WorldWideScience

Sample records for test results final

  1. Results of Final Focus Test Beam

    Energy Technology Data Exchange (ETDEWEB)

    Walz, Dieter R

    2003-06-13

    The beam experiments of Final Focus Test Beam (FFTB) started in September 1993 at SLAC, and have produced a 1.7 {micro}m x 75 nm spot of 46 GeV electron beam. A number of new techniques involving two nanometer spot-size monitors have been developed. Several beam diagnostic/tuning schemes are applied to achieve and maintain the small spot. This experiment opens the way toward the nanometer world for future linear colliders.

  2. Final report on special impact tests of plutonium shipping containers description of test results

    International Nuclear Information System (INIS)

    Bonzon, L.L.

    1977-02-01

    The results from tests conducted to determine the structural response of the LLD-1, Model 1518-6M, and FL-10 plutonium shipping packages when subjected to high-speed impacts (170 to 760 ft/sec) onto unyielding, concrete, and soil targets are presented

  3. Final test results for the ground operations demonstration unit for liquid hydrogen

    Science.gov (United States)

    Notardonato, W. U.; Swanger, A. M.; Fesmire, J. E.; Jumper, K. M.; Johnson, W. L.; Tomsik, T. M.

    2017-12-01

    Described herein is a comprehensive project-a large-scale test of an integrated refrigeration and storage system called the Ground Operations and Demonstration Unit for Liquid Hydrogen (GODU LH2), sponsored by the Advanced Exploration Systems Program and constructed at Kennedy Space Center. A commercial cryogenic refrigerator interfaced with a 125,000 l liquid hydrogen tank and auxiliary systems in a manner that enabled control of the propellant state by extracting heat via a closed loop Brayton cycle refrigerator coupled to a novel internal heat exchanger. Three primary objectives were demonstrating zero-loss storage and transfer, gaseous liquefaction, and propellant densification. Testing was performed at three different liquid hydrogen fill-levels. Data were collected on tank pressure, internal tank temperature profiles, mass flow in and out of the system, and refrigeration system performance. All test objectives were successfully achieved during approximately two years of testing. A summary of the final results is presented in this paper.

  4. Final report of the Buffer Mass Test. Volume II: test results

    International Nuclear Information System (INIS)

    Pusch, R.; Boerjesson, L.; Ramqvist, G.

    1985-08-01

    The evaluation of the Buffer Mass Test mainly concerned the heating of the bentonite/rock system that simulated hot canisters in deposition holes, the swelling and swelling pressure of the expanding bentonite in the heater holes, and the water uptake of the bentonite in the holes as well as in the tunnel backfill. These processes had been predicted on the basis of laboratory-derived data and FEM calculations with due consideration of the actual geometry. The recorded temperatures of the bentonite and surrounding rock were found to be below the maximum temperature that had been set, but higher than the expected values in the initial period of testing. The heater surface temperatures dropped in the course of the tests due to the uptake of water from the rock even in the driest hole which was located in almost fracture-free rock. The water uptake in the highly compacted bentonite in the heater holes was manifested by a successively increased swelling pressure at the bentonite/rock interface. It was rather uniformly distributed over this interface and reached a maximum value of about 10 MPa. The water content determination confirmed that water had been absorbed by the bentonite from the rock even in the driest holes where the counteracting thermal gradient was rather high. In the wettest holes the saturation became almost complete and a high degree of saturation was also observed in the tunnel backfill. Both in the heater holes and the tunnel, the moistening was found to be very uniform along the periphery, which is at least partly explained by the self-sealing ability of bentonite buffer materials. A general conclusion is that the involved physical processes are well understood and that the ultimate physical state of the buffer materials under repository conditions can be safely predicted. With 15 refs. (Author)

  5. The deformable secondary mirror of VLT: final electro-mechanical and optical acceptance test results

    Science.gov (United States)

    Briguglio, Runa; Biasi, Roberto; Xompero, Marco; Riccardi, Armando; Andrighettoni, Mario; Pescoller, Dietrich; Angerer, Gerald; Gallieni, Daniele; Vernet, Elise; Kolb, Johann; Arsenault, Robin; Madec, Pierre-Yves

    2014-07-01

    The Deformable Secondary Mirror (DSM) for the VLT ended the stand-alone electro-mechanical and optical acceptance process, entering the test phase as part of the Adaptive Optics Facility (AOF) at the ESO Headquarter (Garching). The VLT-DSM currently represents the most advanced already-built large-format deformable mirror with its 1170 voice-coil actuators and its internal metrology based on co-located capacitive sensors to control the shape of the 1.12m-diameter 2mm-thick convex shell. The present paper reports the final results of the electro-mechanical and optical characterization of the DSM executed in a collaborative effort by the DSM manufacturing companies (Microgate s.r.l. and A.D.S. International s.r.l.), INAF-Osservatorio Astrofisico di Arcetri and ESO. The electro-mechanical acceptance tests have been performed in the company premises and their main purpose was the dynamical characterization of the internal control loop response and the calibration of the system data that are needed for its optimization. The optical acceptance tests have been performed at ESO (Garching) using the ASSIST optical test facility. The main purpose of the tests are the characterization of the optical shell flattening residuals, the corresponding calibration of flattening commands, the optical calibration of the capacitive sensors and the optical calibration of the mirror influence functions.

  6. Transacsys PLC - Final Results

    CERN Multimedia

    2002-01-01

    Final results from Transacsys PLC. A subsidary of this company was set up to develop the CERN EDH system into a commercial product but incurred too much financial loss so the project was cancelled (1/2 page).

  7. Driving simulator test results Deliverable no D6.3. Final draft

    NARCIS (Netherlands)

    Weiland, J.; Mattes, S.; Kuhn, F.; Gelau, Ch.; Schindhelm, R.; Hoedemaeker, D.D.M.

    2003-01-01

    Deliverable 6.3 reports the procedure and results from a driving simulator study. This study was carried out to test the efficiency of the principles of the in-vehicle information manager, which was developed within the Comunicar project. Thirty-six subjects were tested in a fixed-base driving

  8. ECLSS Sustaining Metal Materials Compatibility Final Report, Electrochemical and Crevice Corrosion Test Results

    Science.gov (United States)

    Lee, R. E.

    2015-01-01

    Electrochemical test results are presented for six noble metals evaluated in two acidic test solutions which are representative of waste liquids processed in the Environmental Control and Life Support System (ECLSS) aboard the International Space Station (ISS). The two test solutions consisted of fresh waste liquid which had been modified with a proposed or alternate pretreatment formulation and its associated brine concentrate. The six test metals included three titanium grades, (Commercially Pure, 6Al-4V alloy and 6Al-4V Low Interstitial alloy), two nickel-chromium alloys (Inconel® 625 and Hastelloy® C276), and one high tier stainless steel (Cronidur® 30).

  9. Gravity Probe B: final results of a space experiment to test general relativity.

    Science.gov (United States)

    Everitt, C W F; DeBra, D B; Parkinson, B W; Turneaure, J P; Conklin, J W; Heifetz, M I; Keiser, G M; Silbergleit, A S; Holmes, T; Kolodziejczak, J; Al-Meshari, M; Mester, J C; Muhlfelder, B; Solomonik, V G; Stahl, K; Worden, P W; Bencze, W; Buchman, S; Clarke, B; Al-Jadaan, A; Al-Jibreen, H; Li, J; Lipa, J A; Lockhart, J M; Al-Suwaidan, B; Taber, M; Wang, S

    2011-06-03

    Gravity Probe B, launched 20 April 2004, is a space experiment testing two fundamental predictions of Einstein's theory of general relativity (GR), the geodetic and frame-dragging effects, by means of cryogenic gyroscopes in Earth orbit. Data collection started 28 August 2004 and ended 14 August 2005. Analysis of the data from all four gyroscopes results in a geodetic drift rate of -6601.8±18.3  mas/yr and a frame-dragging drift rate of -37.2±7.2  mas/yr, to be compared with the GR predictions of -6606.1  mas/yr and -39.2  mas/yr, respectively ("mas" is milliarcsecond; 1  mas=4.848×10(-9)  rad).

  10. Advanced fighter technology integration (AFTI)/F-16 Automated Maneuvering Attack System final flight test results

    Science.gov (United States)

    Dowden, Donald J.; Bessette, Denis E.

    1987-01-01

    The AFTI F-16 Automated Maneuvering Attack System has undergone developmental and demonstration flight testing over a total of 347.3 flying hours in 237 sorties. The emphasis of this phase of the flight test program was on the development of automated guidance and control systems for air-to-air and air-to-ground weapons delivery, using a digital flight control system, dual avionics multiplex buses, an advanced FLIR sensor with laser ranger, integrated flight/fire-control software, advanced cockpit display and controls, and modified core Multinational Stage Improvement Program avionics.

  11. Final focus test beam

    International Nuclear Information System (INIS)

    1991-03-01

    This report discusses the following: the Final Focus Test Beam Project; optical design; magnets; instrumentation; magnetic measurement and BPM calibration; mechanical alignment and stabilization; vacuum system; power supplies; control system; radiation shielding and personnel protection; infrastructure; and administration

  12. The AP600 advanced simplified nuclear power plant. Results of the test program and progress made toward final design approval

    International Nuclear Information System (INIS)

    Bruschi, H.J.

    1996-01-01

    At the 1994 Pacific Basin Conference, Mr. Bruschi presented a paper describing the AP600, Westinghouse's advanced light water reactor design with passive safety features. Since then, a rigorous test program was completed and AP600 became the most thoroughly tested advanced reactor system design in history. Westinghouse is now well on its way toward receiving Final Design Approval from the U.S. Nuclear Regulatory Commission for AP600. In this paper, the results of the test program will be discussed and an update on prospects for building the plant will be covered. (author)

  13. The AP600 advanced simplified nuclear power plant. Results of the test program and progress made toward final design approval

    Energy Technology Data Exchange (ETDEWEB)

    Bruschi, H.J. [Westinghouse Electric Corp., Pittsburgh, PA (United States)

    1996-10-01

    At the 1994 Pacific Basin Conference, Mr. Bruschi presented a paper describing the AP600, Westinghouse`s advanced light water reactor design with passive safety features. Since then, a rigorous test program was completed and AP600 became the most thoroughly tested advanced reactor system design in history. Westinghouse is now well on its way toward receiving Final Design Approval from the U.S. Nuclear Regulatory Commission for AP600. In this paper, the results of the test program will be discussed and an update on prospects for building the plant will be covered. (author)

  14. Present Status And First Results of the Final Focus Beam Line at the KEK Accelerator Test Facility

    International Nuclear Information System (INIS)

    2010-01-01

    ATF2 is a final-focus test beam line which aims to focus the low emittance beam from the ATF damping ring to a vertical size of about 37 nm and to demonstrate nanometer level beam stability. Several advanced beam diagnostics and feedback tools are used. In December 2008, construction and installation were completed and beam commissioning started, supported by an international team of Asian, European, and U.S. scientists. The present status and first results are described.

  15. Present status and first results of the final focus beam line at the KEK Accelerator Test Facility

    CERN Document Server

    Bambade, P; Amann, J; Angal-Kalinin, D; Apsimon, R; Araki, S; Aryshev, A; Bai, S; Bellomo, P; Bett, D; Blair, G; Bolzon, B; Boogert, S; Boorman, G; Burrows, P N; Christian, G; Coe, P; Constance, B; Delahaye, J P; Deacon, L; Elsen, E; Faus-Golfe, A; Fukuda, M; Gao, J; Geffroy, N; Gianfelice-Wendt, E; Guler, H; Hayano, H; Heo, A Y; Honda, Y; Huang, J Y; Hwang, W H; Iwashita, Y; Jeremie, A; Jones, J; Kamiya, Y; Karataev, P; Kim, E S; Kim, H S; Kim, S H; Komamiya, S; Kubo, K; Kume, T; Kuroda, S; Lam, B; Lyapin, A; Masuzawa, M; McCormick, D; Molloy, S; Naito, T; Nakamura, T; Nelson, J; Okamoto, D; Okugi, T; Oroku, M; Park, Y J; Parker, B; Paterson, E; Perry, C; Pivi, M; Raubenheimer, T; Renier, Y; Resta-Lopez, J; Rimbault, C; Ross, M; Sanuki, T; Scarfe, A; Schulte, D; Seryi, A; Spencer, C; Suehara, T; Sugahara, R; Swinson, C; Takahashi, T; Tauchi, T; Terunuma, N; Tomas, R; Urakawa, J; Urner, D; Verderi, M; Wang, M H; Warden, M; Wendt, M; White, G; Wittmer, W; Wolski, A; Woodley, M; Yamaguchi, Y; Yamanaka, T; Yan, Y; Yoda, H; Yokoya, K; Zhou, F; Zimmermann, F; 10.1103/PhysRevSTAB.13.042801

    2010-01-01

    ATF2 is a final-focus test beam line which aims to focus the low emittance beam from the ATF damping ring to a vertical size of about 37 nm and to demonstrate nanometer level beam stability. Several advanced beam diagnostics and feedback tools are used. In December 2008, construction and installation were completed and beam commissioning started, supported by an international team of Asian, European, and U.S. scientists. The present status and first results are described.

  16. Present status and first results of the final focus beam line at the KEK Accelerator Test Facility

    Directory of Open Access Journals (Sweden)

    2010-04-01

    Full Text Available ATF2 is a final-focus test beam line which aims to focus the low emittance beam from the ATF damping ring to a vertical size of about 37 nm and to demonstrate nanometer level beam stability. Several advanced beam diagnostics and feedback tools are used. In December 2008, construction and installation were completed and beam commissioning started, supported by an international team of Asian, European, and U.S. scientists. The present status and first results are described.

  17. Final NOMAD results on $\

    CERN Document Server

    Astier, P.; Baldisseri, A.; Baldo-Ceolin, M.; Banner, M.; Bassompierre, G.; Benslama, K.; Besson, N.; Bird, I.; Blumenfeld, Barry J.; Bobisut, F.; Bouchez, J.; Boyd, S.; Bueno, A.; Bunyatov, S.; Camilleri, L.; Cardini, A.; Cattaneo, P.W.; Cavasinni, V.; Cervera-Villanueva, A.; Chukanov, A.; Collazuol, G.; Conforto, G.; Conta, C.; Contalbrigo, M.; Cousins, R.; Daniels, D.; Degaudenzi, H.; Del Prete, T.; De Santo, A.; Dignan, T.; Di Lella, L.; do Couto e Silva, E.; Dumarchez, J.; Ellis, Malcolm; Feldman, G.J.; Ferrari, R.; Ferrere, D.; Flaminio, V.; Fraternali, M.; Gaillard, J.M.; Gangler, E.; Geiser, A.; Geppert, D.; Gibin, D.; Gninenko, S.; Godley, A.; Gomez-Cadenas, J.J.; Gosset, J.; Gossling, C.; Gouanere, M.; Grant, A.; Graziani, G.; Guglielmi, A.; Hagner, C.; Hernando, J.; Hubbard, D.; Hurst, P.; Hyett, N.; Iacopini, E.; Joseph, C.; Juget, F.; Kirsanov, M.; Klimov, O.; Kokkonen, J.; Kovzelev, A.; Krasnoperov, A.; Kustov, D.; Kuznetsov, V.E.; Lacaprara, S.; Lachaud, C.; Lakic, B.; Lanza, A.; La Rotonda, L.; Laveder, M.; Letessier-Selvon, A.; Levy, J.M.; Linssen, L.; Ljubicic, A.; Long, J.; Lupi, A.; Marchionni, A.; Martelli, F.; Mechain, X.; Mendiburu, J.P.; Meyer, J.P.; Mezzetto, M.; Mishra, S.R.; Moorhead, G.F.; Naumov, D.; Nedelec, P.; Nefedov, Yu.; Nguyen-Mau, C.; Orestano, D.; Pastore, F.; Peak, L.S.; Pennacchio, E.; Pessard, H.; Petti, R.; Placci, A.; Polesello, G.; Pollmann, D.; Polyarush, A.; Popov, B.; Poulsen, C.; Rico, J.; Riemann, P.; Roda, C.; Rubbia, A.; Salvatore, F.; Schahmaneche, K.; Schmidt, B.; Schmidt, T.; Sconza, A.; Sevior, M.; Sillou, D.; Soler, F.J.P.; Sozzi, G.; Steele, D.; Stiegler, U.; Stipcevic, M.; Stolarczyk, T.; Tareb-Reyes, M.; Taylor, G.N.; Tereshchenko, V.; Toropin, A.; Touchard, A.M.; Tovey, S.N.; Tran, M.T.; Tsesmelis, E.; Ulrichs, J.; Vacavant, L.; Valdata-Nappi, M.; Valuev, V.; Vannucci, F.; Varvell, K.E.; Veltri, M.; Vercesi, V.; Vidal-Sitjes, G.; Vieira, J.M.; Vinogradova, T.; Weber, F.V.; Weisse, T.; Wilson, F.F.; Winton, L.J.; Yabsley, Bruce D.; Zaccone, H.; Zuber, K.; Zuccon, P.; Krasnoperov, A V

    2001-01-01

    Results from the nu_tau appearance search in a neutrino beam using the full NOMAD data sample are reported. A new analysis unifies all the hadronic tau decays, significantly improving the overall sensitivity of the experiment to oscillations. The "blind analysis" of all topologies yields no evidence for an oscillation signal. In the two-family oscillation scenario, this sets a 90% C.L. allowed region in the sin^2(2theta)-Delta m^2 plane which includes sin^2(2theta)nu_tau oscillation hypothesis results in sin^2(2theta)<1.5 x 10^{-2} at large Delta m^2 and Delta m^2 < 5.9 eV^2/c^4 at sin^2(2theta)=1. We also derive limits on effective couplings of the tau lepton to nu_mu or nu_e.

