (INIS)

1980-06-01

This report summarizes the results of a study conducted to assess the feasibility and cost of modifying an existing circulator test facility (CTF) at General Atomic Company (GA). The CTF originally was built to test the Delmarva Power and Light Co. steam-driven circulator. This circulator, as modified, could provide a source of hot, pressurized helium for high-temperature gas-cooled reactor (HTGR) and gas-cooled fast breeder reactor (GCFR) component testing. To achieve this purpose, a high-temperature impeller would be installed on the existing machine. The projected range of tests which could be conducted for the project is also presented, along with corresponding cost considerations

Pool water cleaning facility

Energy Technology Data Exchange (ETDEWEB)

Yoshikawa, Kazuhiro; Kinoshita, Shoichiro [Hitachi Ltd., Tokyo (Japan); Asano, Takashi

1998-05-29

Only one system comprising a suppression poor water cleaning system (SPCU) and a filtration desalting tower (F/D) is connected for a plurality of nuclear power plants. Pipelines/valves for connecting the one system of the SPCU pump, the F/D and the plurality of nuclear power plants are disposed, and the system is used in common with the plurality of nuclear power plants. Pipelines/valves for connecting a pipeline for passing SP water to the commonly used SPCU pump and a skimmer surge tank are disposed, and fuel pool water is cooled and cleaned by the commonly used SPCU pump and the commonly used F/D. The number of SPCU pumps and the F/D facilities can be reduced, and a fuel pool water cooling operation mode and a fuel pool water cleaning operation mode which were conducted by an FPC pump so far are conducted by the SPCU pump. (N.H.)

Ecological Realism of U.S. EPA Experimental Stream Facility Studies

Science.gov (United States)

The USEPA’s Experimental Stream Facility (ESF) conducts meso-scale ecotoxicology studies that account for both structural and functional responses of whole stream communities to contaminants or other stressors. The 16 mesocosms of ESF are indoors and consist of a tiled run sectio...

Facile Preparation of Carbon-Nanotube-based 3-Dimensional Transparent Conducting Networks for Flexible Noncontact Sensing Device

KAUST Repository

Tai, Yanlong; Lubineau, Gilles

2016-01-01

Here, we report the controllable fabrication of transparent conductive films (TCFs) for moisture-sensing applications based on heating-rate-triggered, 3-dimensional porous conducting networks of single-walled carbon nanotube (SWCNT)/poly(3

Status and Prospect of Safeguards By Design for Pyroprocessing Facility

International Nuclear Information System (INIS)

Kim, Ho-Dong; Shin, H.S.; Ahn, S.K.

2010-01-01

The concept of Safeguards-By-Design (SBD), which is proposed and developed by the United States and the IAEA, is now widely acknowledged as a fundamental consideration for the effective and efficient implementation of safeguards. The application of a SBD concept is of importance especially for developmental nuclear facilities which have new technological features and relevant challenges to their safeguards approach. At this point of time, the examination of the applicability of SBD on a pyroprocessing facility, which has been being developed in the Republic of Korea (ROK), would be meaningful. The ROK developed a safeguards system with the concept of SBD for Advanced spent fuel Conditioning Process Facility (ACPF) and DUPIC Fuel Development Facility (DFDF) before the SBD concept was formally suggested. Currently. The PRIDE (PyRoprocess Integrated Inactive Demonstration) facility for the demonstration of pyroprocess using 10 ton of non-radioactive nuclear materials per year is being constructed in the ROK. The safeguards system for the facility has been designed in cooperation with a facility designer from the design phase, and the safeguards system would be established according to the future construction schedule. In preparing the design of Engineering Scale Pyroprocess Facility (ESPF), which will use spent fuels in an engineering scale and be constructed in 2016, a research on the safeguards system for this facility is also being conducted. In this connection, a project to support for development of safeguards approach for a reference pyroprocessing facility has been carried out by KAERI in cooperation with KINAC and the IAEA through an IAEA Member State Support Program (MSSP). When this MSSP project is finished in August, 2011, a safeguards system model and safeguards approach for a reference pyroprocessing facility would be established. Maximizing these early experiences and results, a safeguards system of ESPF based on the concept of SBD would be designed and

The choice of Park & Ride Facilities: an analysis using a context-dependent hierarchical choice experiment

OpenAIRE

Heijden, R.E.C.M. van der; Molin, E.J.E.; Timmermans, H.J.P.

2004-01-01

Park and Ride facilities have been proposed in several countries to alleviate the accessibility problems in cities. Despite growing accessibility problems, these facilities do not seem to attract the expected number of car drivers and are under-used. In an attempt to measure consumer evaluations of the attributes of Park and Ride facilities, a stated choice experiment, based on the method of hierarchical information integration, was conducted in the city of Nijmegen, The Netherlands. This pap...

Facility effluent monitoring plan for the 325 Facility

International Nuclear Information System (INIS)

1998-01-01

The Applied Chemistry Laboratory (325 Facility) houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and mixed hazardous waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials, and a waste treatment facility for processing hazardous, mixed, low-level, and transuranic wastes generated by Pacific Northwest Laboratory. Radioactive material storage and usage occur throughout the facility and include a large number of isotopes. This material is in several forms, including solid, liquid, particulate, and gas. Some of these materials are also heated during testing which can produce vapors. The research activities have been assigned to the following activity designations: High-Level Hot Cell, Hazardous Waste Treatment Unit, Waste Form Development, Special Testing Projects, Chemical Process Development, Analytical Hot Cell, and Analytical Chemistry. The following summarizes the airborne and liquid effluents and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

Counterpart experimental study of ISP-42 PANDA tests on PUMA facility

International Nuclear Information System (INIS)

Yang, Jun; Choi, Sung-Won; Lim, Jaehyok; Lee, Doo-Yong; Rassame, Somboon; Hibiki, Takashi; Ishii, Mamoru

2013-01-01

Highlights: ► Counterpart tests were performed on two large-scale BWR integral facilities. ► Similarity of post-LOCA system behaviors observed between two tests. ► Passive core and containment cooling systems work as design in both tests. -- Abstract: A counterpart test to the Passive Nachwärmeabfuhr und Druckabbau Test Anlage (Passive Decay Heat Removal and Depressurization Test Facility, PANDA) International Standard Problem (ISP)-42 test was conducted at the Purdue University Multi-Dimensional Integral Test Assembly (PUMA) facility. Aimed to support code validation on a range of light water reactor (LWR) containment issues, the ISP-42 test consists of six sequential phases (Phases A–F) with separately defined initial and boundary conditions, addressing different stages of anticipated accident scenario and system responses. The counterpart test was performed from Phases A to D, which are within the scope of the normal integral tests performed on the PUMA facility. A scaling methodology was developed by using the PANDA facility as prototype and PUMA facility as test model, and an engineering scaling has been applied to the PUMA facility. The counterpart test results indicated that functions of passive safety systems, such as passive containment cooling system (PCCS) start-up, gravity-driven cooling system (GDCS) discharge, PCCS normal operation and overload function were confirmed in both the PANDA and PUMA facilities with qualitative similarities

Air Quality Facilities

Data.gov (United States)

Iowa State University GIS Support and Research Facility — Facilities with operating permits for Title V of the Federal Clean Air Act, as well as facilities required to submit an air emissions inventory, and other facilities...

Facilities Performance Indicators Report, 2004-05. Facilities Core Data Survey

Science.gov (United States)

Glazner, Steve, Ed.

2006-01-01

The purpose of "Facilities Performance Indicators" is to provide a representative set of statistics about facilities in educational institutions. The second iteration of the web-based Facilities Core Data Survey was posted and available to facilities professionals at more than 3,000 institutions in the Fall of 2005. The website offered a printed…

High-risk facilities. Emergency management in nuclear, chemical and hazardous waste facilities

International Nuclear Information System (INIS)

Kloepfer, Michael

2012-01-01

The book on emergency management in high-risk facilities covers the following topics: Change in the nuclear policy, risk management of high-risk facilities as a constitutional problem - emergency management in nuclear facilities, operational mechanisms of risk control in nuclear facilities, regulatory surveillance responsibilities for nuclear facilities, operational mechanism of the risk control in chemical plants, regulatory surveillance responsibilities for chemical facilities, operational mechanisms of the risk control in hazardous waste facilities, regulatory surveillance responsibilities for hazardous waste facilities, civil law consequences in case of accidents in high-risk facilities, criminal prosecution in case of accidents in high-risk facilities, safety margins as site risk for emission protection facilities, national emergency management - strategic emergency management structures, warning and self-protection of the public in case of CBRN hazards including aspects of the psych-social emergency management.

PUREX facility hazards assessment

International Nuclear Information System (INIS)

Sutton, L.N.