  18. Final air test results for the 1/5-scale Mark I boiling water reactor pressure suppression experiment

    International Nuclear Information System (INIS)

    Collins, E.K.; Lai, W.

    1977-01-01

    A loss-of-coolant accident (LOCA) in a boiling-water reactor (BWR) power plant has never occurred. However, because this type of accident is particularly severe, it is used as a principal basis for design. During a hypothetical LOCA in a Mark I BWR, air followed by steam is injected from a drywell into a toroidal wetwell about half-filled with water. A series of consistent, versatile, and accurate air-water tests simulating LOCA conditions was completed in the Lawrence Livermore Laboratory 1/5-Scale Mark I BWR Pressure Suppression Experimental Facility. Results from this test series were used to quantify the vertical loading function and to study the associated fluid dynamic phenomena. Detailed histories of vertical loads on the wetwell are shown. In particular, variations of hydrodynamic-generated vertical loads with changes in drywell pressurization rate, downcomer submergence, and the vent-line loss coefficient are established. Initial drywell overpressure, which partially preclears the downcomers of water, substantially reduces the peak vertical loads. Scaling relationships, developed from dimensional analysis and verified by bench-top experiments, allow the 1/5-scale results to be applied to a full-scale BWR power plant. This analysis leads to dimensionless groupings which are invariant. These groupongs show that if water is used as the working fluid, the magnitude of the forces in a scaled facility is reduced by the cube of the scale factor; the time when these forces occur is reduced by the square root of the scale factor

  19. Experiments on the behaviour of thermite melt injected into sodium: Final report on the THINA test results

    International Nuclear Information System (INIS)

    Huber, F.; Kaiser, A.; Peppler, W.

    1994-01-01

    During hypothetical accidents of fast breeder reactors the core melts and part of the core material inventory is ejected into the upper coolant plenum. As a consequence, a fuel to coolant thermal interaction occurs between the melt and the sodium. A series of simulating experiments was carried out in KfK/IRS to improve the knowledge about the phenomenology of molten fuel/coolant interactions and to support theoretical work on the safety of fast breeder reactors. In the tests, a thermite melt of up to 3270 K is injected from below into a sodium pool the temperature of which is between 770 and 820 K. The masses of the melt and the sodium are about five and 150 kg, respectively. Thermal interactions have been observed to occur as a sequence of small local pressure events mainly during the melt injection. Large-scale vapour explosions have not been observed. Generally, the conversion ratios of thermal to mechanical energy have been low. (author)

  20. Climax granite test results

    Energy Technology Data Exchange (ETDEWEB)

    Ramspott, L.D.

    1980-01-15

    The Lawrence Livermore Laboratory (LLL), as part of the Nevada Nuclear Waste Storage Investigations (NNWSI) program, is carrying out in situ rock mechanics testing in the Climax granitic stock at the Nevada Test Site (NTS). This summary addresses only those field data taken to date that address thermomechanical modeling for a hard-rock repository. The results to be discussed include thermal measurements in a heater test that was conducted from October 1977 through July 1978, and stress and displacement measurements made during and after excavation of the canister storage drift for the Spent Fuel Test (SFT) in the Climax granite. Associated laboratory and field measurements are summarized. The rock temperature for a given applied heat load at a point in time and space can be adequately modeled with simple analytic calculations involving superposition and integration of numerous point source solutions. The input, for locations beyond about a meter from the source, can be a constant thermal conductivity and diffusivity. The value of thermal conductivity required to match the field data is as much as 25% different from laboratory-measured values. Therefore, unless we come to understand the mechanisms for this difference, a simple in situ test will be required to obtain a value for final repository design. Some sensitivity calculations have shown that the temperature field is about ten times more sensitive to conductivity than to diffusivity under the test conditions. The orthogonal array was designed to detect anisotropy. After considering all error sources, anisotropic efforts in the thermal field were less than 5 to 10%.

  1. Spent-Fuel Test - Climax: An evaluation of the technical feasibility of geologic storage of spent nuclear fuel in granite: Executive summary of final results

    International Nuclear Information System (INIS)

    Patrick, W.C.

    1986-01-01

    This summary volume outlines results that are covered in more detail in the final report of the Spent-Fuel Test - Climate project. The project was conducted between 1978 and 1983 in the granitic Climax stock at the Nevada Test Site. Results indicate that spent fuel can be safely stored for periods of years in this host medium and that nuclear waste so emplaced can be safely retrieved. We also evaluated the effects of heat and radiation (alone and in combination) on emplacement canisters and the surrounding rock mass. Storage of the spent-fuel affected the surrounding rock mass in measurable ways, but did not threaten the stability or safety of the facility at any time

  2. Grimsel Test Site: heat test, final report

    International Nuclear Information System (INIS)

    Schneefuss, J.; Glaess, F.; Gommlich, G.; Schmidt, M.

    1989-05-01

    The Swiss concept for the storage of radioactive waste consists in placing it in compact, dense rock formations. An experiment 'Heat Test' carried out by the 'Gesellschaft fuer Strahlen- und Umweltforschung' in Nagra's Grimsel rock laboratory simulated the heat production of stored radioactive waste. The aim was to evaluate processes for the demonstration of the suitability of a final repository for heat-producing radioactive waste in cristalline rock, to investigate the thermic, mechanic and hydraulic reactions to an artificial heat source, and to develop corresponding calculating models. The duration of the tests was about 3 years. In this report the measured thermic, mechanic and hydraulic reactions are documented and discussed in detail. A simple, rotation symmetrical FEM-model was used for the preparatory and experiment-accompanying modelling of the thermomechanical conditions in the heat test. The test showed that suitable measuring methods for the surveillance of the geomechanics of a final repository are available and that the reactions of the crystalline host rock to the heat source remain locally limited and can be modelled with relatively small effort. 29 refs., 33 figs., 10 tabs

  3. Comparison of basic laboratory test results with more sophisticated laboratory and in-situ tests methods on soils in southeastern Wisconsin : final report, March 21, 2009.

    Science.gov (United States)

    2009-03-21

    This study investigates all of the generated soils data in an attempt to use the more 'routine' laboratory tests to determine geotechnical design parameters (such as phiangle, cohesion, wet unit weight, unconfined compression, consolidation character...

  4. SINGLE HEATER TEST FINAL REPORT

    Energy Technology Data Exchange (ETDEWEB)

    J.B. Cho

    1999-05-01

    The Single Heater Test is the first of the in-situ thermal tests conducted by the U.S. Department of Energy as part of its program of characterizing Yucca Mountain in Nevada as the potential site for a proposed deep geologic repository for the disposal of spent nuclear fuel and high-level nuclear waste. The Site Characterization Plan (DOE 1988) contained an extensive plan of in-situ thermal tests aimed at understanding specific aspects of the response of the local rock-mass around the potential repository to the heat from the radioactive decay of the emplaced waste. With the refocusing of the Site Characterization Plan by the ''Civilian Radioactive Waste Management Program Plan'' (DOE 1994), a consolidated thermal testing program emerged by 1995 as documented in the reports ''In-Situ Thermal Testing Program Strategy'' (DOE 1995) and ''Updated In-Situ Thermal Testing Program Strategy'' (CRWMS M&O 1997a). The concept of the Single Heater Test took shape in the summer of 1995 and detailed planning and design of the test started with the beginning fiscal year 1996. The overall objective of the Single Heater Test was to gain an understanding of the coupled thermal, mechanical, hydrological, and chemical processes that are anticipated to occur in the local rock-mass in the potential repository as a result of heat from radioactive decay of the emplaced waste. This included making a priori predictions of the test results using existing models and subsequently refining or modifying the models, on the basis of comparative and interpretive analyses of the measurements and predictions. A second, no less important, objective was to try out, in a full-scale field setting, the various instruments and equipment to be employed in the future on a much larger, more complex, thermal test of longer duration, such as the Drift Scale Test. This ''shake down'' or trial aspect of the Single Heater Test applied

  5. SINGLE HEATER TEST FINAL REPORT

    International Nuclear Information System (INIS)

    J.B. Cho

    1999-01-01

    The Single Heater Test is the first of the in-situ thermal tests conducted by the U.S. Department of Energy as part of its program of characterizing Yucca Mountain in Nevada as the potential site for a proposed deep geologic repository for the disposal of spent nuclear fuel and high-level nuclear waste. The Site Characterization Plan (DOE 1988) contained an extensive plan of in-situ thermal tests aimed at understanding specific aspects of the response of the local rock-mass around the potential repository to the heat from the radioactive decay of the emplaced waste. With the refocusing of the Site Characterization Plan by the ''Civilian Radioactive Waste Management Program Plan'' (DOE 1994), a consolidated thermal testing program emerged by 1995 as documented in the reports ''In-Situ Thermal Testing Program Strategy'' (DOE 1995) and ''Updated In-Situ Thermal Testing Program Strategy'' (CRWMS M and O 1997a). The concept of the Single Heater Test took shape in the summer of 1995 and detailed planning and design of the test started with the beginning fiscal year 1996. The overall objective of the Single Heater Test was to gain an understanding of the coupled thermal, mechanical, hydrological, and chemical processes that are anticipated to occur in the local rock-mass in the potential repository as a result of heat from radioactive decay of the emplaced waste. This included making a priori predictions of the test results using existing models and subsequently refining or modifying the models, on the basis of comparative and interpretive analyses of the measurements and predictions. A second, no less important, objective was to try out, in a full-scale field setting, the various instruments and equipment to be employed in the future on a much larger, more complex, thermal test of longer duration, such as the Drift Scale Test. This ''shake down'' or trial aspect of the Single Heater Test applied not just to the hardware, but also to the teamwork and cooperation between

  6. Testing of GFL Geosiphon; FINAL

    International Nuclear Information System (INIS)

    Steimke, J.L.

    2001-01-01

    A full-scale, transparent replica of a GeoSiphon was constructed in the TFL to test a new concept, using a solar powered vacuum pump to remove accumulated gases from the air chamber. It did not have a treatment cell containing iron filings as do the actual TNX GeoSiphons in the field, but it was accurate in all other respects. The gas generation that is observed in an actual GeoSiphon was simulated by air injection at the inlet of the TFL GeoSiphon. After facility shakedown, three stages of testing were conducted: verification testing, parametric testing and long term testing. In verification testing, the TFL GeoSiphon was used to reproduce a particular test at TNX in which the water flowrate decreased gradually as the result of air accumulation at the crest of a siphon without an air chamber. For this test the vacuum pump was not used and the air chamber was initially filled with air rather than water. Agreement between data from the TNX GeoSiphon and the TFL GeoSiphon was good, which gave confidence that the TFL GeoSiphon was a good hydraulic representation of the TNX GeoSiphon. For the remaining tests, the solar powered vacuum pump and air chamber were used. In parametric testing, steady state runs were made for water flowrates ranging from 1 gpm to 19 gpm, air injection rates ranging from 0 to 77 standard cc/min and outfall line angles ranging from vertical to 60 degrees from vertical. In all cases, the air chamber and vacuum pump removed nearly all of the air and the GeoSiphon operated without problems. In long term testing, the GeoSiphon was allowed to run continuously for 21 days at one set of conditions. During this time the solar cell kept the storage battery fully charged at all times and the control circuit for the vacuum pump operated reliably. The solar panel was observed to have a large excess capacity when used with the vacuum pump. With two changes, the concept of using a solar powered vacuum pump attached to an air chamber should be ready for long

  7. Temperature buffer test. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Aakesson, Mattias [Clay Technology AB, Lund (Sweden)

    2012-04-15

    The Temperature Buffer Test (TBT) is a joint project between SKB/ANDRA and supported by ENRESA (modelling) and DBE (instrumentation), which aims at improving the understanding and to model the thermo-hydro-mechanical behavior of buffers made of swelling clay submitted to high temperatures (over 100 deg C) during the water saturation process. The test has been carried out in a KBS-3 deposition hole at Aspo HRL. It was installed during the spring of 2003. Two steel heaters (3 m long, 0.6 m diameter) and two buffer arrangements have been investigated: the lower heater was surrounded by rings of compacted Wyoming bentonite only, whereas the upper heater was surrounded by a composite barrier, with a sand shield between the heater and the bentonite. The test was dismantled and sampled during the winter of 2009/2010. This report is the final report and a summary of all work performed within the TBT project. The design and the installation of the different components are summarized: the depositions hole, the heating system, the bentonite blocks with emphasis on the initial density and water content in these, the filling of slots with sand or pellets, the retaining construction with the plug, lid and nine anchor cables, the artificial saturation system, and finally the instrumentation. An overview of the operational conditions is presented: the power output from heaters, which was 1,500 W (and also 1,600 W) from each heater during the first {approx}1,700 days, and then changed to 1,000 and 2,000 W, for the upper and lower heater respectively, during the last {approx}600 days. From the start, the bentonite was hydrated with a groundwater from a nearby bore-hole, but this groundwater was replaced with de-ionized water from day {approx}1,500, due to the high flow resistance of the injections points in the filter, which implied that a high filter pressure couldn't be sustained. The sand shield around the upper heater was hydrated from day {approx}1,500 to day {approx}1

  8. Temperature buffer test. Final report

    International Nuclear Information System (INIS)

    Aakesson, Mattias

    2012-04-01

    The Temperature Buffer Test (TBT) is a joint project between SKB/ANDRA and supported by ENRESA (modelling) and DBE (instrumentation), which aims at improving the understanding and to model the thermo-hydro-mechanical behavior of buffers made of swelling clay submitted to high temperatures (over 100 deg C) during the water saturation process. The test has been carried out in a KBS-3 deposition hole at Aspo HRL. It was installed during the spring of 2003. Two steel heaters (3 m long, 0.6 m diameter) and two buffer arrangements have been investigated: the lower heater was surrounded by rings of compacted Wyoming bentonite only, whereas the upper heater was surrounded by a composite barrier, with a sand shield between the heater and the bentonite. The test was dismantled and sampled during the winter of 2009/2010. This report is the final report and a summary of all work performed within the TBT project. The design and the installation of the different components are summarized: the depositions hole, the heating system, the bentonite blocks with emphasis on the initial density and water content in these, the filling of slots with sand or pellets, the retaining construction with the plug, lid and nine anchor cables, the artificial saturation system, and finally the instrumentation. An overview of the operational conditions is presented: the power output from heaters, which was 1,500 W (and also 1,600 W) from each heater during the first ∼1,700 days, and then changed to 1,000 and 2,000 W, for the upper and lower heater respectively, during the last ∼600 days. From the start, the bentonite was hydrated with a groundwater from a nearby bore-hole, but this groundwater was replaced with de-ionized water from day ∼1,500, due to the high flow resistance of the injections points in the filter, which implied that a high filter pressure couldn't be sustained. The sand shield around the upper heater was hydrated from day ∼1,500 to day ∼1,800. The sensors data concerning

  9. Norcal Prototype LNG Truck Fleet: Final Results

    Energy Technology Data Exchange (ETDEWEB)

    2004-07-01

    U.S. DOE and National Renewable Energy Laboratory evaluated Norcal Waste Systems liquefied natural gas (LNG) waste transfer trucks. Trucks had prototype Cummins Westport ISXG engines. Report gives final evaluation results.

  10. Bisphenol A; Final Test Rule

    Science.gov (United States)

    EPA is issuing a final rule, under section 4 of the Toxic Substances Control Act (TSCA) requiring manufacturers and processors of bisphenol A, hereinafter BPA, (4.4’-isopropylidenediphenol, CAS No. 80-05—7) to conduct a 90-day inhalation study.

  11. Polymer systems testing: Final report

    International Nuclear Information System (INIS)

    1993-01-01

    Los Alamos National Laboratory (LANL) is in the process of decontaminating lead shielding material. The procedure involves abrasive surface etching of the shielding to remove the outer layer of lead that contains the majority of the radioactive contaminants. This procedure generates a small volume of mixed waste in the form of a wet residue containing lead, abrasive grit (Al 2 O 3 ), uranium and water. IC Technologies, Inc. (ICT) has developed several processes for the treatment of mixed wastes involving stabilizing/encapsulating the waste in a polymer monolith. The objective of the test program was to verify the applicability of ICT's technology to this specific waste stream and provide LANL baseline data on the performance of polymer encapsulation techniques. Polymer microencapsulation of lead shielding/blasting grit (surrogate) mixed waste was evaluated. Two polymers, melamine formaldehyde and polyester xylene, were used to examine the effect of waste loading on Toxicity Characteristic Leaching Procedure (TCLP) extract Pb concentration. Six levels of waste loading were evaluated by eleven tests. Significant reduction in Pb solubility during TCLP was achieved. Additional optimization to the single-stage microencapsulation technique utilized will be necessary to mitigate the toxic (RCRA) characteristic of the waste

  12. Final results for the neutron detector efficiencies

    International Nuclear Information System (INIS)

    Zhou Zuying; Tang Hongqing; Qi Bujia; Du Yanfeng; Zhou Chenwei; Xia Haihong; Chen Zemin; Chen Zhenpeng; Chen Yingtang

    1998-01-01

    Final results for neutron detector efficiencies of a liquid organic scintillator are presented. The comparisons of efficiency results to calculations with discrimination against γ-rays and without n-γ discrimination are shown out and discussed. The measured relative neutron detection efficiency of a liquid organic scintillator with the PSD constraint active is in good agreement with SCINFUL calculations from 9 to 40 Mev and NEFF7 calculations from 9 to 20 Mev, the upper limit of the latter code

  13. Material shielding of power frequency magnetic fields: Research and testing results from the EPRI Power Delivery Center-Lenox. Final report

    International Nuclear Information System (INIS)

    Anderson, C.B.

    1998-06-01

    Extensive investigations of a variety of material shielding methods have been performed at the EPRI Power Delivery Center--Lenox, Massachusetts. This work is part of a larger shielding investigation being done for EPRI by Electric Research and Management, Inc. (ERM) as part of the Magnetic Field Management Target in the EPRI Environment Group. Part of this work, involving cylinders of material, is to be included in a shielding handbook being prepared by ERM. Material shielding tests, not included in the handbook, as well as additional material shielding research, including testing, analyses, and computer simulations performed at the EPRI Power Delivery Center--Lenox are documented here. One of the major complications of using materials to shield magnetic fields is the mathematical complexity of the phenomenon involved. The result is that analytical solutions exist only for a very small number of simple geometries such as spheres, infinitely long cylinders, and infinite sheets. In practice, the materials typically come in the form of sheets. At present, there are no analytical methods for directly determining the shielding effectiveness of finite sheets of material, however, EPRI is sponsoring work in this area. There are some methods based on conformal mapping which can provide a solution for simple two-dimensional sheets. While such methods are useful in gaining insight into the mechanisms of shielding, they are not realistic enough to provide accurate shielding estimates. Empirical techniques are still required to determine the shielding effectiveness of material sheets. The material shielding tests and computer simulations are described in the report. The results of these tests and simulations have been used to develop a number of material shielding design rules for use in practical applications

  14. Benchmark Analysis for Condition Monitoring Test Techniques of Aged Low Voltage Cables in Nuclear Power Plants. Final Results of a Coordinated Research Project

    International Nuclear Information System (INIS)

    2017-10-01

    This publication provides information and guidelines on how to monitor the performance of insulation and jacket materials of existing cables and establish a programme of cable degradation monitoring and ageing management for operating reactors and the next generation of nuclear facilities. This research was done through a coordinated research project (CRP) with participants from 17 Member States. This group of experts compiled the current knowledge in a report together with areas of future research and development to cover aging mechanisms and means to identify and manage the consequences of aging. They established a benchmarking programme using cable samples aged under thermal and/or radiation conditions, and tested before and after ageing by various methods and organizations. In particular, 12 types of cable insulation or jacket material were tested, each using 14 different condition monitoring techniques. Condition monitoring techniques yield usable and traceable results. Techniques such as elongation at break, indenter modulus, oxidation induction time and oxidation induction temperature were found to work reasonably well for degradation trending of all materials. However, other condition monitoring techniques, such as insulation resistance, were only partially successful on some cables and other methods like ultrasonic or Tan δ were either unsuccessful or failed to provide reliable information to qualify the method for degradation trending or ageing assessment of cables. The electrical in situ tests did not show great promise for cable degradation trending or ageing assessment, although these methods are known to be very effective for finding and locating faults in cable insulation material. In particular, electrical methods such as insulation resistance and reflectometry techniques are known to be rather effective for locating insulation damage, hot spots or other faults in essentially all cable types. The advantage of electrical methods is that they can be

  15. Pressure locking test results

    Energy Technology Data Exchange (ETDEWEB)

    DeWall, K.G.; Watkins, J.C.; McKellar, M.G.; Bramwell, D. [Idaho National Engineering Lab., Idaho Falls, ID (United States)] [and others

    1996-12-01

    The U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Regulatory Research, is funding the Idaho National Engineering Laboratory (INEL) in performing research to provide technical input for their use in evaluating responses to Generic Letter 95-07, {open_quotes}Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves.{close_quotes} Pressure locking and thermal binding are phenomena that make a closed gate valve difficult to open. This paper discusses only the pressure locking phenomenon in a flexible-wedge gate valve; the authors will publish the results of their thermal binding research at a later date. Pressure locking can occur when operating sequences or temperature changes cause the pressure of the fluid in the bonnet (and, in most valves, between the discs) to be higher than the pressure on the upstream and downstream sides of the disc assembly. This high fluid pressure presses the discs against both seats, making the disc assembly harder to unseat than anticipated by the typical design calculations, which generally consider friction at only one of the two disc/seat interfaces. The high pressure of the bonnet fluid also changes the pressure distribution around the disc in a way that can further contribute to the unseating load. If the combined loads associated with pressure locking are very high, the actuator might not have the capacity to open the valve. The results of the NRC/INEL research discussed in this paper show that the relationship between bonnet pressure and pressure locking stem loads appears linear. The results also show that for this valve, seat leakage affects the bonnet pressurization rate when the valve is subjected to thermally induced pressure locking conditions.

  16. Pressure locking test results

    International Nuclear Information System (INIS)

    DeWall, K.G.; Watkins, J.C.; McKellar, M.G.; Bramwell, D.

    1996-01-01

    The U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Regulatory Research, is funding the Idaho National Engineering Laboratory (INEL) in performing research to provide technical input for their use in evaluating responses to Generic Letter 95-07, open-quotes Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves.close quotes Pressure locking and thermal binding are phenomena that make a closed gate valve difficult to open. This paper discusses only the pressure locking phenomenon in a flexible-wedge gate valve; we will publish the results of our thermal binding research at a later date. Pressure locking can occur when operating sequences or temperature changes cause the pressure of the fluid in the bonnet (and, in most valves, between the discs) to be higher than the pressure on the upstream and downstream sides of the disc assembly. This high fluid pressure presses the discs against both seats, making the disc assembly harder to unseat than anticipated by the typical design calculations, which generally consider friction at only one of the two disc/seat interfaces. The high pressure of the bonnet fluid also changes the pressure distribution around the disc in a way that can further contribute to the unseating load. If the combined loads associated with pressure locking are very high, the actuator might not have the capacity to open the valve. The results of the NRC/INEL research discussed in this paper show that the relationship between bonnet pressure and pressure locking stem loads appears linear. The results also show that for this valve, seat leakage affects the bonnet pressurization rate when the valve is subjected to thermally induced pressure locking conditions

  17. The final focus test beam project

    International Nuclear Information System (INIS)

    Burke, D.

    1991-05-01

    An overview is given of the Final Focus Test Beam (FFTB) that is being constructed as a prototype final focus system for a future electron-positron linear collider. This beam line will use as input the 50 GeV electron beam from the SLC linac, and is designed to reduce the transverse dimensions of the beam spot at the focal point to 1 μm. 5 refs., 2 figs., 1 tab

  18. The testing effect for mediator final test cues and related final test cues in online and laboratory experiments.

    Science.gov (United States)

    Coppens, Leonora C; Verkoeijen, Peter P J L; Bouwmeester, Samantha; Rikers, Remy M J P

    2016-05-31

    The testing effect is the finding that information that is retrieved during learning is more often correctly retrieved on a final test than information that is restudied. According to the semantic mediator hypothesis the testing effect arises because retrieval practice of cue-target pairs (mother-child) activates semantically related mediators (father) more than restudying. Hence, the mediator-target (father-child) association should be stronger for retrieved than restudied pairs. Indeed, Carpenter (2011) found a larger testing effect when participants received mediators (father) than when they received target-related words (birth) as final test cues. The present study started as an attempt to test an alternative account of Carpenter's results. However, it turned into a series of conceptual (Experiment 1) and direct (Experiment 2 and 3) replications conducted with online samples. The results of these online replications were compared with those of similar existing laboratory experiments through small-scale meta-analyses. The results showed that (1) the magnitude of the raw mediator testing effect advantage is comparable for online and laboratory experiments, (2) in both online and laboratory experiments the magnitude of the raw mediator testing effect advantage is smaller than in Carpenter's original experiment, and (3) the testing effect for related cues varies considerably between online experiments. The variability in the testing effect for related cues in online experiments could point toward moderators of the related cue short-term testing effect. The raw mediator testing effect advantage is smaller than in Carpenter's original experiment.

  19. CCTF CORE I test results

    International Nuclear Information System (INIS)

    Murao, Yoshio; Sudoh, Takashi; Akimoto, Hajime; Iguchi, Tadashi; Sugimoto, Jun; Fujiki, Kazuo; Hirano, Kenmei

    1982-07-01

    This report presents the results of the following CCTF CORE I tests conducted in FY. 1980. (1) Multi-dimensional effect test, (2) Evaluation model test, (3) FLECHT coupling test. On the first test, one-dimensional treatment of the core thermohydrodynamics was discussed. On the second and third tests, the test results were compared with the results calculated by the evaluation model codes and the results of the corresponding FLECHT-SET test (Run 2714B), respectively. The work was performed under contracts with the Atomic Energy Bureau of Science and Technology Agency of Japan. (author)

  20. Final report : mobile surveillance and wireless communication systems field operational test. Volume 2, FOT objectives, organization, system design, results, conclusions, and recommendations

    Science.gov (United States)

    1999-03-01

    The Mobile Surveillance and Wireless Communication Systems Field Operational Test (FOT) evaluated the performance of wireless traffic detection and communications systems in areas where permanent detectors, electrical power, and landline communicatio...

  1. Temperature Buffer Test. Final THM modelling

    International Nuclear Information System (INIS)

    Aakesson, Mattias; Malmberg, Daniel; Boergesson, Lennart; Hernelind, Jan; Ledesma, Alberto; Jacinto, Abel

    2012-01-01

    The Temperature Buffer Test (TBT) is a joint project between SKB/ANDRA and supported by ENRESA (modelling) and DBE (instrumentation), which aims at improving the understanding and to model the thermo-hydro-mechanical behavior of buffers made of swelling clay submitted to high temperatures (over 100 deg C) during the water saturation process. The test has been carried out in a KBS-3 deposition hole at Aespoe HRL. It was installed during the spring of 2003. Two heaters (3 m long, 0.6 m diameter) and two buffer arrangements have been investigated: the lower heater was surrounded by bentonite only, whereas the upper heater was surrounded by a composite barrier, with a sand shield between the heater and the bentonite. The test was dismantled and sampled during the winter of 2009/2010. This report presents the final THM modelling which was resumed subsequent to the dismantling operation. The main part of this work has been numerical modelling of the field test. Three different modelling teams have presented several model cases for different geometries and different degree of process complexity. Two different numerical codes, Code B right and Abaqus, have been used. The modelling performed by UPC-Cimne using Code B right, has been divided in three subtasks: i) analysis of the response observed in the lower part of the test, by inclusion of a number of considerations: (a) the use of the Barcelona Expansive Model for MX-80 bentonite; (b) updated parameters in the vapour diffusive flow term; (c) the use of a non-conventional water retention curve for MX-80 at high temperature; ii) assessment of a possible relation between the cracks observed in the bentonite blocks in the upper part of TBT, and the cycles of suction and stresses registered in that zone at the start of the experiment; and iii) analysis of the performance, observations and interpretation of the entire test. It was however not possible to carry out a full THM analysis until the end of the test due to

  2. Temperature Buffer Test. Final THM modelling

    Energy Technology Data Exchange (ETDEWEB)

    Aakesson, Mattias; Malmberg, Daniel; Boergesson, Lennart; Hernelind, Jan [Clay Technology AB, Lund (Sweden); Ledesma, Alberto; Jacinto, Abel [UPC, Universitat Politecnica de Catalunya, Barcelona (Spain)

    2012-01-15

    The Temperature Buffer Test (TBT) is a joint project between SKB/ANDRA and supported by ENRESA (modelling) and DBE (instrumentation), which aims at improving the understanding and to model the thermo-hydro-mechanical behavior of buffers made of swelling clay submitted to high temperatures (over 100 deg C) during the water saturation process. The test has been carried out in a KBS-3 deposition hole at Aespoe HRL. It was installed during the spring of 2003. Two heaters (3 m long, 0.6 m diameter) and two buffer arrangements have been investigated: the lower heater was surrounded by bentonite only, whereas the upper heater was surrounded by a composite barrier, with a sand shield between the heater and the bentonite. The test was dismantled and sampled during the winter of 2009/2010. This report presents the final THM modelling which was resumed subsequent to the dismantling operation. The main part of this work has been numerical modelling of the field test. Three different modelling teams have presented several model cases for different geometries and different degree of process complexity. Two different numerical codes, Code{sub B}right and Abaqus, have been used. The modelling performed by UPC-Cimne using Code{sub B}right, has been divided in three subtasks: i) analysis of the response observed in the lower part of the test, by inclusion of a number of considerations: (a) the use of the Barcelona Expansive Model for MX-80 bentonite; (b) updated parameters in the vapour diffusive flow term; (c) the use of a non-conventional water retention curve for MX-80 at high temperature; ii) assessment of a possible relation between the cracks observed in the bentonite blocks in the upper part of TBT, and the cycles of suction and stresses registered in that zone at the start of the experiment; and iii) analysis of the performance, observations and interpretation of the entire test. It was however not possible to carry out a full THM analysis until the end of the test due to

  3. Final Results of Shuttle MMOD Impact Database

    Science.gov (United States)

    Hyde, J. L.; Christiansen, E. L.; Lear, D. M.