1994-01-01

This report documents the hazards assessment for the Plutonium Uranium Extraction Plant (PUREX) located on the US Department of Energy (DOE) Hanford Site. Operation of PUREX is the responsibility of Westinghouse Hanford Company (WHC). This hazards assessment was conducted to provide the emergency planning technical basis for PUREX. DOE Order 5500.3A requires an emergency planning hazards assessment for each facility that has the potential to reach or exceed the lowest level emergency classification. In October of 1990, WHC was directed to place PUREX in standby. In December of 1992 the DOE Assistant Secretary for Environmental Restoration and Waste Management authorized the termination of PUREX and directed DOE-RL to proceed with shutdown planning and terminal clean out activities. Prior to this action, its mission was to reprocess irradiated fuels for the recovery of uranium and plutonium. The present mission is to establish a passively safe and environmentally secure configuration at the PUREX facility and to preserve that condition for 10 years. The ten year time frame represents the typical duration expended to define, authorize and initiate follow-on decommissioning and decontamination activities

Phase II Investigation at the Former CCC/USDA Grain Storage Facility in Savannah, Missouri

Energy Technology Data Exchange (ETDEWEB)

LaFreniere, Lorraine M. [Argonne National Lab. (ANL), Argonne, IL (United States). Environmental Science Division. Applied Geosciences and Environmental Management Section

2012-05-01

From approximately 1949 until 1970, the Commodity Credit Corporation of the U.S. Department of Agriculture (CCC/USDA) operated a grain storage facility on federally owned property approximately 0.25 mi northwest of Savannah, Missouri. During this time, commercial grain fumigants containing carbon tetrachloride were commonly used by the CCC/USDA and the private grain storage industry to preserve grain in their facilities. In November 1998, carbon tetrachloride was detected in a private well (Morgan) roughly 50 ft south of the former CCC/USDA facility, as a result of statewide screening of private wells near former CCC/USDA facilities, conducted in Missouri by the U.S. Environmental Protection Agency (EPA 1999). The 1998 and subsequent investigations by the EPA and the Missouri Department of Natural Resources (MDNR) confirmed the presence of carbon tetrachloride in the Morgan well, as well as in a second well on property currently owned by the Missouri Department of Transportation (MoDOT), directly east of the former CCC/USDA facility. The identified concentrations in these two wells were above the EPA maximum contaminant level (MCL) and the Missouri risk-based corrective action default target level (DTL) values of 5.0 μg/L for carbon tetrachloride in water used for domestic purposes (EPA 1999; MDNR 2000a,b, 2006). Because the observed contamination in the Morgan and MoDOT wells might be linked to the past use of carbon tetrachloride-based fumigants at its former grain storage facility, the CCC/USDA is conducting an investigation to (1) characterize the source(s), extent, and factors controlling the subsurface distribution and movement of carbon tetrachloride and (2) evaluate the potential risks to human health, public welfare, and the environment posed by the contamination. This work is being performed in accord with an Intergovernmental Agreement established in 2007 between the Farm Service Agency of the USDA and the MDNR, to address carbon tetrachloride

Status and Plans for a Superconducting RF Accelerator Test Facility at Fermilab

International Nuclear Information System (INIS)

Andrews, R.; Baffes, C.M.; Carlson, K.; Chase, B.; Church, M.D.; Harms, E.R.; Klebaner, A.L.; Leibfritz, J.R.; Martinez, A.; Nagaitsev, S.; Nobrega, L.E.

2012-01-01

The Advanced Superconducting Test Accelerator (ASTA) is being constructed at Fermilab. The existing New Muon Lab (NML) building is being converted for this facility. The accelerator will consist of an electron gun, injector, beam acceleration section consisting of 3 TTF-type or ILC-type cryomodules, multiple downstream beam lines for testing diagnostics and conducting various beam tests, and a high power beam dump. When completed, it is envisioned that this facility will initially be capable of generating a 750 MeV electron beam with ILC beam intensity. An expansion of this facility was recently completed that will provide the capability to upgrade the accelerator to a total beam energy of 1.5 GeV. Two new buildings were also constructed adjacent to the ASTA facility to house a new cryogenic plant and multiple superconducting RF (SRF) cryomodule test stands. In addition to testing accelerator components, this facility will be used to test RF power systems, instrumentation, and control systems for future SRF accelerators such as the ILC and Project-X. This paper describes the current status and overall plans for this facility.

Cryogenic Thermal Conductivity Measurements on Candidate Materials for Space Missions

Science.gov (United States)

Tuttle, JIm; Canavan, Ed; Jahromi, Amir

2017-01-01

Spacecraft and instruments on space missions are built using a wide variety of carefully-chosen materials. In addition to having mechanical properties appropriate for surviving the launch environment, these materials generally must have thermal conductivity values which meet specific requirements in their operating temperature ranges. Space missions commonly propose to include materials for which the thermal conductivity is not well known at cryogenic temperatures. We developed a test facility in 2004 at NASAs Goddard Space Flight Center to measure material thermal conductivity at temperatures between 4 and 300 Kelvin, and we have characterized many candidate materials since then. The measurement technique is not extremely complex, but proper care to details of the setup, data acquisition and data reduction is necessary for high precision and accuracy. We describe the thermal conductivity measurement process and present results for several materials.

Nuclear facilities

International Nuclear Information System (INIS)

Anon.

2000-01-01

Here is given the decree (2000-1065) of the 25. of October 2000 reporting the publication of the convention between the Government of the French Republic and the CERN concerning the safety of the LHC (Large Hadron Collider) and the SPS (Proton Supersynchrotron) facilities, signed in Geneva on July 11, 2000. By this convention, the CERN undertakes to ensure the safety of the LHC and SPS facilities and those of the operations of the LEP decommissioning. The French legislation and regulations on basic nuclear facilities (concerning more particularly the protection against ionizing radiations, the protection of the environment and the safety of facilities) and those which could be decided later on apply to the LHC, SPS and auxiliary facilities. (O.M.)

Facility effluent monitoring plan for 242-A Evaporator facility

International Nuclear Information System (INIS)

Crummel, G.M.; Gustavson, R.D.

1993-03-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1* for any operations that involve hazardous materials and radioactive substances that could affect employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation showed the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility effluent Monitoring Plans, WHC-EP-0438-1**. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

HYTEST Phase I Facility Commissioning and Modeling

Energy Technology Data Exchange (ETDEWEB)

Lee P. Shunn; Richard D. Boardman; Shane J. Cherry; Craig G. Rieger

2009-09-01

The purpose of this document is to report the first year accomplishments of two coordinated Laboratory Directed Research and Development (LDRD) projects that utilize a hybrid energy testing laboratory that couples various reactors to investigate system reactance behavior. This work is the first phase of a series of hybrid energy research and testing stations - referred to hereafter as HYTEST facilities – that are planned for construction and operation at the Idaho National Laboratory (INL). A HYTEST Phase I facility was set up and commissioned in Bay 9 of the Bonneville County Technology Center (BCTC). The purpose of this facility is to utilize the hydrogen and oxygen that is produced by the High Temperature Steam Electrolysis test reactors operating in Bay 9 to support the investigation of kinetic phenomena and transient response of integrated reactor components. This facility provides a convenient scale for conducting scoping tests of new reaction concepts, materials performance, new instruments, and real-time data collection and manipulation for advance process controls. An enclosed reactor module was assembled and connected to a new ventilation system equipped with a variable-speed exhaust blower to mitigate hazardous gas exposures, as well as contract with hot surfaces. The module was equipped with a hydrogen gas pump and receiver tank to supply high quality hydrogen to chemical reactors located in the hood.

Integration of Biosafety into Core Facility Management

Science.gov (United States)

Fontes, Benjamin

2013-01-01

This presentation will discuss the implementation of biosafety policies for small, medium and large core laboratories with primary shared objectives of ensuring the control of biohazards to protect core facility operators and assure conformity with applicable state and federal policies, standards and guidelines. Of paramount importance is the educational process to inform core laboratories of biosafety principles and policies and to illustrate the technology and process pathways of the core laboratory for biosafety professionals. Elevating awareness of biohazards and the biosafety regulatory landscape among core facility operators is essential for the establishment of a framework for both project and material risk assessment. The goal of the biohazard risk assessment process is to identify the biohazard risk management parameters to conduct the procedure safely and in compliance with applicable regulations. An evaluation of the containment, protective equipment and work practices for the procedure for the level of risk identified is facilitated by the establishment of a core facility registration form for work with biohazards and other biological materials with potential risk. The final step in the biocontainment process is the assumption of Principal Investigator role with full responsibility for the structure of the site-specific biosafety program plan by core facility leadership. The presentation will provide example biohazard protocol reviews and accompanying containment measures for core laboratories at Yale University.

Calculation of displacement and helium production at the Clinton P. Anderson Los Alamos Meson Physics Facility (LAMPF) irradiation facility

International Nuclear Information System (INIS)

Wechsler, M.S.; Davidson, D.R.; Greenwood, L.R.; Sommer, W.F.