    2015-01-01

    The Shuttle Hypervelocity Impact Database documents damage features on each Orbiter thought to be from micrometeoroids (MM) or orbital debris (OD). Data is divided into tables for crew module windows, payload bay door radiators and thermal protection systems along with other miscellaneous regions. The combined number of records in the database is nearly 3000. Each database record provides impact feature dimensions, location on the vehicle and relevant mission information. Additional detail on the type and size of particle that produced the damage site is provided when sampling data and definitive spectroscopic analysis results are available. Guidelines are described which were used in determining whether impact damage is from micrometeoroid or orbital debris impact based on the findings from scanning electron microscopy chemical analysis. Relationships assumed when converting from observed feature sizes in different shuttle materials to particle sizes will be presented. A small number of significant impacts on the windows, radiators and wing leading edge will be highlighted and discussed in detail, including the hypervelocity impact testing performed to estimate particle sizes that produced the damage.

  4. FIRST RESULTS FROM OEDOTENSIOMETRIC TESTS

    Directory of Open Access Journals (Sweden)

    Luigi Cavazza

    2008-09-01

    Full Text Available An oedotensiometer was used to examine to examine the behaviour of sieved sample of a swelling soil (a vertisol as well as of the same soils treated with solution of Na+ + Ca2+ to simulate the soil changes from excessive irrigation with brackish water. The oedometer test consisted in an infiltration of water from below through a ceramic porous plate at a feeding pressure of +10 cm water and successive drainage under a depression mostly of -112 cm of water. The rate of water entry as well as the swelling rate of the sample were monitored. Preliminary considerations regards the domains in which the shrinkage curve of a swelling soil is subdivided and make hypothesis on the swelling process expected when the infiltration from below of the sample is applied. The results support the hypothesis that when the water pressure is applied some water enters rather rapidly in the larger structural pores and is followed later by the swelling in the smaller pores, responsible for the basic domain. This first conclusion demonstrates that the assumption of a simultaneous movement of solid and liquid components in the sample, which is the base of most theoretical developments for swelling soils, cannot be accepted for the tested samples. Some cases with water clogging on the sample surface confirm a late final swelling of the soil and permitted to evaluate the hydraulic conductivity of the swollen soil. These manifestations are more evident in sodicated soils. The loading of the sample reduces the swelling of the sample and seems to reduce its permeability. The reduction of the feeding water pressure further reduces the sample swelling. The draining process from saturated soil sample shows that most of the process occurs in the large pores of the structural domain. This gives the possibility to evaluate the water diffusivity coefficient for the structural domain of the sample. In draining the soil with the highest sodication there was a variation of soil volume

  5. MITG test procedure and results

    International Nuclear Information System (INIS)

    Eck, M.E.; Mukunda, M.

    1983-01-01

    Elements and modules for Radioisotope Thermoelectric Generator have been performance tested since the inception of the RTG program. These test articles seldom resembled flight hardware and often lacked adequate diagnostic instrumentation. Because of this, performance problems were not identified in the early stage of program development. The lack of test data in an unexpected area often hampered the development of a problem solution. A procedure for conducting the MITG Test was developed in an effort to obtain data in a systematic, unambiguous manner. This procedure required the development of extensive data acquisition software and test automation. The development of a facility to implement the test procedure, the facility hardware and software requirements, and the results of the MITG testing are the subject of this paper

  6. Final results of the PERSEE experiment

    Science.gov (United States)

    Le Duigou, J.-M.; Lozi, J.; Cassaing, F.; Houairi, K.; Sorrente, B.; Montri, J.; Jacquinod, S.; Réess, J.-M.; Pham, L.; Lhomé, E.; Buey, T.; Hénault, F.; Marcotto, A.; Girard, P.; Mauclert, N.; Barillot, M.; Coudé du Foresto, V.; Ollivier, M.

    2017-11-01

    The PERSEE breadboard, developed by a consortium including CNES, IAS, LESIA, OCA, ONERA and TAS since 2006, is a nulling demonstrator that couples an infrared nulling interferometer with a formation flying simulator able to introduce realistic disturbances in the set-up. The general idea is to prove that an adequate optical design can considerably release the constraints applied at the spacecrafts level of a future interferometric space mission like Darwin/TPF or one of its precursors. The breadboard is now fully operational and the measurements sequences are managed from a remote control room using automatic procedures. A set of excellent results were obtained in 2011: the measured polychromatic nulling depth with non polarized light is 8.8x10-6 stabilized at 9x10-8 in the [1.65-2.45] μm spectral band (37% bandwidth) during 100s. This result was extended to a 7h duration thanks to an automatic calibration process. The various contributors are identified and the nulling budget is now well mastered. We also proved that harmonic disturbances in the 1-100Hz up to several tens of nm rms can be very efficiently corrected by a Linear Quadratic Control (LQG) if a sufficient flux is available. These results are important contributions to the feasibility of a future space based nulling interferometer.

  7. Final results of the search for $\

    CERN Document Server

    Agafonova, N.; Anokhina, A.; Aoki, S.; Ariga, A.; Ariga, T.; Bertolin, A.; Bozza, C.; Brugnera, R.; Buonaura, A.; Buontempo, S.; Chernyavskiy, M.; Chukanov, A.; Consiglio, L.; D'Ambrosio, N.; De Lellis, G.; De Serio, M.; del Amo Sanchez, P.; Di Crescenzo, A.; Di Ferdinando, D.; Di Marco, N.; Dmitrievsky, S.; Dracos, M.; Duchesneau, D.; Dusini, S.; Dzhatdoev, T.; Ebert, J.; Ereditato, A.; Favier, J.; Fini, R.A.; Fornari, F.; Fukuda, T.; Galati, G.; Garfagnini, A.; Gentile, V.; Goldberg, J.; Gornushkin, Y.; Gorbunov, S.; Grella, G.; Guler, A.M.; Gustavino, C.; Hagner, C.; Hara, T.; Hayakawa, T.; Hollnagel, A.; Hosseini, B.; Ishiguro, K.; Iuliano, A.; Jakovcic, K.; Jollet, C.; Kamiscioglu, C.; Kamiscioglu, M.; Kim, S.H.; Kitagawa, N.; Klicek, B.; Kodama, K.; Komatsu, M.; Kose, U.; Kreslo, I.; Laudisio, F.; Lauria, A.; Ljubicic, A.; Longhin, A.; Loverre, P.; Malgin, A.; Malenica, M.; Mandrioli, G.; Matsuo, T.; Matveev, V.; Mauri, N.; Medinaceli, E.; Meisel, F.; Meregaglia, A.; Mikado, S.; Miyanishi, M.; Mizutani, F.; Monacelli, P.; Montesi, M.C.; Morishima, K.; Muciaccia, M.T.; Naganawa, N.; Naka, T.; Nakamura, M.; Nakano, T.; Niwa, K.; Okateva, N.; Ogawa, S.; Ozaki, K.; Paoloni, A.; Paparella, L.; Park, B.D.; Pasqualini, L.; Pastore, A.; Patrizii, L.; Pessard, H.; Podgrudkov, D.; Polukhina, N.; Pozzato, M.; Pupilli, F.; Roda, M.; Roganova, T.; Rokujo, H.; Rosa, G.; Ryazhskaya, O.; Sato, O.; Schembri, A.; Shakiryanova, I.; Shchedrina, T.; Shibuya, H.; Shibayama, E.; Shiraishi, T.; Simone, S.; Sirignano, C.; Sirri, G.; Sotnikov, A.; Spinetti, M.; Stanco, L.; Starkov, N.; Stellacci, S.M.; Stipcevic, M.; Strolin, P.; Takahashi, S.; Tenti, M.; Terranova, F.; Tioukov, V.; Vasina, S.; Vilain, P.; Voevodina, E.; Votano, L.; Vuilleumier, J.L.; Wilquet, G.; Yoon, C.S.

    The OPERA experiment has discovered the tau neutrino appearance in the CNGS muon neutrino beam, in agreement with the 3 neutrino flavour oscillation hypothesis. The OPERA neutrino interaction target, made of Emulsion Cloud Chamber, was particularly efficient in the reconstruction of electromagnetic showers. Moreover, thanks to the very high granularity of the emulsion films, showers induced by electrons can be distinguished from those induced by $\\pi^0$s, thus allowing the detection of charged current interactions of electron neutrinos. In this paper the results of the search for electron neutrino events using the full dataset are reported. An improved method for the electron neutrino energy estimation is exploited. Data are compatible with the 3 neutrino flavour mixing model expectations and are used to set limits on the oscillation parameters of the 3+1 neutrino mixing model, in which an additional mass eigenstate $m_{4}$ is introduced. At high $\\Delta m^{2}_{41}$ $( \\gtrsim 0.1~\\textrm{eV}^{2})$, an upper ...

  8. Final Technical Report: Results of Phase 1

    Energy Technology Data Exchange (ETDEWEB)

    Narang, David, J.; Hambrick, Joshua; Srinivasan, Devarajan; Ayyannar, Raja; O' Brien, Kathleen

    2011-09-28

    Arizona Public Service Company (APS) expects that by 2027, renewable energy will account for 6,590 GWh in energy consumption by its customers. While much of this future energy will come from large centrally-located power plants, distributed renewable energy, sited at the point of end-use will also play an important role in meeting the needs of APS customers and is expected to provide 1,734 GWh. With increasing penetration of residential and commercial photovoltaic (PV) systems at the point of end-use, PV power generation not only offsets the load, but could also cause significant shifts in power flow patterns through the distribution system, and could possibly cause reversal of flow through some branches of a distribution circuit. Significant changes to power flow introduced into existing distribution systems due to the increased amount of PV systems may cause operational issues, including over-voltage on the distribution feeder (loss of voltage regulation) and incorrect operation of control equipment, which may lead to an increase in the number of operations and related equipment wear that could affect equipment reliability and customer power quality. Additionally, connecting generation resources to a distribution feeder can introduce additional sources of short-circuit current to the distribution system. This could potentially result in increased short-circuit currents, potentially reaching damaging levels, causing protection desensitization and a potential loss of protection coordination. These effects may be further compounded by variability of PV production due to shading by clouds. The effects of these phenomena in distributed PV applications are not well understood, and there is a great need to characterize this variability. This project will contribute to understanding the effects of high-penetration solar electricity on the design and operation of distribution systems by demonstrating how a high penetration of PV systems affects grid operations of a

  9. Engineering model cryocooler test results

    International Nuclear Information System (INIS)

    Skimko, M.A.; Stacy, W.D.; McCormick, J.A.

    1992-01-01

    This paper reports that recent testing of diaphragm-defined, Stirling-cycle machines and components has demonstrated cooling performance potential, validated the design code, and confirmed several critical operating characteristics. A breadboard cryocooler was rebuilt and tested from cryogenic to near-ambient cold end temperatures. There was a significant increase in capacity at cryogenic temperatures and the performance results compared will with code predictions at all temperatures. Further testing on a breadboard diaphragm compressor validated the calculated requirement for a minimum axial clearance between diaphragms and mating heads

  10. Nondestructive testing of thermocompression bonds. Final report

    International Nuclear Information System (INIS)

    Hale, G.M.

    1981-02-01

    A Scanning Laser Acoustic Microscope (SLAM) was used to characterize hybrid microcircuit beam lead bonds formed on thin film networks by a thermocompression process. Results from subsequent pull testing show that the SLAM offered no significant advantage over visual inspection for detecting bad bonds. Infrared microscopy and resistance measurements were also reviewed and rejected as being ineffective inspection methods

  11. Summary of CCTF test results

    International Nuclear Information System (INIS)

    Iguchi, T.; Murao, Y.; Sugimoto, J.; Akimoto, H.; Okubo, T.; Hojo, T.

    1987-01-01

    Conservatism of current safety analysis was assessed by comparing the predicted result with cylindrical core test facility (CCTF) test result performed at Japan Atomic Energy Research Institute. WREM code was selected for the assessment. The overall conservatism of the WREM code on the peak clad temperature prediction was confirmed against CCTF evaluation model (EM) test which simulated the typical initial and boundary conditions in the safety evaluation analysis. WREM code predicted the reasonable core boundary conditions and the conservatism of the code came mainly from core calculation. The conservatism of the WREM code against CCTF data could be attributed to the following three points: (1) no horizontal mixing assumption between subchannels at each elevation; (2) no modeling on heat transfer enhancement caused by the radial core power profile; and (3) conservative heat transfer correlations in the code

  12. Mobile evaporator corrosion test results

    International Nuclear Information System (INIS)

    Rozeveld, A.; Chamberlain, D.B.

    1997-05-01

    Laboratory corrosion tests were conducted on eight candidates to select a durable and cost-effective alloy for use in mobile evaporators to process radioactive waste solutions. Based on an extensive literature survey of corrosion data, three stainless steel alloys (304L, 316L, AL-6XN), four nickel-based alloys (825, 625, 690, G-30), and titanium were selected for testing. The corrosion tests included vapor phase, liquid junction (interface), liquid immersion, and crevice corrosion tests on plain and welded samples of candidate materials. Tests were conducted at 80 degrees C for 45 days in two different test solutions: a nitric acid solution. to simulate evaporator conditions during the processing of the cesium ion-exchange eluant and a highly alkaline sodium hydroxide solution to simulate the composition of Tank 241-AW-101 during evaporation. All of the alloys exhibited excellent corrosion resistance in the alkaline test solution. Corrosion rates were very low and localized corrosion was not observed. Results from the nitric acid tests showed that only 316L stainless steel did not meet our performance criteria. The 316L welded interface and crevice specimens had rates of 22.2 mpy and 21.8 mpy, respectively, which exceeds the maximum corrosion rate of 20 mpy. The other welded samples had about the same corrosion resistance as the plain samples. None of the welded samples showed preferential weld or heat-affected zone (HAZ) attack. Vapor corrosion was negligible for all alloys. All of the alloys except 316L exhibited either open-quotes satisfactoryclose quotes (2-20 mpy) or open-quotes excellentclose quotes (<2 mpy) corrosion resistance as defined by National Association of Corrosion Engineers. However, many of the alloys experienced intergranular corrosion in the nitric acid test solution, which could indicate a susceptibility to stress corrosion cracking (SCC) in this environment

  13. Testing the initial-final mass relationship of white dwarfs

    International Nuclear Information System (INIS)

    Catalan, S; Isern, J; Garcia-Berro, E; Ribas, I

    2009-01-01

    In this contribution we revisit the initial-final mass relationship of white dwarfs, which links the mass of a white dwarf with that of its progenitor in the main-sequence. Although this function is of paramount importance to several fields in modern astrophysics, it is still not well constrained either from the theoretical or the observational points of view. We present here a revision of the present semi-empirical initial-final mass relationship using all the available data and including our recent results obtained from studying white dwarfs in common proper motion pairs. We have also analyzed the results obtained so far to provide some clues on the dependence of this relationship on metallicity. Finally, we have also performed an indirect test of the initial-final mass relationship by studying its effect on the luminosity function and on the mass distribution of white dwarfs.

  14. Evaluating the RELM Test Results

    Directory of Open Access Journals (Sweden)

    Michael K. Sachs

    2012-01-01

    Full Text Available We consider implications of the Regional Earthquake Likelihood Models (RELM test results with regard to earthquake forecasting. Prospective forecasts were solicited for M≥4.95 earthquakes in California during the period 2006–2010. During this period 31 earthquakes occurred in the test region with M≥4.95. We consider five forecasts that were submitted for the test. We compare the forecasts utilizing forecast verification methodology developed in the atmospheric sciences, specifically for tornadoes. We utilize a “skill score” based on the forecast scores λfi of occurrence of the test earthquakes. A perfect forecast would have λfi=1, and a random (no skill forecast would have λfi=2.86×10-3. The best forecasts (largest value of λfi for the 31 earthquakes had values of λfi=1.24×10-1 to λfi=5.49×10-3. The best mean forecast for all earthquakes was λ̅f=2.84×10-2. The best forecasts are about an order of magnitude better than random forecasts. We discuss the earthquakes, the forecasts, and alternative methods of evaluation of the performance of RELM forecasts. We also discuss the relative merits of alarm-based versus probability-based forecasts.

  15. EFTF cobalt test assembly results

    International Nuclear Information System (INIS)

    Rawlins, J.A.; Wootan, D.W.; Carter, L.L.; Brager, H.R.; Schenter, R.E.

    1988-01-01

    A cobalt test assembly containing yttrium hydride pins for neutron moderation was irradiated in the Fast Flux Test Facility during Cycle 9A for 137.7 equivalent full power days at a power level fo 291 MW. The 36 test pins consisted of a batch of 32 pins containing cobalt metal to produce Co-60, and a set of 4 pins with europium oxide to produce Gd-153, a radioisotope used in detection of the bone disease Osteoporosis. Post-irradiation examination of the cobalt pins determined the Co-60 produced with an accuracy of about 5 %. The measured Co-60 spatially distributed concentrations were within 20 % of the calculated concentrations. The assembly average Co-60 measured activity was 4 % less than the calculated value. The europium oxide pins were gamma scanned for the europium isotopes Eu-152 and Eu-154 to an absolute accuracy of about 10 %. The measured europium radioisotpe anc Gd-153 concentrations were within 20 % of calculated values. In conclusion, the hydride assembly performed well and is an excellent vehicle for many Fast Flux Test Facility isotope production applications. The results also demonstrate that the calculational methods developed by the Westinghouse Hanford Company are very accurate. (author)

  16. The testing effect for mediator final test cues and related final test cues in online and laboratory experiments

    NARCIS (Netherlands)

    L.C. Coppens; P.P.J.L. Verkoeijen; S. Bouwmeester; R.M.J.P. Rikers

    2016-01-01

    Background The testing effect is the finding that information that is retrieved during learning is more often correctly retrieved on a final test than information that is restudied. According to the semantic mediator hypothesis the testing effect arises because retrieval practice of cue-target

  17. The testing effect for mediator final test cues and related final test cues in online and laboratory experiments

    NARCIS (Netherlands)

    Coppens, Leonora C.; Verkoeijen, Peter P. J. L.; Bouwmeester, Samantha; Rikers, Remy M. J. P.

    2016-01-01

    Background The testing effect is the finding that information that is retrieved during learning is more often correctly retrieved on a final test than information that is restudied. According to the semantic mediator hypothesis the testing effect arises because retrieval practice of cue-target pairs

  18. RSG Deployment Case Testing Results

    Energy Technology Data Exchange (ETDEWEB)

    Owsley, Stanley L.; Dodson, Michael G.; Hatchell, Brian K.; Seim, Thomas A.; Alexander, David L.; Hawthorne, Woodrow T.

    2005-09-01

    The RSG deployment case design is centered on taking the RSG system and producing a transport case that houses the RSG in a safe and controlled manner for transport. The transport case was driven by two conflicting constraints, first that the case be as light as possible, and second that it meet a stringent list of Military Specified requirements. The design team worked to extract every bit of weight from the design while striving to meet the rigorous Mil-Spec constraints. In the end compromises were made primarily on the specification side to control the overall weight of the transport case. This report outlines the case testing results.

  19. Salt decontamination demonstration test results

    International Nuclear Information System (INIS)

    Snell, E.B.; Heng, C.J.

    1983-06-01

    The Salt Decontamination Demonstration confirmed that the precipitation process could be used for large-scale decontamination of radioactive waste sale solution. Although a number of refinements are necessary to safely process the long-term requirement of 5 million gallons of waste salt solution per year, there were no observations to suggest that any fundamentals of the process require re-evaluation. Major accomplishments were: (1) 518,000 gallons of decontaminated filtrate were produced from 427,000 gallons of waste salt solution from tank 24H. The demonstration goal was to produce a minimum of 200,000 gallons of decontaminated salt solution; (2) cesium activity in the filtrate was reduced by a factor of 43,000 below the cesium activity in the tank 24 solution. This decontamination factor (DF) exceeded the demonstration goal of a DF greater than 10,000; (3) average strontium-90 activity in the filtrate was reduced by a factor of 26 to less than 10 3 d/m/ml versus a goal of less than 10 4 d/m/ml; and (4) the concentrated precipitate was washed to a final sodium ion concentration of 0.15 M, well below the 0.225 M upper limit for DWPF feed. These accomplishments were achieved on schedule and without incident. Total radiation exposure to personnel was less than 350 mrem and resulted primarily from sampling precipitate slurry inside tank 48. 3 references, 6 figures, 2 tables

  20. Cyclonic valve test: preliminary results

    Energy Technology Data Exchange (ETDEWEB)

    Monteiro, Andre Sampaio; Moraes, Carlos Alberto C.; Marins, Luiz Philipe M.; Soares, Fabricio; Oliveira, Dennis; Lima, Fabio Soares de; Airao, Vinicius [Petroleo Brasileiro S.A. (PETROBRAS), Rio de Janeiro, RJ (Brazil); Ton, Tijmen [Twister BV, Rijswijk (Netherlands)

    2012-07-01

    For many years, the petroleum industry has been developing a valve that input less shear to the flow for a given required pressure drop and this can be done using the cyclonic concept. This paper presents a comparison between the performances of a cyclonic valve (low shear) and a conventional globe valve. The aim of this work is to show the advantages of using a cyclonic low shear valve instead of the commonly used in the primary separation process by PETROBRAS. Tests were performed at PETROBRAS Experimental Center (NUEX) in Aracaju/SE varying some parameters: water cut; pressure loss (from 4 kgf/cm2 to 10 kgf/cm2); flow rates (30 m3/h and 45 m3/h). Results indicates a better performance of the cyclonic valve, if compared with a conventional one, and also that the difference of the performance, is a function of several parameters (emulsion stability, water content free, and oil properties). The cyclonic valve tested can be applied as a choke valve, as a valve between separation stages (for pressure drop), or for controlling the level of vessels. We must emphasize the importance to avoid the high shear imposed by conventional valves, because once the emulsion is created, it becomes more difficult to break it. New tests are being planned to occur in 2012, but PETROBRAS is also analyzing real cases where the applications could increase the primary process efficiency. In the same way, the future installations are also being designed considering the cyclonic valve usage. (author)

  1. Multi-frac test series. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Schmidt, R A; Warpinski, N R; Finley, S J; Shear, R C

    1981-11-01

    This paper describes a series of five full-scale tests performed to evaluate various multi-frac concepts. The tests were conducted at the Nevada Test Site in horizontal boreholes drilled in ash-fall tuff from a tunnel under 1300 ft of overburden.

  2. Manipulator Comparative Testing Program: Final report

    International Nuclear Information System (INIS)

    Draper, J.V.; Handel, S.J.; Sundstrom, E.; Herndon, J.N; Fujita, Y.; Maeda, M.

    1987-02-01

    The manipulator systems tested included the Meidensha BILARM 83A, the Central Research Laboratories Model M-2, and the GCA PaR Systems Model 6000. Six manipulator and control mode combinations were evaluated: (1) the BILARM in master/slave mode without force reflection, (2) the BILARM in master/slave mode with force reflection, (3) the Model M-2 in master/slave mode without force reflection, (4) the Model M-2 in master/slave mode with force reflection, (5) the BILARM with switchbox controls, and (6) the PaR 6000 with switchbox controls. The experiments examined differences between master/slave systems with and without force reflection and differences between master/slave systems and switchbox-controlled systems. A fourth experiment examined the relative contributions of the remote viewing system and the manipulator system to the performance of remote handling tasks. Results of the experiments showed that operators using the Model M-2 in master/slave mode had significantly faster times to completion than operators using the BILARM in master/slave mode, with about the same error rate per trial. Operators were slower using the BILARM with force reflection than without it, and they committed more errors. There was no statistically significant difference between force-reflection and nonforce-reflection conditions for the M-2 manipulator for any of the performance criteria. Tasks and procedures used in this testing were not sensitive to differences within any single system. No inferences about the effect of force reflection on remote task performance should be made from these data. The two manipulator systems in switchbox mode had significantly slower times to completion than any system in master/slave mode, with approximately the same error rate per trial. There were no significant differences between the BILARM in switchbox mode and the PaR arm

  3. 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.

  4. Test Results for CSTR Test 4

    International Nuclear Information System (INIS)

    Lee, D.D.

    2001-01-01

    One of the 3 technologies currently being developed for the Savannah River Salt Waste Processing Program is the Small-Tank Tetraphenylborate Process (STTP). This process uses sodium tetraphenylborate to precipitate and remove radioactive Cs from the waste and monosodium titanate to sorb and remove radioactive Sr and actinides. ORNL is demonstrating this process at the 1:4000 scale using a 20-liter continuous-flow stirred tank reactor (CSTR) system. The primary goal of Test 4 was to verify that the STTP process could achieve and maintain the necessary Cs decontamination while TPB was actively decomposing. Even with TPB being decomposed by the off-normal conditions of this test, the decontaimination factor for 137 Cs obtained for the filtrate from the Slurry Concentrating Tank ranged from 47,000 to 646,000, exceeding the WAC standard

  5. Irradiation effects test series test IE-1 test results report

    International Nuclear Information System (INIS)

    Quapp, W.J.; Allison, C.M.; Farrar, L.C.; Mehner, A.S.

    1977-03-01

    The report describes the results of the first programmatic test in the Nuclear Regulatory Commission Irradiation Effects Test Series. This test (IE-1) used four 0.97m long PWR-type fuel rods fabricated from previously irradiated Saxton fuel. The objectives of this test were to evaluate the effect of fuel pellet density on pellet-cladding interaction during a power ramp and to evaluate the influence of the irradiated state of the fuel and cladding on rod behavior during film boiling operation. Data are presented on the behavior of irradiated fuel rods during steady-state operation, a power ramp, and film boiling operation. The effects of as-fabricated gap size, as-fabricated fuel density, rod power, and power ramp rate on pellet-cladding interaction are discussed. Test data are compared with FRAP-T2 computer model predictions, and comments on the consequences of sustained film boiling operation on irradiated fuel rod behavior are provided

  6. Sanitary Landfill Supplemental Test Final Report

    International Nuclear Information System (INIS)

    Altman, D.J.

    1999-01-01

    This report summarizes the performance of the Sanitary Landfill Supplemental Test data, an evaluation of applicability, conclusions, recommendations, and related information for implementation of this remediation technology at the SRS Sanitary Landfill

  7. Spacecraft fabrication and test MODIL. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Saito, T.T.

    1994-05-01

    This report covers the period from October 1992 through the close of the project. FY 92 closed out with the successful briefing to industry and with many potential and important initiatives in the spacecraft arena. Due to the funding uncertainties, we were directed to proceed as if our funding would be approximately the same as FY 92 ($2M), but not to make any major new commitments. However, the MODIL`s FY 93 funding was reduced to $810K and we were directed to concentrate on the cryocooler area. The cryocooler effort completed its demonstration project. The final meetings with the cryocooler fabricators were very encouraging as we witnessed the enthusiastic reception of technology to help them reduce fabrication uncertainties. Support of the USAF Phillips Laboratory cryocooler program was continued including kick-off meetings for the Prototype Spacecraft Cryocooler (PSC). Under Phillips Laboratory support, Gill Cruz visited British Aerospace and Lucas Aerospace in the United Kingdom to assess their manufacturing capabilities. In the Automated Spacecraft & Assembly Project (ASAP), contracts were pursued for the analysis by four Brilliant Eyes prime contractors to provide a proprietary snap shot of their current status of Integrated Product Development. In the materials and structure thrust the final analysis was completed of the samples made under the contract (``Partial Automation of Matched Metal Net Shape Molding of Continuous Fiber Composites``) to SPARTA. The Precision Technologies thrust funded the Jet Propulsion Laboratory to prepare a plan to develop a Computer Aided Alignment capability to significantly reduce the time for alignment and even possibly provide real time and remote alignment capability of systems in flight.

  8. Irradiation effects test Series Scoping Test 1: test results report

    International Nuclear Information System (INIS)

    Quapp, W.J.; Allison, C.M.; Farrar, L.C.

    1977-09-01

    The report describes the results of the first scoping test in the Irradiation Effects Test Series conducted by the Thermal Fuels Behavior Program, which is part of the Water Reactor Research Program of EG and G Idaho, Inc. The research is sponsored by the United States Nuclear Regulatory Commission. This test used an unirradiated, three-foot-long, PWR-type fuel rod. The objective of this test was to thoroughly evaluate the remote fabrication procedures to be used for irradiated rods in future tests, handling plans, and reactor operations. Additionally, selected fuel behavior data were obtained. The fuel rod was subjected to a series of preconditioning power cycles followed by a power increase which brought the fuel rod power to about 20.4 kW/ft peak linear heat rating at a coolant mass flux of 1.83 x 10 6 lb/hr-ft 2 . Film boiling occurred for a period of 4.8 minutes following flow reductions to 9.6 x 10 5 and 7.5 x 10 5 lb/hr-ft 2 . The test fuel rod failed following reactor shutdown as a result of heavy internal and external cladding oxidation and embrittlement which occurred during the film boiling operation

  9. Chemical compatibility screening test results

    International Nuclear Information System (INIS)

    Nigrey, P.J.; Dickens, T.G.

    1997-12-01

    A program for evaluating packaging components that may be used in transporting mixed-waste forms has been developed and the first phase has been completed. This effort involved the screening of ten plastic materials in four simulant mixed-waste types. These plastics were butadiene-acrylonitrile copolymer rubber, cross-linked polyethylene (XLPE), epichlorohydrin rubber, ethylene-propylene rubber (EPDM), fluorocarbon (Viton or Kel-F), polytetrafluoroethylene, high-density polyethylene (HDPE), isobutylene-isoprene copolymer rubber (butyl), polypropylene, and styrene-butadiene rubber (SBR). The selected simulant mixed wastes were (1) an aqueous alkaline mixture of sodium nitrate and sodium nitrite; (2) a chlorinated hydrocarbon mixture; (3) a simulant liquid scintillation fluid; and (4) a mixture of ketones. The testing protocol involved exposing the respective materials to 286,000 rads of gamma radiation followed by 14-day exposures to the waste types at 60 degrees C. The seal materials were tested using vapor transport rate (VTR) measurements while the liner materials were tested using specific gravity as a metric. For these tests, a screening criterion of 0.9 g/hr/m 2 for VTR and a specific gravity change of 10% was used. Based on this work, it was concluded that while all seal materials passed exposure to the aqueous simulant mixed waste, EPDM and SBR had the lowest VTRs. In the chlorinated hydrocarbon simulant mixed waste, only Viton passed the screening tests. In both the simulant scintillation fluid mixed waste and the ketone mixture simulant mixed waste, none of the seal materials met the screening criteria. For specific gravity testing of liner materials, the data showed that while all materials with the exception of polypropylene passed the screening criteria, Kel-F, HDPE, and XLPE offered the greatest resistance to the combination of radiation and chemicals

  10. Irradiation effects test series, test IE-5. Test results report

    International Nuclear Information System (INIS)

    Croucher, D.W.; Yackle, T.R.; Allison, C.M.; Ploger, S.A.