1984-01-01

CT: Differential and total displacement and helium production rates are calculated for copper irradiated by spallation neutrons and 760 MeV protons at the Clinton P. Anderson Los Alamos Meson Physics Facility (LAMPF). The calculations are performed using the SPECTER and VNMTC computer codes, the latter being specially designed for spallation radiation damage calculations. For comparison, similar SPECTER calculations are also described for irradiation of copper in EBR-II and RTNS-II. The results indicate substantial contributions to the displacement and helium production rates due to neutrons in the high-energy tail (above 20 MeV) of the LAMPF spallation neutron spectrum. Still higher production rates are calculated for irradiations in the direct proton beam. These results will provide useful background information for research to be conducted at a new irradiation facility at LAMPF

Development of Facilities Master Plan and Laboratory Renovation Project

Energy Technology Data Exchange (ETDEWEB)

Fox, Andrea D

2011-10-03

Funding from this grant has allowed Morehouse School of Medicine to complete its first professionally developed, comprehensive campus master plan that is in alignment with the recently completed strategic plan. In addition to master planning activities, funds were used for programming and designing research renovations, and also to supplement other research facility upgrades by providing lighting and equipment. The activities funded by this grant will provide the catalyst for substantial improvement in the School's overall facilities for biomedical education and research, and will also provide much of the information needed to conduct a successful campaign to raise funds for proposed buildings and renovations.

Case study : a transformer repair facility

Energy Technology Data Exchange (ETDEWEB)

Jerade, L. [Jacques Whitford Environment Ltd., Vancouver, BC (Canada)

2006-07-01

Polychlorinated biphenyls (PCBs) are synthetic chemical compounds consisting of chlorine, carbon and hydrogen. They are very stable, fire resistant, do not conduct electricity and have low volatility at normal temperatures. They were mainly used as a cooling and insulating fluid for industrial transformers and capacitors. Some of the same properties that made PCBs so widely used, also make them environmentally hazardous, especially their extreme resistance to chemical and biological breakdown by natural processes in the environment. Typical chemicals associated with the presence of PCB oils are chlorobenzene, lead, xylene, and petroleum hydrocarbons. A case study of a transformer repair facility was discussed along with its soil and groundwater remediation. This presentation discussed the delineation program for the site which operated as a repair facility of PCB-containing transformers from 1968 until 1998. The property was bought by Siemens Canada Ltd. in 1998 and was sold in 2004. As part of the purchasing agreement, a Certificate of Compliance from the British Columbia Ministry of Environment was required. Remediation work was therefore needed. The presentation also covered: zones of contamination and contaminants of concern, soil impacts, groundwater impacts, and an evaluation of remediation options. In-situ treatment of soil with hydrogen peroxide and the selected remedial option were discussed. A soil economic analysis was also conducted. Last, challenges, solutions, and conclusions were presented. tabs., figs.

Referral of children seeking care at private health facilities in Uganda

DEFF Research Database (Denmark)

Mbonye, Anthony K.; Buregyeya, Esther; Rutebemberwa, Elizeus

2017-01-01

Background In Uganda, referral of sick children seeking care at public health facilities is poor and widely reported. However, studies focusing on the private health sector are scanty. The main objective of this study was to assess referral practices for sick children seeking care at private health...... facilities in order to explore ways of improving treatment and referral of sick children in this sector. Methods A survey was conducted from August to October 2014 in Mukono district, central Uganda. Data was collected using a structured questionnaire supplemented by Focus Group Discussions and Key Informant...... interviews with private providers and community members. Results A total of 241 private health facilities were surveyed; 170 (70.5%) were registered drug shops, 59 (24.5%) private clinics and 12 (5.0%) pharmacies. Overall, 104/241 (43.2%) of the private health facilities reported that they had referred sick...

North Slope, Alaska ESI: FACILITY (Facility Points)

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — This data set contains data for oil field facilities for the North Slope of Alaska. Vector points in this data set represent oil field facility locations. This data...

Thermal effects of electrically conductive deposits in melter

International Nuclear Information System (INIS)

Choi, I.G.; Bickford, D.F.; Carter, J.T.

1992-01-01

The radioactive waste processed by the Defense Waste Processing Facility melter at the Savannah river Site contains noble metal fission-products. Operation of waste-glass melters treating commercial power reactor wastes indicates that accumulation of noble metals on melter floors can lead to distortion of electric heating patterns, loss of power, and possible electrode damage. Changes in melter geometry have been developed in Japan and Germany to minimize these effects. The two existing melters for the US Department of Energy's Defense Waste Processing Facility were designed in 1982, before this effect was known or had been characterized. Modeling and pilot scale tests are being conducted in the Integrated DWPF melter system to determine if the effect is significant for melters processing defense wastes, and if the effect can be diagnosed and corrected without significant damage or changes to the melter design. This document provides a discussion of these tests

Public Private Partnership Benefits in Delivering Public Facilities in Malaysia

Directory of Open Access Journals (Sweden)

Sapri M.

2016-01-01

Full Text Available The development of infrastructure in developing country such as Malaysia was increasingly founded by the Public–Private Partnership (PPP scheme. Collaboration with private sector has become popular as a means to improve the delivery of public facilities. Yet, empirical evidence on how PPP initiative has benefits the delivery of public facilities within Malaysia context is lagging. The purpose of this paper is to identify and assess the perception of stakeholders on the benefits of adopting PPP in delivering public facilities in Malaysia. Literature review was carried out to identify PPP benefits, which were then incorporated into the questionnaire. The mean score and mean score ranking was conducted to assess the agreement level of stakeholders towards the PPP benefits. The overall findings show that the implementation of PPP has benefitted the delivery of public facilities in both financial and non-financial aspects. From the analysis, improvement in service quality is perceived as the top advantage followed by innovation in design and transfer of risk. The findings provide more informed basis on the rationale of PPP implementation and its potential in improving the delivery of public facilities within Malaysia context.

Evaluation of seismic criteria used in design of INEL facilities

International Nuclear Information System (INIS)

Young, G.A.

1977-01-01

This report provides the results of an independent evaluation of seismic studies that were made to establish the seismic acceleration levels and the response spectra used in the design of vital facilities at Idaho National Engineering Laboratory. A comparison of the procedures used to define the seismic acceleration values and response spectra at INEL with the requirements of the Nuclear Regulatory Commission showed that additional geologic studies would probably be required in order to fulfill NRC regulations. Recommendations are made on justifiable changes in the acceleration values and response spectra used at INEL. The geologic, geophysical, and seismological studies needed to provide a better understanding of the tectonic processes in the Snake River plains and the surrounding region are identified. Both potential and historical acceleration values are evaluated on a probability basis to permit a risk assessment approach to the design of new facilities and facility modifications. Studies conducted to develop seismic criteria for the design of the Loss of Fluid Test reactor and the New Waste Calcining Facility were selected as typical examples of criteria development previously used in the design of INEL facilities

Experiments to determine the migration potential for water and contaminants in shallow land burial facilities design, emplacement, and preliminary results

International Nuclear Information System (INIS)

DePoorter, G.L.; Abeele, W.V.; Burton, B.W.

1982-01-01

Leaching and transport of radionuclides by water has been a primary mode of radioactive contamination from low-level radioactive waste disposal facilities. Similarly, the infiltration of water into nonradioactive hazardous waste disposal facilities has resulted in the movement of contaminants out of these disposal facilities. Although there have been many laboratory studies on water movement and contaminant transport, there is a need for more large scale field experiments. Large scale field experiments are necessary to (1) measure hydraulic conductivities on a scale typical of actual shallow land burial facilities and hazardous waste disposal facilities, (2) allow comparisons to be made between full scale and laboratory measurements, (3) verify the applicability of calculational methods for determining unsaturated hydraulic conductivities from water retention curves, and (4) for model validation. Experiments that will provide the information to do this are described in this paper

Photoproduction and Radiative Decay of eta' Meson in CLAS at Jlab

Energy Technology Data Exchange (ETDEWEB)

Mbianda Njencheu, Georgie [Old Dominion Univ., Norfolk, VA (United States); Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States)

2017-05-01

In this work the η' meson photoproduction cross sections as well as the distribution of the di-pion invariant mass, m(π+π-), in the radiative decay mode n' -> π+π-γ have been measured using the CLAS detector at the Thomas Jefferson National Accelerator Facility using tagged incident photons in the center-of-mass energy range 1.96 GeV - 2.72 GeV. The measurements are performed on a liquid hydrogen target in the reaction γ π -> π η'(η'-> π+π-γ). The analysis is based on the highest statistics collected in this decay channel in comparison to other experiments reported so far. The n' photoproduction cross sections measured with radiative decay are in a good agreement with results of previous publication from the same data set in CLAS obtained through η' -> π+π-γ decay mode. Two free parameters, α and Β, are extracted from a model-independent fit to the m(π+π-) distribution and their values are found to agree well with recent theoretical expectations. The results of both parameters confirm the existence of the box anomaly, ρ-ω mixing and effects of the a2(1320) tensor meson in the radiative decay of η'.

Measurement of Outflow Facility Using iPerfusion.

Directory of Open Access Journals (Sweden)

Joseph M Sherwood

Full Text Available Elevated intraocular pressure (IOP is the predominant risk factor for glaucoma, and reducing IOP is the only successful strategy to prevent further glaucomatous vision loss. IOP is determined by the balance between the rates of aqueous humour secretion and outflow, and a pathological reduction in the hydraulic conductance of outflow, known as outflow facility, is responsible for IOP elevation in glaucoma. Mouse models are often used to investigate the mechanisms controlling outflow facility, but the diminutive size of the mouse eye makes measurement of outflow technically challenging. In this study, we present a new approach to measure and analyse outflow facility using iPerfusion™, which incorporates an actuated pressure reservoir, thermal flow sensor, differential pressure measurement and an automated computerised interface. In enucleated eyes from C57BL/6J mice, the flow-pressure relationship is highly non-linear and is well represented by an empirical power law model that describes the pressure dependence of outflow facility. At zero pressure, the measured flow is indistinguishable from zero, confirming the absence of any significant pressure independent flow in enucleated eyes. Comparison with the commonly used 2-parameter linear outflow model reveals that inappropriate application of a linear fit to a non-linear flow-pressure relationship introduces considerable errors in the estimation of outflow facility and leads to the false impression of pressure-independent outflow. Data from a population of enucleated eyes from C57BL/6J mice show that outflow facility is best described by a lognormal distribution, with 6-fold variability between individuals, but with relatively tight correlation of facility between fellow eyes. iPerfusion represents a platform technology to accurately and robustly characterise the flow-pressure relationship in enucleated mouse eyes for the purpose of glaucoma research and with minor modifications, may be applied

The impact of two Department of Energy orders on the design and cost of select plutonium facilities at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Rey, V.C.

1999-01-01

The Los Alamos National Laboratory (LANL) is a research and development facility in northern New Mexico, owned by the federal government and operated for the US Department of Energy (DOE) by the University of California (UC). LANL conducts research and experiments in many arenas including plutonium. Its plutonium facilities are required to meet the facility design and safety criteria of applicable DOE orders as specified in the UC contract. Although DOE 420.1, Facility Safety, superseded DOE 6430.1A, General Design Criteria, the UC contract requires LANL to adhere to DOE 6430.1A, Division 13 in its special nuclear facilities. A comparison of costs and savings relative to installation of double-wall piping at two LANL plutonium facilities is demonstrated. DOE 6430.1A is prescriptive in its design criteria whereas DOE 420.1 is a performance-based directive. The differences in these orders impact time and design costs in nuclear construction projects. LANL's approach to integrated quality and conduct of operations for design, needs to be re-evaluated. In conclusion, there is a need for highly-technical, knowledgeable people and an integrated, quality/conduct of operations-based approach to assure that nuclear facilities are designed and constructed in a safe and cost-effective manner

Environmental, economic, and energy impacts of material recovery facilities. A MITE Program evaluation

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-10-01

This report documents an evaluation of the environmental, economic, and energy impacts of material recovery facilities (MRFs) conducted under the Municipal Solid Waste Innovative Technology Evaluation (MITE) Program. The MITE Program is sponsored by the US Environmental Protection Agency to foster the demonstration and development of innovative technologies for the management of municipal solid waste (MSW). This project was also funded by the National Renewable Energy Laboratory (NREL). Material recovery facilities are increasingly being used as one option for managing a significant portion of municipal solid waste (MSW). The owners and operators of these facilities employ a combination of manual and mechanical techniques to separate and sort the recyclable fraction of MSW and to transport the separated materials to recycling facilities.

Environmental monitoring of subsurface low-level waste disposal facilities at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Ashwood, T.L.; Hicks, D.S.

1992-01-01

Oak Ridge National Laboratory (ORNL) generates low-level waste (LLW) as part of its research and isotope production activities. This waste is managed in accordance with US Department of Energy (DOE) Order 5820.2A. Solid LLW management includes disposal in above-ground, tumulus-type facilities as well as in various types of subsurface facilities. Since 1986, subsurface disposal has been conducted using various designs employing greater-confinement-disposal (GCD) techniques. The purpose of this paper is to present monitoring results that document the short-term performance of these GCD facilities

Procedure of uranium mine and mill facilities decommissioning work

International Nuclear Information System (INIS)

Li Renjie

1995-01-01

The procedure of decommissioning work of uranium mine and mill facilities includes three stages: preparation, on-the-spot construction and acceptance after being completed. The first stage, preparation, is discussed in detail, and it is presented to take the measures of strengthening leadership and improving leading body to conduct the decommissioning work best

National Ignition Facility project acquisition plan

International Nuclear Information System (INIS)

Callaghan, R.W.

1996-04-01

The purpose of this National Ignition Facility Acquisition Plan is to describe the overall procurement strategy planned for the National Ignition Facility (NIF) Project. The scope of the plan describes the procurement activities and acquisition strategy for the following phases of the NIF Project, each of which receives either plant and capital equipment (PACE) or other project cost (OPC) funds: Title 1 and 2 design and Title 3 engineering (PACE); Optics manufacturing facilitization and pilot production (OPC); Convention facility construction (PACE); Procurement, installation, and acceptance testing of equipment (PACE); and Start-up (OPC). Activities that are part of the base Inertial Confinement Fusion (ICF) Program are not included in this plan. The University of California (UC), operating Lawrence Livermore National Laboratory (LLNL) and Los Alamos National Laboratory, and Lockheed-Martin, which operates Sandia National Laboratory (SNL) and the University of Rochester Laboratory for Laser Energetics (UR-LLE), will conduct the acquisition of needed products and services in support of their assigned responsibilities within the NIF Project structure in accordance with their prime contracts with the Department of Energy (DOE). LLNL, designated as the lead Laboratory, will have responsibility for all procurements required for construction, installation, activation, and startup of the NIF

26 CFR 1.142(a)(5)-1 - Exempt facility bonds: Sewage facilities.

Science.gov (United States)

2010-04-01

... 26 Internal Revenue 2 2010-04-01 2010-04-01 false Exempt facility bonds: Sewage facilities. 1.142... Bonds § 1.142(a)(5)-1 Exempt facility bonds: Sewage facilities. (a) In general. Under section 103(a), a... in section 142(a) is a sewage facility. This section defines the term sewage facility for purposes of...

Cost-of-illness of cholera to households and health facilities in rural Malawi.

Directory of Open Access Journals (Sweden)

Patrick G Ilboudo

Full Text Available Cholera remains an important public health problem in many low- and middle-income countries. Vaccination has been recommended as a possible intervention for the prevention and control of cholera. Evidence, especially data on disease burden, cost-of-illness, delivery costs and cost-effectiveness to support a wider use of vaccine is still weak. This study aims at estimating the cost-of-illness of cholera to households and health facilities in Machinga and Zomba Districts, Malawi. A cross-sectional study using retrospectively collected cost data was undertaken in this investigation. One hundred patients were purposefully selected for the assessment of the household cost-of-illness and four cholera treatment centres and one health facility were selected for the assessment conducted in health facilities. Data collected for the assessment in households included direct and indirect costs borne by cholera patients and their families while only direct costs were considered for the assessment conducted in health facilities. Whenever possible, descriptive and regression analysis were used to assess difference in mean costs between groups of patients. The average costs to patients' households and health facilities for treating an episode of cholera amounted to US$65.6 and US$59.7 in 2016 for households and health facilities, respectively equivalent to international dollars (I$ 249.9 and 227.5 the same year. Costs incurred in treating a cholera episode were proportional to duration of hospital stay. Moreover, 52% of households used coping strategies to compensate for direct and indirect costs imposed by the disease. Both households and health facilities could avert significant treatment expenditures through a broader use of pre-emptive cholera vaccination. These findings have direct policy implications regarding priority investments for the prevention and control of cholera.

Cost-of-illness of cholera to households and health facilities in rural Malawi.

Science.gov (United States)

Ilboudo, Patrick G; Huang, Xiao Xian; Ngwira, Bagrey; Mwanyungwe, Abel; Mogasale, Vittal; Mengel, Martin A; Cavailler, Philippe; Gessner, Bradford D; Le Gargasson, Jean-Bernard

2017-01-01

Cholera remains an important public health problem in many low- and middle-income countries. Vaccination has been recommended as a possible intervention for the prevention and control of cholera. Evidence, especially data on disease burden, cost-of-illness, delivery costs and cost-effectiveness to support a wider use of vaccine is still weak. This study aims at estimating the cost-of-illness of cholera to households and health facilities in Machinga and Zomba Districts, Malawi. A cross-sectional study using retrospectively collected cost data was undertaken in this investigation. One hundred patients were purposefully selected for the assessment of the household cost-of-illness and four cholera treatment centres and one health facility were selected for the assessment conducted in health facilities. Data collected for the assessment in households included direct and indirect costs borne by cholera patients and their families while only direct costs were considered for the assessment conducted in health facilities. Whenever possible, descriptive and regression analysis were used to assess difference in mean costs between groups of patients. The average costs to patients' households and health facilities for treating an episode of cholera amounted to US$65.6 and US$59.7 in 2016 for households and health facilities, respectively equivalent to international dollars (I$) 249.9 and 227.5 the same year. Costs incurred in treating a cholera episode were proportional to duration of hospital stay. Moreover, 52% of households used coping strategies to compensate for direct and indirect costs imposed by the disease. Both households and health facilities could avert significant treatment expenditures through a broader use of pre-emptive cholera vaccination. These findings have direct policy implications regarding priority investments for the prevention and control of cholera.