    1978-01-01

    Test IE-5, conducted in the Power Burst Facility at the Idaho National Engineering Laboratory, employed three 0.97-m long pressurized water reactor type fuel rods, fabricated from previously irradiated zircaloy-4 cladding and one similar rod fabricated from unirradiated cladding. The objectives of the test were to evaluate the influence of simulated fission products, cladding irradiation damage, and fuel rod internal pressure on pellet-cladding interaction during a power ramp and on fuel rod behavior during film boiling operation. The four rods were subjected to a preconditioning period, a power ramp to an average fuel rod peak power of 65 kW/m, and steady state operation for one hour at a coolant mass flux of 4880 kg/s-m 2 for each rod. After a flow reduction to 1800 kg/s-m 2 , film boiling occurred on one rod. Additional flow reductions to 970 kg/s-m 2 produced film boiling on the three remaining fuel rods. Maximum time in film boiling was 80s. The rod having the highest initial internal pressure (8.3 MPa) failed 10s after the onset of film boiling. A second rod failed about 90s after reactor shutdown. The report contains a description of the experiment, the test conduct, test results, and results from the preliminary postirradiation examination. Calculations using a transient fuel rod behavior code are compared with the test results

  11. Final Test Analysis of Post Graduate Medical Residents

    Directory of Open Access Journals (Sweden)

    Maliheh Arab

    2009-04-01

    Full Text Available Background and purpose: Multiple choice questions are the most frequent test for medical students. It is important to analysis the overall response to individual  questions in the test.The aim of this study is to analyse questions of post graduate medical residency  tests.Methods: Final annual local (Ramadan medical school and national tests given to three Residency groups  including  17 Obstetrics  and gynecology testees,  7 pediatrics  and  12 internal  medicine  in 2004 were studied. In local tests residents answered to 148, 150 and 144 and in national  tests to ISO MCQS. Questions were  evaluated regarding cognitive domain level, Difficultly index and Discriminative index  and finally to evaluate  the optimal,  proper, acceptable and  ''must  omitted" questions.Results: Questions of local Obstetrics and gynecology, pediatrics and internal medicine tests evaluated the "recall" level in 72%, 72% and 51% and in national  tests 71%,  35% and 19%,  respectively. Questions  with  Discriminative indices  of 0.7 or more (proper  were 3 and  5% in  Obstetrics  and gynecology, 3.5% and 1% in pediatrics and 1% in local and national tests. Proper difficulty indices (30-70  were shown in 53% and 54% in Obstetrics  and gynecology, 34% and 43% in pediatrics and 40% and  42% in internal  medicine.  Generally  evaluating,  "must  omitted" questions in local and national tests were 76% in Obstetrics and gynecology, 81% and 79% in pediatrics and 91% and 85% in internal medicine. The most common causes making the questions to be considered  "must omitted" in studied tests were negative, zero or less than 0.2 Discriminative indices.Conclusion: Test analysis  of final  annual  local  (Ramadan medical  school  and national  tests  of Obstetrics  and gynecology, Pediatrics and internal medicine residency  programs  in 2004 revealed that most of the questions  are planned  in  "recall" level, harbor  improper

  12. A final test for AMS at ESTEC

    CERN Multimedia

    Paola Catapano

    2010-01-01

    The Alpha Magnetic Spectrometer (AMS) left CERN on Friday 12th February on the first leg of its journey to the International Space Station (ISS). The special convoy carrying the experiment arrived at the European Space Agency’s research and technology centre (ESTEC) in the Netherlands at 4.30 pm on Tuesday 16th February. AMS will then fly to the Kennedy Space Center in Florida before lifting off aboard the space shuttle.   Arrival of the AMS detector at ESTEC in the Netherlands (Credit ESA/Jari Makinen) The transportation of an 8.5-tonne load filled with superfluid helium across Europe is no ordinary shipment. The AMS detector was first inserted into a supporting structure, specially built by the collaboration’s mechanical engineers, then surrounded by protective plastic foil, placed in a box and finally carefully loaded onto the special lorry also carrying a diesel generator running a pump to keep the helium at the right temperature (about 2 K). Its initial destination is ES...

  13. Railgun bore material test results

    International Nuclear Information System (INIS)

    Wang, S.Y.; Burton, R.L.; Witherspoon, F.D.; Bloomberg, H.W.; Goldstein, S.A.; Tidman, D.A.; Winsor, N.K.

    1987-01-01

    GT-Devices, Inc. has constructed a material test facility (MTF) to study the fundamental heat transfer problem of both railgun and electrothermal guns, and to test candidate gun materials under real plasma conditions. The MTF electrothermally produces gigawatt-level plasmas with pulse lengths of 10-30 microseconds. Circular bore and non-circular bore test barrels have been successfully operated under a wide range of simulated heating environments for EM launchers. Diagnostics include piezoelectric MHz pressure probes, time-of-flight probes, and current and voltage probes. Ablation measurements are accomplished by weighing and optical inspection, including borescope, optical microscope, and scanning electron microscope (SEM). From these measurements the ablation threshold for both the rail and insulator materials can be determined as a function of plasma heating. The MTF diagnostics are supported by an unsteady 1-D model of MTF which uses the flux-corrected transport (FCT) algorithm to calculate the fluid equations in conservative form. A major advantage of the FCT algorithm is that it can model gas dynamic shock behaviour without the requirement of numerical diffusion. The principle use of the code is to predict the material surface temperature ΔT/α from the unsteady heat transfer q(t)

  14. Arc melter demonstration baseline test results

    International Nuclear Information System (INIS)

    Soelberg, N.R.; Chambers, A.G.; Anderson, G.L.; Oden, L.L.; O'Connor, W.K.; Turner, P.C.

    1994-07-01

    This report describes the test results and evaluation for the Phase 1 (baseline) arc melter vitrification test series conducted for the Buried Waste Integrated Demonstration program (BWID). Phase 1 tests were conducted on surrogate mixtures of as-incinerated wastes and soil. Some buried wastes, soils, and stored wastes at the INEL and other DOE sites, are contaminated with transuranic (TRU) radionuclides and hazardous organics and metals. The high temperature environment in an electric arc furnace may be used to process these wastes to produce materials suitable for final disposal. An electric arc furnace system can treat heterogeneous wastes and contaminated soils by (a) dissolving and retaining TRU elements and selected toxic metals as oxides in the slag phase, (b) destroying organic materials by dissociation, pyrolyzation, and combustion, and (c) capturing separated volatilized metals in the offgas system for further treatment. Structural metals in the waste may be melted and tapped separately for recycle or disposal, or these metals may be oxidized and dissolved into the slag. The molten slag, after cooling, will provide a glass/ceramic final waste form that is homogeneous, highly nonleachable, and extremely durable. These features make this waste form suitable for immobilization of TRU radionuclides and toxic metals for geologic timeframes. Further, the volume of contaminated wastes and soils will be substantially reduced in the process

  15. Boraflex test results and evaluation

    International Nuclear Information System (INIS)

    Lindquist, K.; Kline, D.E.; Haley, T.C.

    1993-02-01

    New data developed, collected, and evaluated to further assess the in-pool performance of the neutron absorber material, Boraflex. The data are from new EPRI test programs, utility surveillance programs, and blackness testing at a number of plants. This new data provides a basis for quantifying the gap phenomenon in full length panels of Boraflex in spent fuel racks; the maximum anticipated gap size, frequency of gap occurrence, and axial distribution of gaps. Methods have been developed to assess the reactivity effects of gaps and Boraflex shrinkage. The analyses presented demonstrates that the reactivity effect of gaps is very small, not much larger than the statistical variations inherent in the calculational method. The data and analyses presented serve to close the issue of gap formation and shrinkage in panels of Boraflex and the effect of such gaps and shrinkage on the reactivity of the fuel/rack configuration. Ongoing EPRI programs to assess the long term performance of Boraflex in spent fuel storage racks are described

  16. Irradiation Effects Test Series: Test IE-3. Test results report

    International Nuclear Information System (INIS)

    Farrar, L.C.; Allison, C.M.; Croucher, D.W.; Ploger, S.A.

    1977-10-01

    The objectives of the test reported were to: (a) determine the behavior of irradiated fuel rods subjected to a rapid power increase during which the possibility of a pellet-cladding mechanical interaction failure is enhanced and (b) determine the behavior of these fuel rods during film boiling following this rapid power increase. Test IE-3 used four 0.97-m long pressurized water reactor type fuel rods fabricated from previously irradiated fuel. The fuel rods were subjected to a preconditioning period, followed by a power ramp to 69 kW/m at a coolant mass flux of 4920 kg/s-m 2 . After a flow reduction to 2120 kg/s-m 2 , film boiling occurred on the fuel rods. One rod failed approximately 45 seconds after the reactor was shut down as a result of cladding embrittlement due to extensive cladding oxidation. Data are presented on the behavior of these irradiated fuel rods during steady-state operation, the power ramp, and film boiling operation. The effects of a power ramp and power ramp rates on pellet-cladding interaction are discussed. Test data are compared with FRAP-T3 computer model calculations and data from a previous Irradiation Effects test in which four irradiated fuel rods of a similar design were tested. Test IE-3 results indicate that the irradiated state of the fuel rods did not significantly affect fuel rod behavior during normal, abnormal (power ramp of 20 kW/m per minute), and accident (film boiling) conditions

  17. Irradiation Effects Test Series: Test IE-2. Test results report

    International Nuclear Information System (INIS)

    Allison, C.M.; Croucher, D.W.; Ploger, S.A.; Mehner, A.S.

    1977-08-01

    The report describes the results of a test using four 0.97-m long PWR-type fuel rods with differences in diametral gap and cladding irradiation. The objective of this test was to provide information about the effects of these differences on fuel rod behavior during quasi-equilibrium and film boiling operation. The fuel rods were subjected to a series of preconditioning power cycles of less than 30 kW/m. Rod powers were then increased to 68 kW/m at a coolant mass flux of 4900 kg/s-m 2 . After one hour at 68 kW/m, a power-cooling-mismatch sequence was initiated by a flow reduction at constant power. At a flow of 2550 kg/s-m 2 , the onset of film boiling occurred on one rod, Rod IE-011. An additional flow reduction to 2245 kg/s-m 2 caused the onset of film boiling on the remaining three rods. Data are presented on the behavior of fuel rods during quasiequilibrium and during film boiling operation. The effects of initial gap size, cladding irradiation, rod power cycling, a rapid power increase, and sustained film boiling are discussed. These discussions are based on measured test data, preliminary postirradiation examination results, and comparisons of results with FRAP-T3 computer model calculations

  18. The Final Results from the Sudbury Neutrino Observatory

    CERN Multimedia

    CERN. Geneva

    2010-01-01

    The Sudbury Neutrino Observatory (SNO) was a water Cherenkov detector dedicated to investigate elementary particles called neutrinos. It successfully took data between 1999 and 2006. The detector was unique in its use of heavy water as a detection medium, permitting it to make a solar model-independent test of solar neutrino mixing. In fact, SNO conclusively showed that solar neutrinos oscillate on their way from the core of the Sun to the Earth. This groundbreaking observation was made during three independent phases of the experiment. Even if data taking ended, SNO is still in a mode of precise determination of the solar neutrino oscillation parameters because all along SNO had developed several methods to tell charged-current events apart from neutral-current events. This ability is crucial for the final and ultimate data analysis of all the phases. The physics reach of a combined three-phase solar analysis will be reviewed together with results and subtleties about solar neutrino physics.

  19. Expanded studies of linear collider final focus systems at the Final Focus Test Beam

    International Nuclear Information System (INIS)

    Tenenbaum, P.G.

    1995-12-01

    In order to meet their luminosity goals, linear colliders operating in the center-of-mass energy range from 3,50 to 1,500 GeV will need to deliver beams which are as small as a few Manometers tall, with x:y aspect ratios as large as 100. The Final Focus Test Beam (FFTB) is a prototype for the final focus demanded by these colliders: its purpose is to provide demagnification equivalent to those in the future linear collider, which corresponds to a focused spot size in the FFTB of 1.7 microns (horizontal) by 60 manometers (vertical). In order to achieve the desired spot sizes, the FFTB beam optics must be tuned to eliminate aberrations and other errors, and to ensure that the optics conform to the desired final conditions and the measured initial conditions of the beam. Using a combination of incoming-beam diagnostics. beam-based local diagnostics, and global tuning algorithms, the FFTB beam size has been reduced to a stable final size of 1.7 microns by 70 manometers. In addition, the chromatic properties of the FFTB have been studied using two techniques and found to be acceptable. Descriptions of the hardware and techniques used in these studies are presented, along with results and suggestions for future research

  20. Expanded studies of linear collider final focus systems at the Final Focus Test Beam

    Energy Technology Data Exchange (ETDEWEB)

    Tenenbaum, Peter Gregory [Stanford Univ., CA (United States)

    1995-12-01

    In order to meet their luminosity goals, linear colliders operating in the center-of-mass energy range from 3,50 to 1,500 GeV will need to deliver beams which are as small as a few Manometers tall, with x:y aspect ratios as large as 100. The Final Focus Test Beam (FFTB) is a prototype for the final focus demanded by these colliders: its purpose is to provide demagnification equivalent to those in the future linear collider, which corresponds to a focused spot size in the FFTB of 1.7 microns (horizontal) by 60 manometers (vertical). In order to achieve the desired spot sizes, the FFTB beam optics must be tuned to eliminate aberrations and other errors, and to ensure that the optics conform to the desired final conditions and the measured initial conditions of the beam. Using a combination of incoming-beam diagnostics. beam-based local diagnostics, and global tuning algorithms, the FFTB beam size has been reduced to a stable final size of 1.7 microns by 70 manometers. In addition, the chromatic properties of the FFTB have been studied using two techniques and found to be acceptable. Descriptions of the hardware and techniques used in these studies are presented, along with results and suggestions for future research.

  1. The Final Focus Test Beam laser referene system

    International Nuclear Information System (INIS)

    Bressler, V.E.; Ruland, R.E.

    1993-05-01

    The original design for the SLAC linac included an alignment reference system with 270 diffraction gratings situated along the 3000 meter linac. These gratings have provided SLAC with a global reference line repeatable to within 200 micro meters. For the Final Focus Test Beam, this laser system has been extended and 13 new diffraction gratings have been installed. Improvements targets and the availability of new instruments allows us to evaluate the performance of the laser reference system at the 510 micro meter level. An explanation of the system and the results of our evaluation are presented

  2. Anthraquinone Final Reporting and Recordkeeping Requirements and Test Rule

    Science.gov (United States)

    EPA is issuing a final rule, under section 4 of the Toxic Substances Control Act (TSCA), requiring manufacturers and processors of 9,10-anthraquinone (CAS No. 84—65—1), hereinafter anthraquinone, to perform testing.

  3. Abnormal Cervical Cancer Screening Test Results

    Science.gov (United States)

    ... AQ FREQUENTLY ASKED QUESTIONS FAQ187 GYNECOLOGIC PROBLEMS Abnormal Cervical Cancer Screening Test Results • What is cervical cancer screening? • What causes abnormal cervical cancer screening test ...

  4. Final result of the Munich-Frascati gravitational radiation experiment

    International Nuclear Information System (INIS)

    Kafka, P.; Schnupp, L.

    1977-02-01

    Within 580 days of usable common observation time between July 1973 and February 1976, this Weber-type coincidence experiment had set the lowest upper limits to the rates of gravitational wave pulses. We report the total result up to the dismantling of the detectors. We also describe a reevaluation of our data using Weber's preferred algorithm for two months in 1974 during which Weber communicated to have found a particularly significant effect in his own experiment. Finally, we confront the negative results with the far aims of gravitational pulse astronomy. (orig.) [de

  5. Final result of the Munich-Frascati gravitational radiation experiment

    International Nuclear Information System (INIS)

    Kafka, P.; Schnupp, L.

    1978-01-01

    Within 580 days of usable common observation time between July 1973 and February 1976, this Weber-type coincidence experiment had set the lowest upper limits to the rates of gravitational wave pulses. We report the total result up to the dismantling of the detectors. We also describe a re-evaluation of our data using Weber's preferred algorithm for two months in 1974 during which Weber communicated to have found a particularly significant effect in his own experiment. Finally, we confront the negative results with the far aims of gravitational pulse astronomy. (orig.) [de

  6. Final turbine and test facility design report Alden/NREC fish friendly turbine

    Energy Technology Data Exchange (ETDEWEB)

    Cook, Thomas C. [Alden Research Lab., Holden, MA (United States); Cain, Stuart A. [Alden Research Lab., Holden, MA (United States); Fetfatsidis, Paul [Alden Research Lab., Holden, MA (United States); Hecker, George E. [Alden Research Lab., Holden, MA (United States); Stacy, Philip S. [Alden Research Lab., Holden, MA (United States)

    2000-09-01

    The final report provides an overview of the Alden/NREC Fish Friendly turbine design phase, turbine test plan, preliminary test results, costs, schedule, and a hypothetical application at a real world project.

  7. CERTS Microgrid Laboratory Test Bed - PIER Final Project Report

    Energy Technology Data Exchange (ETDEWEB)

    Eto, Joseph H.; Eto, Joseph H.; Lasseter, Robert; Schenkman, Ben; Klapp, Dave; Linton, Ed; Hurtado, Hector; Roy, Jean; Lewis, Nancy Jo; Stevens, John; Volkommer, Harry

    2008-07-25

    The objective of the CERTS Microgrid Laboratory Test Bed project was to enhance the ease of integrating small energy sources into a microgrid. The project accomplished this objective by developing and demonstrating three advanced techniques, collectively referred to as the CERTS Microgrid concept, that significantly reduce the level of custom field engineering needed to operate microgrids consisting of small generating sources. The techniques comprising the CERTS Microgrid concept are: 1) a method for effecting automatic and seamless transitions between grid-connected and islanded modes of operation; 2) an approach to electrical protection within the microgrid that does not depend on high fault currents; and 3) a method for microgrid control that achieves voltage and frequency stability under islanded conditions without requiring high-speed communications. The techniques were demonstrated at a full-scale test bed built near Columbus, Ohio and operated by American Electric Power. The testing fully confirmed earlier research that had been conducted initially through analytical simulations, then through laboratory emulations, and finally through factory acceptance testing of individual microgrid components. The islanding and resychronization method met all Institute of Electrical and Electronics Engineers 1547 and power quality requirements. The electrical protections system was able to distinguish between normal and faulted operation. The controls were found to be robust and under all conditions, including difficult motor starts. The results from these test are expected to lead to additional testing of enhancements to the basic techniques at the test bed to improve the business case for microgrid technologies, as well to field demonstrations involving microgrids that involve one or mroe of the CERTS Microgrid concepts.

  8. Sanitary landfill in situ bioremediation optimization test. Final report

    International Nuclear Information System (INIS)

    1996-01-01

    This work was performed as part of a corrective action plan for the Savannah River Site Sanitary Landfill. This work was performed for the Westinghouse Savannah River Company Environmental Restoration Department as part of final implementation of a groundwater remediation system for the SRS Sanitary Landfill. Primary regulatory surveillance was provided by the South Carolina Department of Health and Environmental Control and the US Environmental Protection Agency (Region IV). The characterization, monitoring and remediation systems in the program generally consisted of a combination of innovative and baseline methods to allow comparison and evaluation. The results of these studies will be used to provide input for the full-scale groundwater remediation system for the SRS Sanitary Landfill. This report summarizes the performance of the Sanitary Landfill In Situ Optimization Test data, an evaluation of applicability, conclusions, recommendations, and related information for implementation of this remediation technology at the SRS Sanitary Landfill

  9. Reproducibility of the results in ultrasonic testing

    International Nuclear Information System (INIS)

    Chalaye, M.; Launay, J.P.; Thomas, A.

    1980-12-01

    This memorandum reports on the conclusions of the tests carried out in order to evaluate the reproducibility of ultrasonic tests made on welded joints. FRAMATOME have started a study to assess the dispersion of results afforded by the test line and to characterize its behaviour. The tests covered sensors and ultrasonic generators said to be identical to each other (same commercial batch) [fr

  10. Innovative improvements of thermal response tests - Final report

    Energy Technology Data Exchange (ETDEWEB)

    Poppei, J.; Schwarz, R. [AF-Colenco Ltd, Baden (Switzerland); Peron, H.; Silvani, C; Steinmann, G.; Laloui, L. [Swiss Federal Institute of Technology, Laboratoire de Mecanique des Sols, Lausanne (Switzerland); Wagner, R.; Lochbuehler, T.; Rohner, E. [Geowatt AG, Zuerich (Switzerland)

    2008-12-15

    This illustrated final report for Swiss Federal Office of Energy (SFOE) takes a look at innovative improvements to thermal response tests that are used to investigate the thermo-physical properties of the ground for the purpose of dimensioning borehole heat exchangers. Recent technical developments in the borehole investigation tools area provide a promising prerequisite for improved estimates of thermal conductivity. A mini-module developed at the Swiss Federal Institute of Technology EPFL which is suitable for fast and flexible thermal response testing is discussed as is a wireless miniature data logger for continuous temperature recordings in borehole heat exchangers up to a depth of 350 m. This allows high-resolution vertical temperature profiling in boreholes. International state-of-the-art methods are reviewed. The adaptations to the analytical methods necessary for the effective application of these tools are discussed and numerical methods available are looked at. The testing of the methods developed and their results are discussed, as is the influence of ground-water flow.

  11. HERBE- Analysis of test operation results

    International Nuclear Information System (INIS)

    Pesic, M. et.al.

    1991-01-01

    This document is part of the safety analyses performed for the RB reactor operation with the coupled fast-thermal system HERBE and is part of the final safety report together with the 'Report on test operation of HERBE for the period Dec. 15 1989 - May 15 1990. This report covers the following main topics: determination of reactivity variations dependent on the variations moderator critical level; determination of reactivity for the flooded neutron converter; and the accident analysis of neutron converter flooding

  12. The 'gender gap' in final examination results at Oxford University.

    Science.gov (United States)

    Mellanby, J; Martin, M; O'Doherty, J

    2000-08-01

    A lower proportion of women than men obtain first class degrees at British universities (the so-called gender gap). At Oxford University, this difference is not seen in all degree subjects but is found both in some Arts and in some Science subjects. We have used a questionnaire administered under supervision to undergraduates 2 to 3 months before their final examination to assess factors which might be expected to affect examination performance. These included measures of verbal and non-verbal reasoning (Alice Heim AH6 test), self-esteem, motivation, responses to stresses of examinations and of personal relationships, happiness, risk-taking and working patterns. We have also obtained a detailed breakdown of the marks the students were given in the examination. Women scored higher on negative emotions while men scored higher on self-esteem, their perception of their own academic efficacy and on risk-taking strategies, but none of these factors predicted outcome. Verbal reasoning ability did predict outcome but there was no gender difference. Hence, it is concluded that the gender gap is not due to any of these individual differences and is more likely to be related to the nature of the academic assessment system.

  13. Hipparcos to deliver its final results catalogue soon

    Science.gov (United States)

    1995-10-01

    perspective, when the results are delivered to them at the end of March 1996. The final product of the Hipparcos mission, a monumental 14-volume catalogue, with page upon page of astronomical results of unprecedented accuracy, will be published by ESA and the scientific teams at the end of March 1997. The four leaders of he European scientific teams, who have been involved in the project since its earliest days, announced hat he Hipparcos and Tycho Catalogues have passed all he test that they have been able to devise to assess he quality of he data. Professor Jean Kovalevsky (Observatoire de la Cote d'Azur, Grasse, France), Dr Lennart Lindegren (Lund Observatory, Sweden), Professor Erik Hog (Copenhagen Observatory, Denmark), and Dr Catherine Turon (Observatoire de Paris-Meudon), and other scientific representatives from the ESA member states, are delighted with he latest developments. "There will be thousands of direct and indirect users of the Hipparcos results over the coming years", said Catherine Turon who lead the team responsible for putting together the satellite's observing programme, "and they will not only have access to a magnificent catalogue, but one which has been finalised somewhat more rapidly than our expectations before launch ". Some ten thousand known double star systems have been observed by Hipparcos, and nearly ten thousand more have been discovered for the first time. In these binary systems, two stars orbit around each other, and Hipparcos promises to provide measurements of the masses of he stars in such systems, information which is impossible to determine in any other way. "Many of our scientific colleagues who have waited patiently for the results of this mission will be astonished with what the final catalogue contains" said Professor Hog, originator of he Tycho Catalogue concept, and one of the hiving forces behind the mission. In thousands of cases, the stars are seen to be variable by Hipparcos. In these cases, the light output from he star

  14. Finite Element Analysis and Test Results Comparison for the Hybrid Wing Body Center Section Test Article

    Science.gov (United States)

    Przekop, Adam; Jegley, Dawn C.; Rouse, Marshall; Lovejoy, Andrew E.

    2016-01-01

    This report documents the comparison of test measurements and predictive finite element analysis results for a hybrid wing body center section test article. The testing and analysis efforts were part of the Airframe Technology subproject within the NASA Environmentally Responsible Aviation project. Test results include full field displacement measurements obtained from digital image correlation systems and discrete strain measurements obtained using both unidirectional and rosette resistive gauges. Most significant results are presented for the critical five load cases exercised during the test. Final test to failure after inflicting severe damage to the test article is also documented. Overall, good comparison between predicted and actual behavior of the test article is found.

  15. Review of tolerances at the Final Focus Test Beam

    International Nuclear Information System (INIS)

    Bulos, F.; Burke, D.; Helm, R.; Irwin, J.; Roy, G.; Yamamoto, N.

    1991-01-01

    The authors review the tolerances associated with the Final Focus Test Beam (FFTB). The authors have computed the acceptability window of the input beam for orbit jitter, emittance beta functions mismatch, incoming dispersion and coupling; tolerances on magnet alignment, strength and multipole content; and the initial tuneability capture of the line

  16. Review of tolerances at the Final Focus Test Beam

    International Nuclear Information System (INIS)

    Bulos, F.; Burke, D.; Helm, R.; Irwin, J.; Roy, G.; Yamamoto, N.

    1991-05-01

    We review the tolerances associated with the Final Focus Test Beam (FFTB). We have computed the acceptability window of the input beam for orbit jitter, emittance beta functions mismatch, incoming dispersion and coupling; tolerances on magnet alignment, strength and multipole content; and the initial tuneability capture of the line. 2 refs., 1 fig

  17. Modeling Results For the ITER Cryogenic Fore Pump. Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Pfotenhauer, John M. [University of Wisconsin, Madison, WI (United States); Zhang, Dongsheng [University of Wisconsin, Madison, WI (United States)

    2014-03-31

    A numerical model characterizing the operation of a cryogenic fore-pump (CFP) for ITER has been developed at the University of Wisconsin – Madison during the period from March 15, 2011 through June 30, 2014. The purpose of the ITER-CFP is to separate hydrogen isotopes from helium gas, both making up the exhaust components from the ITER reactor. The model explicitly determines the amount of hydrogen that is captured by the supercritical-helium-cooled pump as a function of the inlet temperature of the supercritical helium, its flow rate, and the inlet conditions of the hydrogen gas flow. Furthermore the model computes the location and amount of hydrogen captured in the pump as a function of time. Throughout the model’s development, and as a calibration check for its results, it has been extensively compared with the measurements of a CFP prototype tested at Oak Ridge National Lab. The results of the model demonstrate that the quantity of captured hydrogen is very sensitive to the inlet temperature of the helium coolant on the outside of the cryopump. Furthermore, the model can be utilized to refine those tests, and suggests methods that could be incorporated in the testing to enhance the usefulness of the measured data.

  18. Results of steel containment vessel model test

    International Nuclear Information System (INIS)

    Luk, V.K.; Ludwigsen, J.S.; Hessheimer, M.F.; Komine, Kuniaki; Matsumoto, Tomoyuki; Costello, J.F.

    1998-05-01

    A series of static overpressurization tests of scale models of nuclear containment structures is being conducted by Sandia National Laboratories for the Nuclear Power Engineering Corporation of Japan and the US Nuclear Regulatory Commission. Two tests are being conducted: (1) a test of a model of a steel containment vessel (SCV) and (2) a test of a model of a prestressed concrete containment vessel (PCCV). This paper summarizes the conduct of the high pressure pneumatic test of the SCV model and the results of that test. Results of this test are summarized and are compared with pretest predictions performed by the sponsoring organizations and others who participated in a blind pretest prediction effort. Questions raised by this comparison are identified and plans for posttest analysis are discussed

  19. The PANDA facility and first test results

    International Nuclear Information System (INIS)

    Dreier, J.; Huggenberger, M.; Aubert, C.; Bandurski, T.; Fischer, O.; Healzer, J.; Lomperski, S.; Strassberger, H.J.; Varadi, G.; Yadigaroglu, G.

    1996-01-01

    The PANDA test facility at the Paul Scherrer Institute is used to study the long-term performance of the Simplified Boiling Water Reactor's passive containment cooling system. The PANDA tests demonstrate performance on a larger scale than previous tests and examine the effects of any non-uniform spatial distributions of steam and non-condensable gases in the system. The facility is in 1:1 vertical scale and 1:25 scale for volume, power etc. Extensive facility characterization tests and steady-state passive containment condenser performance tests are presented. The results of the base case test of a series of transient system behaviour tests are reviewed. The first PANDA tests exhibited reproducibility, and indicated that the Simplified Boiling Water Reactor's containment is likely to be favorably responsive and highly robust to changes in the thermal transport patterns. (orig.) [de

  20. Final Report on SSD2 pilot results in Denmark

    DEFF Research Database (Denmark)

    Andersen, Jens Hinge; Jørgensen, Kevin; Jensen, Louise Grønhøj Hørbye

    This document is the “Report on SSD2 pilot results” of the project OC/EFSA/DCM/2013/05: “Pilot project on the implementation of SSD2 in the frame of the electronic transmission of harmonised data collection of analytical results to EFSA”. The report includes a description of the software and tools...... used, a description of the challenges encountered in migrating data structure from SSD1/XML to SSD2 in the national data repositories, a summary of the experience gained in testing SSD2 and recommendations for EFSA on effectiveness and suitability of the SSD2 in the different domains. The following...

  1. Superconducting solenoid model magnet test results

    Energy Technology Data Exchange (ETDEWEB)

    Carcagno, R.; Dimarco, J.; Feher, S.; Ginsburg, C.M.; Hess, C.; Kashikhin, V.V.; Orris, D.F.; Pischalnikov, Y.; Sylvester, C.; Tartaglia, M.A.; Terechkine, I.; /Fermilab

    2006-08-01

    Superconducting solenoid magnets suitable for the room temperature front end of the Fermilab High Intensity Neutrino Source (formerly known as Proton Driver), an 8 GeV superconducting H- linac, have been designed and fabricated at Fermilab, and tested in the Fermilab Magnet Test Facility. We report here results of studies on the first model magnets in this program, including the mechanical properties during fabrication and testing in liquid helium at 4.2 K, quench performance, and magnetic field measurements. We also describe new test facility systems and instrumentation that have been developed to accomplish these tests.

  2. Superconducting solenoid model magnet test results

    International Nuclear Information System (INIS)

    Carcagno, R.; Dimarco, J.; Feher, S.; Ginsburg, C.M.; Hess, C.; Kashikhin, V.V.; Orris, D.F.; Pischalnikov, Y.; Sylvester, C.; Tartaglia, M.A.; Terechkine, I.; Tompkins, J.C.; Wokas, T.; Fermilab

    2006-01-01

    Superconducting solenoid magnets suitable for the room temperature front end of the Fermilab High Intensity Neutrino Source (formerly known as Proton Driver), an 8 GeV superconducting H- linac, have been designed and fabricated at Fermilab, and tested in the Fermilab Magnet Test Facility. We report here results of studies on the first model magnets in this program, including the mechanical properties during fabrication and testing in liquid helium at 4.2 K, quench performance, and magnetic field measurements. We also describe new test facility systems and instrumentation that have been developed to accomplish these tests

  3. Alternative filtration testing program: Pre-evaluation of test results

    International Nuclear Information System (INIS)

    Georgeton, G.K.; Poirier, M.R.

    1990-01-01

    Based on results of testing eight solids removal technologies and one pretreatment option, it is recommended that a centrifugal ultrafilter and polymeric ultrafilter undergo further testing as possible alternatives to the Norton Ceramic filters. Deep bed filtration should be considered as a third alternative, if a backwashable cartridge filter is shown to be inefficient in separate testing

  4. Alternative filtration testing program: Pre-evaluation of test results

    Energy Technology Data Exchange (ETDEWEB)

    Georgeton, G.K.; Poirier, M.R.