Life-Cycle Assessments of Selected NASA Ground-Based Test Facilities

Science.gov (United States)

Sydnor, George Honeycutt

2012-01-01

In the past two years, two separate facility-specific life cycle assessments (LCAs) have been performed as summer student projects. The first project focused on 13 facilities managed by NASA s Aeronautics Test Program (ATP), an organization responsible for large, high-energy ground test facilities that accomplish the nation s most advanced aerospace research. A facility inventory was created for each facility, and the operational-phase carbon footprint and environmental impact were calculated. The largest impacts stemmed from electricity and natural gas used directly at the facility and to generate support processes such as compressed air and steam. However, in specialized facilities that use unique inputs like R-134a, R-14, jet fuels, or nitrogen gas, these sometimes had a considerable effect on the facility s overall environmental impact. The second LCA project was conducted on the NASA Ames Arc Jet Complex and also involved creating a facility inventory and calculating the carbon footprint and environmental impact. In addition, operational alternatives were analyzed for their effectiveness at reducing impact. Overall, the Arc Jet Complex impact is dominated by the natural-gas fired boiler producing steam on-site, but alternatives were provided that could reduce the impact of the boiler operation, some of which are already being implemented. The data and results provided by these LCA projects are beneficial to both the individual facilities and NASA as a whole; the results have already been used in a proposal to reduce carbon footprint at Ames Research Center. To help future life cycle projects, several lessons learned have been recommended as simple and effective infrastructure improvements to NASA, including better utility metering and data recording and standardization of modeling choices and methods. These studies also increased sensitivity to and appreciation for quantifying the impact of NASA s activities.

Facility transition instruction

International Nuclear Information System (INIS)

Morton, M.R.

1997-01-01

The Bechtel Hanford, Inc. facility transition instruction was initiated in response to the need for a common, streamlined process for facility transitions and to capture the knowledge and experience that has accumulated over the last few years. The instruction serves as an educational resource and defines the process for transitioning facilities to long-term surveillance and maintenance (S and M). Generally, these facilities do not have identified operations missions and must be transitioned from operational status to a safe and stable configuration for long-term S and M. The instruction can be applied to a wide range of facilities--from process canyon complexes like the Plutonium Uranium Extraction Facility or B Plant, to stand-alone, lower hazard facilities like the 242B/BL facility. The facility transition process is implemented (under the direction of the US Department of Energy, Richland Operations Office [RL] Assistant Manager-Environmental) by Bechtel Hanford, Inc. management, with input and interaction with the appropriate RL division and Hanford site contractors as noted in the instruction. The application of the steps identified herein and the early participation of all organizations involved are expected to provide a cost-effective, safe, and smooth transition from operational status to deactivation and S and M for a wide range of Hanford Site facilities

Assistance Dogs: Historic Patterns and Roles of Dogs Placed by ADI or IGDF Accredited Facilities and by Non-Accredited U.S. Facilities.

Science.gov (United States)

Walther, Sandra; Yamamoto, Mariko; Thigpen, Abigail Paige; Garcia, Anaissa; Willits, Neil H; Hart, Lynette A

2017-01-01

Dogs' roles to support people with disabilities are increasing. Existing U.S. laws and regulations pertaining to the use of dogs for people with disabilities are only minimally enforced. Pushback legislation against some aspects of uses of assistance dogs currently is being passed or proposed in several states. Further, the U.S. Department of the Army and the Veterans' Administration support only dogs trained by an Assistance Dogs International (ADI) or International Guide Dog Federation (IGDF) accredited facility. Lacking a mandatory national process for screening the selection, training, and placement of assistance dogs with persons who have disabilities, the U.S. offers a creative but confusing opportunity for people to train their own dogs for any disability. While no U.S. surveillance system monitors assistance dogs, other countries generally have a legislated or regulatory process for approving assistance dogs or a cultural convention for obtaining dogs from accredited facilities. We conducted an online survey investigating current demographics of assistance dogs placed in 2013 and 2014 with persons who have disabilities, by facilities worldwide that are associated with ADI or IGDF and by some non-accredited U.S. facilities. Placement data from ADI and IGDF facilities revealed that in most countries aside from the U.S., guide dogs were by far the main type of assistance dog placed. In the U.S., there were about equal numbers of mobility and guide dogs placed, including many placed by large older facilities, along with smaller numbers of other types of assistance dogs. In non-accredited U.S. facilities, psychiatric dogs accounted for most placements. Dogs for families with an autistic child were increasing in all regions around the world. Of dog breeds placed, accredited facilities usually mentioned Labrador Retrievers and Golden Retrievers, and sometimes, German Shepherd Dogs. The facilities bred their dogs in-house, or acquired them from certain breeders

Hazards assessment for the Waste Experimental Reduction Facility

International Nuclear Information System (INIS)

Calley, M.B.; Jones, J.L. Jr.

1994-01-01

This report documents the hazards assessment for the Waste Experimental Reduction Facility (WERF) located at the Idaho National Engineering Laboratory, which is operated by EG ampersand G Idaho, Inc., for the US Department of Energy (DOE). The hazards assessment was performed to ensure that this facility complies with DOE and company requirements pertaining to emergency planning and preparedness for operational emergencies. DOE Order 5500.3A requires that a facility-specific hazards assessment be performed to provide the technical basis for facility emergency planning efforts. This hazards assessment was conducted in accordance with DOE Headquarters and DOE Idaho Operations Office (DOE-ID) guidance to comply with DOE Order 5500.3A. The hazards assessment identifies and analyzes hazards that are significant enough to warrant consideration in a facility's operational emergency management program. This hazards assessment describes the WERF, the area surrounding WERF, associated buildings and structures at WERF, and the processes performed at WERF. All radiological and nonradiological hazardous materials stored, used, or produced at WERF were identified and screened. Even though the screening process indicated that the hazardous materials could be screened from further analysis because the inventory of radiological and nonradiological hazardous materials were below the screening thresholds specified by DOE and DOE-ID guidance for DOE Order 5500.3A, the nonradiological hazardous materials were analyzed further because it was felt that the nonradiological hazardous material screening thresholds were too high

Facilities Performance Indicators Report 2012-13: Tracking Your Facilities Vital Signs

Science.gov (United States)

APPA: Association of Higher Education Facilities Officers, 2014

2014-01-01

This paper features an expanded Web-based "Facilities Performance Indicators (FPI) Report." The purpose of APPA's Facilities Performance Indicators is to provide a representative set of statistics about facilities in educational institutions. "The Facilities Performance Indicators Report" is designed for survey…

Guide to research facilities

Energy Technology Data Exchange (ETDEWEB)

1993-06-01

This Guide provides information on facilities at US Department of Energy (DOE) and other government laboratories that focus on research and development of energy efficiency and renewable energy technologies. These laboratories have opened these facilities to outside users within the scientific community to encourage cooperation between the laboratories and the private sector. The Guide features two types of facilities: designated user facilities and other research facilities. Designated user facilities are one-of-a-kind DOE facilities that are staffed by personnel with unparalleled expertise and that contain sophisticated equipment. Other research facilities are facilities at DOE and other government laboratories that provide sophisticated equipment, testing areas, or processes that may not be available at private facilities. Each facility listing includes the name and phone number of someone you can call for more information.

Experimental Fuels Facility Re-categorization Based on Facility Segmentation

Energy Technology Data Exchange (ETDEWEB)

Reiss, Troy P.; Andrus, Jason

2016-07-01

The Experimental Fuels Facility (EFF) (MFC-794) at the Materials and Fuels Complex (MFC) located on the Idaho National Laboratory (INL) Site was originally constructed to provide controlled-access, indoor storage for radiological contaminated equipment. Use of the facility was expanded to provide a controlled environment for repairing contaminated equipment and characterizing, repackaging, and treating waste. The EFF facility is also used for research and development services, including fuel fabrication. EFF was originally categorized as a LTHC-3 radiological facility based on facility operations and facility radiological inventories. Newly planned program activities identified the need to receive quantities of fissionable materials in excess of the single parameter subcritical limit in ANSI/ANS-8.1, “Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors” (identified as “criticality list” quantities in DOE-STD-1027-92, “Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports,” Attachment 1, Table A.1). Since the proposed inventory of fissionable materials inside EFF may be greater than the single parameter sub-critical limit of 700 g of U-235 equivalent, the initial re-categorization is Hazard Category (HC) 2 based upon a potential criticality hazard. This paper details the facility hazard categorization performed for the EFF. The categorization was necessary to determine (a) the need for further safety analysis in accordance with LWP-10802, “INL Facility Categorization,” and (b) compliance with 10 Code of Federal Regulations (CFR) 830, Subpart B, “Safety Basis Requirements.” Based on the segmentation argument presented in this paper, the final hazard categorization for the facility is LTHC-3. Department of Energy Idaho (DOE-ID) approval of the final hazard categorization determined by this hazard assessment document (HAD) was required per the

Characterization and adjustment of the neutron radiography facility of the RP-10 nuclear reactor

International Nuclear Information System (INIS)

Ravello R, Y.R.

2001-01-01

The main aim of this work was to characterize and adjust the neutron radiography facility of the RP-10 nuclear reactor, and therefore be able to offer with this technique services to the industry and research centers in general. This technique will be complemented with others such as x-rays and gamma radiography. First, the shielding capacity of the facility was analyzed, proving that it complies with the radiological safety requirements established by the radiological safety code. Then gamma filtration tests were conducted in order to implement the direct method for image formation, optical density curves were built according to the thickness of the gamma filter, the type of film and the type of irradiation. Also, the indirect method for image formation was implemented for two types of converters: indium and dysprosium. Growth curves for optical density were also made according to contact time between converter-film, for different types of films. The resolution of the facility was also analyzed using two methods: Klasens (1946) and Harms (1986). Harms method came closer to the resolution of the human eye when compared to the Klasens method. Finally, the application fields of neutron radiography are presented, including those conducted at the neutron radiography facility of the RP-10 nuclear reactor. With this work, the RP-10 neutron radiography facility is ready to offer inspection and research services

Determinants of facility delivery after implementation of safer mother programme in Nepal: a prospective cohort study.

Science.gov (United States)

Karkee, Rajendra; Binns, Colin W; Lee, Andy H

2013-10-20

There are several barriers for pregnant women to deliver in a health care facility. This prospective cohort study investigated factors affecting facility delivery and reasons for unplanned place of delivery after implementation of the safer mother programme in Nepal. Baseline interviews using a validated questionnaire were conducted on a sample of 700 pregnant women representative of the Kaski district in central Nepal. Follow-up interviews of the cohort were then conducted within 45 days postpartum. Stepwise logistic regression analysis was performed to determine factors associated with the facility delivery outcome. Of the 644 pregnant women whose delivery location had been identified, 547 (85%) gave birth in a health care facility. Women were more likely to deliver in a health facility if they were educated especially with higher secondary or above qualification (adjusted odds ratio (OR) 12.39, 95% confidence interval (CI) 5.09 to 30.17), attended 4 or more antenatal care visits (OR 2.15, 95% CI 1.25 to 3.69), and lived within 30 minutes to the facility (OR 11.61, 95% CI 5.77 to 24.04). For the 97 women who delivered at home, 72 (74.2%) were unplanned, mainly due to quick precipitation of labour making it impossible to reach a health facility. It appeared that facility delivery occurs more frequent among educated women and those who live nearby, even though maternity services are now freely available in Nepal. Because of the difficult terrain and transportation problem in rural areas, interventions that make maternity service physically accessible during antenatal period are needed to increase the utilisation of health facility for child birth.

Siting simulation for low-level waste disposal facilities

International Nuclear Information System (INIS)

Roop, R.D.; Rope, R.C.

1985-01-01

The Mock Site Licensing Demonstration Project has developed the Low-Level Radioactive Waste Siting Simulation, a role-playing exercise designed to facilitate the process of siting and licensing disposal facilities for low-level waste (LLW). This paper describes the development, content, and usefulness of the siting simulation. The simulation can be conducted at a workshop or conference, involves 14 or more participants, and requires about eight hours to complete. The simulation consists of two sessions; in the first, participants negotiate the selection of siting criteria, and in the second, a preferred disposal site is chosen from three candidate sites. The project has sponsored two workshops (in Boston, Massachusetts and Richmond, Virginia) in which the simulation has been conducted for persons concerned with LLW management issues. It is concluded that the simulation can be valuable as a tool for disseminating information about LLW management; a vehicle that can foster communication; and a step toward consensus building and conflict resolution. The DOE National Low-Level Waste Management Program is now making the siting simulation available for use by states, regional compacts, and other organizations involved in development of LLW disposal facilities

The choice of park and ride facilities: an analysis using a context-dependent hierarchical choice experiment

OpenAIRE

Ilona D M Bos; Rob E C M Van der Heijden; Eric J E Molin; Harry J P Timmermans

2004-01-01

Park and ride (P & R) facilities have been proposed in several countries to alleviate the accessibility problems in cities. Despite growing accessibility problems, these facilities do not seem to attract the expected number of car drivers and are underused. In an attempt to measure consumer evaluations of the attributes of P & R facilities, a stated choice experiment, based on the method of hierarchical information integration, was conducted in the city of Nijmegen, The Netherlands. This pape...

Hanford Facility dangerous waste permit application, liquid effluent retention facility and 200 area effluent treatment facility

International Nuclear Information System (INIS)

Coenenberg, J.G.

1997-01-01

The Hanford Facility Dangerous Waste Permit Application is considered to 10 be a single application organized into a General Information Portion (document 11 number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the 12 Unit-Specific Portion is limited to Part B permit application documentation 13 submitted for individual, 'operating' treatment, storage, and/or disposal 14 units, such as the Liquid Effluent Retention Facility and 200 Area Effluent 15 Treatment Facility (this document, DOE/RL-97-03). 16 17 Both the General Information and Unit-Specific portions of the Hanford 18 Facility Dangerous Waste Permit Application address the content of the Part B 19 permit application guidance prepared by the Washington State Department of 20 Ecology (Ecology 1987 and 1996) and the U.S. Environmental Protection Agency 21 (40 Code of Federal Regulations 270), with additional information needs 22 defined by the Hazardous and Solid Waste Amendments and revisions of 23 Washington Administrative Code 173-303. For ease of reference, the Washington 24 State Department of Ecology alpha-numeric section identifiers from the permit 25 application guidance documentation (Ecology 1996) follow, in brackets, the 26 chapter headings and subheadings. A checklist indicating where information is 27 contained in the Liquid Effluent Retention Facility and 200 Area Effluent 28 Treatment Facility permit application documentation, in relation to the 29 Washington State Department of Ecology guidance, is located in the Contents 30 Section. 31 32 Documentation contained in the General Information Portion is broader in 33 nature and could be used by multiple treatment, storage, and/or disposal units 34 (e.g., the glossary provided in the General Information Portion). Wherever 35 appropriate, the Liquid Effluent Retention Facility and 200 Area Effluent 36 Treatment Facility permit application documentation makes cross-reference to 37 the General Information Portion, rather than duplicating

Hanford Facility dangerous waste permit application, liquid effluent retention facility and 200 area effluent treatment facility

Energy Technology Data Exchange (ETDEWEB)

Coenenberg, J.G.

1997-08-15

The Hanford Facility Dangerous Waste Permit Application is considered to 10 be a single application organized into a General Information Portion (document 11 number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the 12 Unit-Specific Portion is limited to Part B permit application documentation 13 submitted for individual, `operating` treatment, storage, and/or disposal 14 units, such as the Liquid Effluent Retention Facility and 200 Area Effluent 15 Treatment Facility (this document, DOE/RL-97-03). 16 17 Both the General Information and Unit-Specific portions of the Hanford 18 Facility Dangerous Waste Permit Application address the content of the Part B 19 permit application guidance prepared by the Washington State Department of 20 Ecology (Ecology 1987 and 1996) and the U.S. Environmental Protection Agency 21 (40 Code of Federal Regulations 270), with additional information needs 22 defined by the Hazardous and Solid Waste Amendments and revisions of 23 Washington Administrative Code 173-303. For ease of reference, the Washington 24 State Department of Ecology alpha-numeric section identifiers from the permit 25 application guidance documentation (Ecology 1996) follow, in brackets, the 26 chapter headings and subheadings. A checklist indicating where information is 27 contained in the Liquid Effluent Retention Facility and 200 Area Effluent 28 Treatment Facility permit application documentation, in relation to the 29 Washington State Department of Ecology guidance, is located in the Contents 30 Section. 31 32 Documentation contained in the General Information Portion is broader in 33 nature and could be used by multiple treatment, storage, and/or disposal units 34 (e.g., the glossary provided in the General Information Portion). Wherever 35 appropriate, the Liquid Effluent Retention Facility and 200 Area Effluent 36 Treatment Facility permit application documentation makes cross-reference to 37 the General Information Portion, rather than duplicating

Neutron spectral characterization of the PCA-PV benchmark facility

International Nuclear Information System (INIS)

Stallmann, F.W.; Kam, F.B.K.; Fabry, A.

1980-01-01

The Pool Critical Assembly (PCA) at the Oak Ridge National Laboratory is being used to generate the PCA-PV benchmark neutron field. A configuration consisting of steel blocks and water gaps is used to simulate the thermal shield pressure vessel configurations in power reactors. The distances between the steel blocks can be changed so that the penetration of neutrons through water and steel can be determined and compared for many different configurations. Easy access and low flux levels make it possible to conduct extensive measurements using active and passive neutron dosimetry, which are impossible to perform in commercial reactors. The clean core and simple geometry facilitates neutron transport calculations which can be validated in detail by comparison with measurements. A facility which has the same configuration of water and steel as the PCA-PV facility but contains test specimens for materials testing, will be irradiated in the higher fluxes at the Oak Ridge Research Reactor. Using the results from the PCA-PV facility, the correlation between neutron flux-fluences and radiation damage in steel can be established. This facility is being discussed in a separate paper

The on-line low temperature nuclear orientation facility NICOLE

International Nuclear Information System (INIS)

Ohtsubo, T; Roccia, S; Gaulard, C; Stone, N J; Stone, J R; Köster, U; Nikolov, J; Veskovic, M; Simpson, G S

2017-01-01

We review major experiments and results obtained by the on-line low temperature nuclear orientation method at the NICOLE facility at ISOLDE, CERN since the year 2000 and highlight their general physical impact. This versatile facility, providing a large degree of controlled nuclear polarization, was used for a long-standing study of magnetic moments at shell closures in the region Z  = 28, N  = 28–50 but also for dedicated studies in the deformed region around A  ∼ 180. Another physics program was conducted to test symmetry in the weak sector and constrain weak coupling beyond V–A . Those two programs were supported by careful measurements of the involved solid state physics parameters to attain the full sensitivity of the technique and provide interesting interdisciplinary results. Future plans for this facility include the challenging idea of measuring the beta–gamma–neutron angular distributions from polarized beta delayed neutron emitters, further test of fundamental symmetries and obtaining nuclear structure data used in medical applications. The facility will also continue to contribute to both the nuclear structure and fundamental symmetry test programs. (paper)

Circulation Modeling for Proposed Port Facility at Ponce and Guayanilla, Puerto Rico

National Research Council Canada - National Science Library

Scheffner, Norman

2002-01-01

... of Ponce and Guayanilla, Puerto Rico. Impacts of the proposed construction were determined by conducting numerical simulations of tidal and storm surge circulation at the project sites using with and without the proposed port facilities...

Facility effluent monitoring plan for 242-A evaporator facility

International Nuclear Information System (INIS)

Crummel, G.M.; Gustavson, R.D.

1995-02-01

A facility effluent monitoring plan is required by the U.S. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could affect employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation showed the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-1. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated, as a minimum, every three years

EPA Facility Registry Service (FRS): Facility Interests Dataset

Data.gov (United States)

U.S. Environmental Protection Agency — This web feature service consists of location and facility identification information from EPA's Facility Registry Service (FRS) for all sites that are available in...

Design, construction and monitoring of temporary storage facilities for removed contaminants

International Nuclear Information System (INIS)

Saegusa, Hiromitsu; Funaki, Hironori; Kurikami, Hiroshi; Sakamoto, Yoshiaki; Tokizawa, Takayuki

2013-01-01

Since the Fukushima Daiichi nuclear power plant accident caused by the Tohoku Region Pacific Coast Earthquake on March 11, 2011, decontamination work has been conducted in the surrounding environment within the Fukushima prefecture. Removed contaminants including soil, grass and trees are to be stored safely at temporary storage facilities for up to three years, after which they will be transferred to a planned interim storage facility. The decontamination pilot project was carried out in both the restricted and planned evacuation areas in order to assess decontamination methods and demonstrate measures for radiation protection of workers. Fourteen temporary storage facilities of different technical specifications were designed and constructed under various topographic conditions and land use. In order to support the design, construction and monitoring of temporary storage facilities for removed contaminants during the full-scale decontamination within the prefecture of Fukushima, technical know-how obtained during the decontamination pilot project has been identified and summarized in this paper. (author)

Branch technical position for performance assessment of low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Campbell, A.C.; Abramson, L.; Byrne, R.M.

1994-01-01

The U.S. Nuclear Regulatory Commission has developed a Draft Branch Technical Position on Performance Assessment of Low-Level Radioactive Waste Disposal Facilities. The draft technical position addresses important issues in performance assessment modeling and provides a framework and technical basis for conducting and evaluating performance assessments in a disposal facility license application. The technical position also addresses specific technical policy issues and augments existing NRC guidance pertaining to LLW performance assessment

A study on items necessary to develop the requirements for the management of serious accidents postulated in fuel fabrication, enrichment and reprocessing facilities

International Nuclear Information System (INIS)

Takanashi, Mitsuhiro; Yamate, Kazuki; Asada, Kazuo; Yamada, Takashi; Endo, Shigeki

2013-05-01

The purpose of this study is to supply the points to discuss on new rules of fuel fabrication, enrichment and reprocessing facilities (hereinafter referred to as 'fuel cycle facilities') conducted by Nuclear Regulation Authority. Requirements for management of serious accidents in the fuel cycle facilities were summarized in this study. Taking into account the lessons learned from the accident of TEPCO Fukushima Daiichi Nuclear Power Plant in Mar. 2011, Act for the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors was amended in June 2012. The main items of the amendment were as follows: Preparation for the management of serious accidents, Introduction of evaluation system for safety improvement, Application of new standards to existing nuclear facilities (back-fitting). Japan Nuclear Energy Safety organization (JNES) conducted a fundamental study on serious accidents and their management in the fuel cycle facilities and made a report. In the report, the concept of Defense in Depth and the definition of serious accidents for the fuel cycle facilities were discussed. Those discussions were conducted by reference to new regulation rules (draft) for power reactors and from the view of features of the fuel cycle facilities. However, further detailed studies are necessary in order to clarify some issues in it. It was also reflected opinions from experts in JNES technical meetings on accident management of the fuel cycle facilities to brush up this report. (author)

The Study on Domestic and Foreign Cases for Decommissioning of DPRK Nuclear Facilities

International Nuclear Information System (INIS)

Baek, Ye Ji; Hhu, Joo Youn; Lee, Jung Hyun; Hwang, Yong Soo

2016-01-01

This study was able to analyze domestic and foreign cases, and collect data on the approximate amount of waste and time required time; however, data on applied technology, input manpower, required cost, and waste disposal method was insufficient. DPRK activities such as nuclear weapon development or nuclear testing not only threaten our country's security but also have an adverse effect on nuclear nonproliferation and security in the international society. Therefore, denuclearization of the DPRK is prior task that is essential to peace on the Korean Peninsula. The fundamental purpose of denuclearization of the DPRK is to safely decommission facilities related to developing nuclear weapons and to depose related radioactive waste and nuclear materials. Understanding descriptive references and physical properties of the facility and its purpose important for decommissioning nuclear facilities. Although it was impossible to collect data on DPRK nuclear facilities to perform complete decommissioning, we were able to understand the process used at DPRK nuclear facilities with open source data. This study has been conducted to establish overall measures for decommissioning DPRK nuclear facilities. DPRK nuclear facilities in this study include a IRT- 2000 type nuclear research reactor, a 5 MWe graphite moderated reactor, nuclear fuel fabrication facility, and a nuclear fuel reprocessing facility, which are considered as facilities that produce or manufacture nuclear materials needed for nuclear weapons or related to such activities.

The Study on Domestic and Foreign Cases for Decommissioning of DPRK Nuclear Facilities

Energy Technology Data Exchange (ETDEWEB)

Baek, Ye Ji; Hhu, Joo Youn; Lee, Jung Hyun; Hwang, Yong Soo [Korea Institute of Nuclear Non-proliferation and Control, Daejeon (Korea, Republic of)

2016-05-15

This study was able to analyze domestic and foreign cases, and collect data on the approximate amount of waste and time required time; however, data on applied technology, input manpower, required cost, and waste disposal method was insufficient. DPRK activities such as nuclear weapon development or nuclear testing not only threaten our country's security but also have an adverse effect on nuclear nonproliferation and security in the international society. Therefore, denuclearization of the DPRK is prior task that is essential to peace on the Korean Peninsula. The fundamental purpose of denuclearization of the DPRK is to safely decommission facilities related to developing nuclear weapons and to depose related radioactive waste and nuclear materials. Understanding descriptive references and physical properties of the facility and its purpose important for decommissioning nuclear facilities. Although it was impossible to collect data on DPRK nuclear facilities to perform complete decommissioning, we were able to understand the process used at DPRK nuclear facilities with open source data. This study has been conducted to establish overall measures for decommissioning DPRK nuclear facilities. DPRK nuclear facilities in this study include a IRT- 2000 type nuclear research reactor, a 5 MWe graphite moderated reactor, nuclear fuel fabrication facility, and a nuclear fuel reprocessing facility, which are considered as facilities that produce or manufacture nuclear materials needed for nuclear weapons or related to such activities.

Mixed and Low-Level Waste Treatment Facility project

International Nuclear Information System (INIS)

1992-04-01

Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. This report, Appendix A, Environmental ampersand Regulatory Planning ampersand Documentation, identifies the regulatory requirements that would be imposed on the operation or construction of a facility designed to process the INEL's waste streams. These requirements are contained in five reports that discuss the following topics: (1) an environmental compliance plan and schedule, (2) National Environmental Policy Act requirements, (3) preliminary siting requirements, (4) regulatory justification for the project, and (5) health and safety criteria

RCRA Facilities Assessment (RFA)---Oak Ridge National Laboratory

International Nuclear Information System (INIS)

1987-03-01

US Department of Energy (DOE) facilities are required to be in full compliance with all federal and state regulations. In response to this requirement, the Oak Ridge National Laboratory (ORNL) has established a Remedial Action Program (RAP) to provide comprehensive management of areas where past and current research, development, and waste management activities have resulted in residual contamination of facilities or the environment. This report presents the RCRA Facility Assessment (RFA) required to meet the requirements of RCRA Section 3004(u). Included in the RFA are (1) a listing of all sites identified at ORNL that could be considered sources of releases or potential releases; (2) background information on each of these sites, including location, type, size, period of operation, current operational status, and information on observed or potential releases (as required in Section II.A.1 of the RCRA permit); (3) analytical results obtained from preliminary surveys conducted to verify the presence or absence of releases from some of the sites; and (4) ORNL's assessment of the need for further remedial attention

Initial emission assessment of hazardous-waste-incineration facilities

International Nuclear Information System (INIS)

Harrington, E.S.; Holton, G.A.; O'Donnell, F.R.

1982-01-01

Health and Safety Research Division, sponsored by EPA, conducted a study to quantify emission factors from stacks, spills, fugitives, storage, and treatment for a typical hazardous waste incinerator facility. Engineering participated in preparing flowsheets and providing calculations for fugitive emissions. Typical block-flow diagrams were developed two types of hazardous waste incinerators (rotary kiln and liquid-injector) and for three capacities (small: 1 MM Btu/hr, median: 10 MM Btu/hr, and large: 150 MM Btu/hr). Storage reqirements and support services were determined in more detail. Using the properties of a typical waste, fugitive emissions were determined, including emissions from pump leaks, valve leaks, flange leaks, and tank vents. An atmospheric dispersion model was then employed to calculate atmospheric concentration and population exposure estimates. With these estimates, an assessment was performed to determine the percentage of concentrations and exposure associated with selected emissions from each source at the incineration facility. Results indicated the relative importance of each source at the incineration facility. Results indicated the relative importance of each source both in terms of public health and pollution control requirements

RCRA Facilities Assessment (RFA)---Oak Ridge National Laboratory

Energy Technology Data Exchange (ETDEWEB)

1987-03-01

US Department of Energy (DOE) facilities are required to be in full compliance with all federal and state regulations. In response to this requirement, the Oak Ridge National Laboratory (ORNL) has established a Remedial Action Program (RAP) to provide comprehensive management of areas where past and current research, development, and waste management activities have resulted in residual contamination of facilities or the environment. This report presents the RCRA Facility Assessment (RFA) required to meet the requirements of RCRA Section 3004(u). Included in the RFA are (1) a listing of all sites identified at ORNL that could be considered sources of releases or potential releases; (2) background information on each of these sites, including location, type, size, period of operation, current operational status, and information on observed or potential releases (as required in Section II.A.1 of the RCRA permit); (3) analytical results obtained from preliminary surveys conducted to verify the presence or absence of releases from some of the sites; and (4) ORNL`s assessment of the need for further remedial attention.

RCRA Facilities Assessment (RFA)---Oak Ridge National Laboratory

Energy Technology Data Exchange (ETDEWEB)

1987-03-01

US Department of Energy (DOE) facilities are required to be in full compliance with all federal and state regulations. In response to this requirement, the Oak Ridge National Laboratory (ORNL) has established a Remedial Action Program (RAP) to provide comprehensive management of areas where past and current research, development, and waste management activities have resulted in residual contamination of facilities or the environment. This report presents the RCRA Facility Assessment (RFA) required to meet the requirements of RCRA Section 3004(u). Included in the RFA are (1) a listing of all sites identified at ORNL that could be considered sources of releases or potential releases; (2) background information on each of these sites, including location, type, size, period of operation, current operational status, and information on observed or potential releases (as required in Section II.A.1 of the RCRA permit); (3) analytical results obtained from preliminary surveys conducted to verify the presence or absence of releases from some of the sites; and (4) ORNL's assessment of the need for further remedial attention.

Experimental Results Obtained with Air Liquide Cold Compression System: CERN LHC and SNS Projects

Science.gov (United States)

Delcayre, F.; Courty, J.-C.; Hamber, F.; Hilbert, B.; Monneret, E.; Toia, J.-L.

2006-04-01

Large scale collider facilities will make intensive use of superconducting magnets, operating below 2.0 K. This dictates high-capacity refrigeration systems operating below 2.0 K. These systems, making use of cryogenic centrifugal compressors in a series arrangement with room temperature screw compressors will be coupled to a refrigerator, providing a certain power at 4.5 K. A first Air Liquide Cold Compression System (CCS) unit was built and delivered to CERN in 2001. Installed at the beginning of 2002, it was commissioned and tested successfully during year 2002. A series of four sets of identical CCS were then tested in 2004. Another set of four cryogenic centrifugal compressors (CCC) has been delivered to Thomas Jefferson National Accelerator Facility (JLAB) for the Spallation Neutron Source (SNS) in 2002. These compressors were tested and commissioned from December 2004 to July 2005. The experimental results obtained with these systems will be presented and discussed: the characteristics of the CCC will be detailed. The principles of control for the CCC in series will be detailed.

A rock characterisation facility consultative document

International Nuclear Information System (INIS)

1992-10-01

This U.K. Nirex Ltd., consultative document describes a proposed underground rock characterisation facility, east of Sellafield, for conducting geophysical surveys as a basis for refining long-term safety analysis of an underground repository for intermediate-level and low-level radioactive wastes. Planning application will be submitted in 1993. The construction of shafts and galleries is described and the site's geologic, topographical, climatic and archaeological features discussed. The effects to the local environment and on local populations and other socio-economic factors are discussed. (UK)

Quantification of greenhouse gas emissions from a biological waste treatment facility

DEFF Research Database (Denmark)

Jensen, Morten Bang; Møller, Jacob; Mønster, Jacob

2017-01-01

measurements downwind of the facility. Emission measurements were conducted over a period of three days, and in total, 80 plume traverses were obtained. On-site screening showed that important processes resulting in methane emissions were aerobic composting reactors, anaerobic digester reactors, composting...

A facile avenue to conductive polymer brushes via cyclopentadiene-maleimide Diels-Alder ligation

Czech Academy of Sciences Publication Activity Database

Yameen, B.; Rodriguez-Emmenegger, C.; Preuss, C. M.; Pop-Georgievski, Ognen; Verveniotis, Elisseos; Trouillet, V.; Rezek, Bohuslav; Barner-Kowollik, C.

2013-01-01

Roč. 49, č. 77 (2013), s. 8623-8625 ISSN 1359-7345 R&D Projects: GA ČR GBP205/12/G118; GA ČR GAP108/11/1857; GA ČR(CZ) GBP108/12/G108 Institutional support: RVO:61389013 ; RVO:68378271 Keywords : conductive poly(3-hexylthiophen) brushes * Diels-Alder ligation * Kelvin Probe Force Microscopy (KFM) Subject RIV: CD - Macromolecular Chemistry Impact factor: 6.718, year: 2013

Status and Prospect of Safeguards By Design for the Pyroprocessing Facility

International Nuclear Information System (INIS)

Kim, Hodong; Shin, H.S.; Ahn, S.K.

2010-01-01

The concept of Safeguards-By-Design (SBD), which is proposed and developed by the United States and the IAEA, is now widely acknowledged as a fundamental consideration for the effective and efficient implementation of safeguards. The application of a SBD concept is of importance especially for developmental nuclear facilities which have new technological features and relevant challenges to their safeguards approach. At this point of time, the examination of the applicability of SBD on a pyroprocessing facility, which has been being developed in the Republic of Korea (ROK), would be meaningful. The ROK developed a safeguards system with the concept of SBD for Advanced spent fuel Conditioning Process Facility (ACPF) and DUPIC Fuel Development Facility (DFDF) before the SBD concept was formally suggested. Currently. The PRIDE (PyRoprocess Integrated Inactive Demonstration) facility for the demonstration of pyroprocess using 10 ton of non-radioactive nuclear materials per year is being constructed in the ROK. The safeguards system for the facility has been designed in cooperation with a facility designer from the design phase, and the safeguards system would be established according to the future construction schedule. In preparing the design of Engineering Scale Pyroprocess Facility (ESPF), which will use spent fuels in an engineering scale and be constructed in 2016, a research on the safeguards system for this facility is also being conducted. In this connection, a project to support for development of safeguards approach for a reference pyroprocessing facility has been carried out by KAERI in cooperation with KINAC and the IAEA through an IAEA Member State Support Program (MSSP). When this MSSP project is finished in August, 2011, a safeguards system model and safeguards approach for a reference pyroprocessing facility would be established. Maximizing these early experiences and results, a safeguards system of ESPF based on the concept of SBD would be designed and