    1990-09-28

    Based on results of testing eight solids removal technologies and one pretreatment option, it is recommended that a centrifugal ultrafilter and polymeric ultrafilter undergo further testing as possible alternatives to the Norton Ceramic filters. Deep bed filtration should be considered as a third alternative, if a backwashable cartridge filter is shown to be inefficient in separate testing.

  5. Test results of HTTR control system

    International Nuclear Information System (INIS)

    Motegi, Toshihiro; Iigaki, Kazuhiko; Saito, Kenji; Sawahata, Hiroaki; Hirato, Yoji; Kondo, Makoto; Shibutani, Hideki; Ogawa, Satoru; Shinozaki, Masayuki; Mizushima, Toshihiko; Kawasaki, Kozo

    2006-06-01

    The plant control performance of the IHX helium flow rate control system, the PPWC helium flow rate control system, the secondary helium flow rate control system, the inlet temperature control system, the reactor power control system and the outlet temperature control system of the HTTR are obtained through function tests and power-up tests. As the test results, the control systems show stable control response under transient condition. Both of inlet temperature control system and reactor power control system shows stable operation from 30% to 100%, respectively. This report describes the outline of control systems and test results. (author)

  6. 78 FR 69817 - Polyethylene Retail Carrier Bags From Thailand: Final Court Decision and Amended Final Results of...

    Science.gov (United States)

    2013-11-21

    ... Bags From Thailand: Final Court Decision and Amended Final Results of Administrative Review of the..., which recalculated the weighted-average duty margin for polyethylene retail carrier bags (PRCBs) from... Packaging at the CIT. \\2\\ See Polyethylene Retail Carrier Bags from Thailand: Final Results and Partial...

  7. BWR Full Integral Simulation Test (FIST). Phase I test results

    International Nuclear Information System (INIS)

    Hwang, W.S.; Alamgir, M.; Sutherland, W.A.

    1984-09-01

    A new full height BWR system simulator has been built under the Full-Integral-Simulation-Test (FIST) program to investigate the system responses to various transients. The test program consists of two test phases. This report provides a summary, discussions, highlights and conclusions of the FIST Phase I tests. Eight matrix tests were conducted in the FIST Phase I. These tests have investigated the large break, small break and steamline break LOCA's, as well as natural circulation and power transients. Results and governing phenomena of each test have been evaluated and discussed in detail in this report. One of the FIST program objectives is to assess the TRAC code by comparisons with test data. Two pretest predictions made with TRACB02 are presented and compared with test data in this report

  8. Integrated leak rate test results of JOYO reactor containment vessel

    International Nuclear Information System (INIS)

    Tamura, M.; Endo, J.

    1982-02-01

    Integrated leak rate tests of JOYO after the reactor coolant system had been filled with sodium have been performed two times since 1978 (February 1978 and December 1979). The tests were conducted with the in-containment sodium systems, primary argon cover gas system and air conditioning systems operating. Both the absolute pressure method and the reference chamber method were employed during the test. The results of both tests confirmed the functioning of the containment vessel, and leak rate limits were satisfied. In Addition, the adequancy of the test instrumentation system and the test method was demonstrated. Finally the plant conditions required to maintain reasonable accuracy for the leak rate testing of LMFBR were established. In this paper, the test conditions and the test results are described. (author)

  9. SULTAN test facility: Summary of recent results

    International Nuclear Information System (INIS)

    Stepanov, Boris; Bruzzone, Pierluigi; Sedlak, Kamil; Croari, Giancarlo

    2013-01-01

    The test campaigns of the ITER conductors in the SULTAN test facility re-started in December 2011 after three months break. The main focus of the activities is about the qualification tests of the Central Solenoid (CS) conductors, with three different samples for a total six variations of strand suppliers and cable layouts. In 2012, five Toroidal Field (TF) conductor samples have also been tested as part of the supplier and process qualification phase of the European, Korean, Chinese and Russian Federation Agencies. A summary of the test results for all the ITER samples tested in the last period is presented, including an updated statistics of the broad transition, the performance degradation and the impact of layout variations. The role of SULTAN test facility during the ITER construction is reviewed, and the load of work for the next three years is anticipated

  10. Production LHC HTS power lead test results

    CERN Document Server

    Tartaglia, M; Fehér, S; Huang, Y; Orris, D F; Pischalnikov, Y; Rabehl, Roger Jon; Sylvester, C D; Zbasnik, J

    2005-01-01

    The Fermilab Magnet test facility has built and operated a test stand to characterize the performance of HTS power leads. We report here the results of production tests of 20 pairs of 7.5 kA HTS power leads manufactured by industry for installation in feed boxes for the LHC Interaction Region quadrupole strings. Included are discussions of the thermal, electrical, and quench characteristics under "standard" and "extreme" operating conditions, and the stability of performance across thermal cycles.

  11. Production LHC HTS power lead test results

    International Nuclear Information System (INIS)

    Tartaglia, M.A.; Carcagno, R.H.; Feher, S.; Huang, Y.; Orris, D.F.; Pischalnikov, Y.; Rabehl, R.J.; Sylvester, C.; Zbasnik, J.

    2004-01-01

    The Fermilab Magnet test facility has built and operated a test stand to characterize the performance of HTS power leads. We report here the results of production tests of 20 pairs of 7.5 kA HTS power leads manufactured by industry for installation in feed boxes for the LHC Interaction Region quadrupole strings. Included are discussions of the thermal, electrical, and quench characteristics under ''standard'' and ''extreme'' operating conditions, and the stability of performance across thermal cycles

  12. Final design and performance of in situ testing in Grimsel

    International Nuclear Information System (INIS)

    Fuentes-Cantillana, J.L.; Garcia-SiNeriz, J.L.

    1998-01-01

    This report is focused on the design, engineering, and construction aspects of the in situ test carried out at the Grimsel underground laboratory in Switzerland. This reproduces the AGP-granite concept of ENRESA for HLW repositories in crystalline rock. Two heaters, similar in dimensions and weight to the canisters in the reference concept, have been placed in a horizontal drift with a 2.28-m diameter, a total test length of 17.4 m, and backfilled with a total of 115.7 † of highly-compacted bentonite blocks. The backfilled area has been closed with a concrete plug which is 2.7 m thick. More than 600 sensors have been installed in the test to monitor different parameters such as temperature, pressures, humidity, etc., within both the buffer material and the host rock. The installation was completed and commissioned in February 1997, and then the heating phase, which will last for at least 3 years, was started. During this period, the test will basically be operated in an automatic mode, controlled and monitored from Spain via modem. The report is the Final Report from AITEMIN for Phase 4 of the project and includes a description of the test configuration and layout; the design, engineering, and manufacturing aspects of the different test components and equipment; the emplacement operation; and the as built information regarding the final position of the main components and the sensors. (Author)

  13. The optics of the Final Focus Test Beam

    International Nuclear Information System (INIS)

    Irwin, J.; Brown, K.; Bulos, F.; Burke, D.; Helm, R.; Roy, G.; Ruth, R.; Yamamoto, N.; Oide, K.

    1991-05-01

    The Final Focus Test Beam (FFTB), currently under construction at the end of the SLAC Linac, is being built by an international collaboration as a test bed for ideas and methods required in the design and construction of final focus systems for next generation e + e - linear colliders. The FFTB lattice is based on the previously developed principle of using sextupole pairs in a dispersive region to compensate chromaticity. The linear lattice was optimized for length, and implementation of diagnostic procedures. The transformations between sextupole pairs (CCX and CCY) are exactly -I, the matrix for the intermediate transformer (BX) is exactly diagonal, and the dispersion function has zero slope at the sextupoles and is thus zero at the minimum of the β x function in the intermediate transformer. The introduction of sextupoles in final focus systems leads to the presence of additional optical aberrations, and synchrotron radiation in the dipoles also enlarges the final spot size. The important fourth-order optical aberrations which determine the main features of the design have been identified. Additional lower order aberrations arise in the implementation of these designs, since the real system is not the ideal design. We concentrate on these aberrations and describe strategies for their diagnosis and correction

  14. Final design of ITER port plug test facility

    Energy Technology Data Exchange (ETDEWEB)

    Cerisier, Thierry, E-mail: thierry.cerisier@yahoo.fr [ITER Organization, Route de Vinon-sur-Verdon, CS 90046, St Paul-lez-Durance Cedex, 13067 (France); Levesy, Bruno [ITER Organization, Route de Vinon-sur-Verdon, CS 90046, St Paul-lez-Durance Cedex, 13067 (France); Romannikov, Alexander [Institution “Project Center ITER”, Kurchatov sq. 1, Building 3, Moscow 123182 (Russian Federation); Rumyantsev, Yuri [JSC “Cryogenmash”, Moscow reg., Balashikha 143907 (Russian Federation); Cordier, Jean-Jacques; Dammann, Alexis [ITER Organization, Route de Vinon-sur-Verdon, CS 90046, St Paul-lez-Durance Cedex, 13067 (France); Minakov, Victor; Rosales, Natalya; Mitrofanova, Elena [JSC “Cryogenmash”, Moscow reg., Balashikha 143907 (Russian Federation); Portone, Sergey; Mironova, Ekaterina [Institution “Project Center ITER”, Kurchatov sq. 1, Building 3, Moscow 123182 (Russian Federation)

    2016-11-01

    Highlights: • We introduce the port plug test facility (purpose and status of the design). • We present the PPTF sub-systems. • We present the environmental and functional tests. • We present the occupational and nuclear safety functions. • We conclude on the achievements and next steps. - Abstract: To achieve the overall ITER machine availability target, the availability of diagnostics and heating port plugs shall be as high as 99.5%. To fulfill this requirement, it is mandatory to test the port plugs at operating temperature before installation on the machine and after refurbishment. The ITER port plug test facility (PPTF) is composed of several test stands that can be used to test the port plugs whereas at the end of manufacturing (in a non-nuclear environment), or after refurbishment in the ITER hot cell facility. The PPTF provides the possibility to perform environmental (leak tightness, vacuum and thermo-hydraulic performances) and functional tests (radio frequency acceptance tests, behavior of the plugs’ steering mechanism and calibration of diagnostics) on upper and equatorial port plugs. The final design of the port plug test facility is described. The configuration of the standalone test stands and the integration in the hot cell facility are presented.

  15. The optics of the Final Focus Test Beam

    International Nuclear Information System (INIS)

    Irwin, J.; Brown, K.; Bulos, F.; Burke, D.; Helm, R.; Roy, G.; Ruth, R.; Yamamoto, N.; Oide, K.

    1991-01-01

    The Final Focus Test Beam (FFTB), currently under construction at the end of the SLAC Linac, is being built by an international collaboration as a test bed for ideas and methods required in the design and construction of final focus systems for next generation e + e - linear colliders. The FFTB lattice shown is based on the previously developed principle of using sextupole pairs in a dispersive region to compensate chromaticity. The linear lattice was optimized for length, and implementation of diagnostic procedures. The transformations between sextupole pairs (CCX and CCY) are exactly -I, the matrix for the intermediate transformer (BX) is exactly diagonal, and the dispersion function has zero slope at the sextupoles and is thus zero at the minimum of the β x function in the intermediate transformer

  16. Plasma lenses for SLAC Final Focus Test facility

    International Nuclear Information System (INIS)

    Betz, D.; Cline, D.; Joshi, C.; Rajagopalan, S.; Rosenzweig, J.; Su, J.J.; Williams, R.; Chen, P.; Gundersen, M.; Katsouleas, T.; Norem, J.

    1991-01-01

    A collaborative group of accelerator and plasma physicists and engineers has formed with an interest in exploring the use of plasma lenses to meet the needs of future colliders. Analytic and computational models of plasma lenses are briefly reviewed and several design examples for the SLAC Final Focus Test Beam are presented. The examples include discrete, thick, and adiabatic lenses. A potential plasma source with desirable lens characteristics is presented

  17. Development of Final Running Test System for Digital Systems

    International Nuclear Information System (INIS)

    Lee, Kwang-Dae; Lee, Eui-Jong; Lim, Hee-Taek; Kim, Min-Seok

    2016-01-01

    In nuclear industry, the newly designed systems to upgrade are qualified to meet IEEE standards and the regulatory guidelines for their functions, performance and reliability requirements. Failure Mode and Effect Analysis, Fault Tree Analysis, and Hazard Analysis have been used to improve the reliability of the control system. To ensure the completeness of the software, the verification and validation processes are carried out during the development process. In spite of the many efforts depending on the analysis and procedures, there are limitations to improve the reliability. The lessons learned from the currently installed system failures show the incompleteness of the final integration test. The current point-to-point and logic-to-logic separate test procedures manually performed by the engineers can cause some procedures missed and have effects on the critical functions. The design processes of the digital systems are met in accordance with the international standards and regulatory guidelines. The lessons learned from the failures of the running digital systems showed the limitations of the current verification and validation efforts. The various improvements and attempts have been considered including the expert review processes and the completeness of the test. In this paper, the Final Running Test Method evaluating the completeness of the digital system using the control patterns and the Test System Architecture are proposed

  18. Development of Final Running Test System for Digital Systems

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kwang-Dae; Lee, Eui-Jong; Lim, Hee-Taek; Kim, Min-Seok [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    In nuclear industry, the newly designed systems to upgrade are qualified to meet IEEE standards and the regulatory guidelines for their functions, performance and reliability requirements. Failure Mode and Effect Analysis, Fault Tree Analysis, and Hazard Analysis have been used to improve the reliability of the control system. To ensure the completeness of the software, the verification and validation processes are carried out during the development process. In spite of the many efforts depending on the analysis and procedures, there are limitations to improve the reliability. The lessons learned from the currently installed system failures show the incompleteness of the final integration test. The current point-to-point and logic-to-logic separate test procedures manually performed by the engineers can cause some procedures missed and have effects on the critical functions. The design processes of the digital systems are met in accordance with the international standards and regulatory guidelines. The lessons learned from the failures of the running digital systems showed the limitations of the current verification and validation efforts. The various improvements and attempts have been considered including the expert review processes and the completeness of the test. In this paper, the Final Running Test Method evaluating the completeness of the digital system using the control patterns and the Test System Architecture are proposed.

  19. International Standard problem ISP 14: behaviour of a fuel bundle simulator during a specified heatup and flooding period (Rebeka experiment): results of post-test analyses: final comparison report

    International Nuclear Information System (INIS)

    Karwat, H.

    1985-02-01

    The test consisted in investigating the non-steady material behaviour of a bundle of electrically heated fuel rod simulators with respect to local fuel temperatures, cladding strain, time to burst and local strain at location of burst, together with the thermal hydraulic boundary conditions. The original aim has not been fully achievable. The applied codes for mechanical fuel behaviour largely demonstrated their capabilities for pretest predictions when certain local fluid dynamic parameters are well known to the code users. The difficulties expected with proper analysis of thermal hydraulics of the test were confirmed, caused by the coupling between pin cooling conditions, rod upper plenum calculations and the feedback to clad deformation and burst simulation

  20. Test Beam Results Obtained with the Q4 Prototype

    Energy Technology Data Exchange (ETDEWEB)

    Aguilar-Benitez, M.; Alberdi, J.; Cerrada, M.; Colino, N.; Daniel, M.; Fouz, M. c.; Marin, J.; Mocholi, J.; Oller, J. C.; Puerta, J.; Romero, L.; Salicio, J. M.

    2000-07-01

    A prototype of the CMS Barrel Muon Detector incorporating all the features of the final chambers was built at CIEMAT using the mass production assembly procedures and tools. The performance of this prototype was studied in a muon test beam at CERN and the results obtained are presented here. (Author)

  1. Test beam results obtained with the Q4 prototype

    International Nuclear Information System (INIS)

    Aguilar-Benitez, M.; Alberdi, J.; Cerrada, M.; Colino, N.; Daniel, M.; Fouz, M.C.; Marin, J.; Mocholi, J.; Oller, J. C.; Puerta, J.; Romero, L.; Salicio, J. M.; Willmott, C.

    2000-10-01

    A prototype of the CMS Barrel Muon Detector incorporating all the features of the final chambers was built at CIEMAT using the mass production assembly procedures and tools. The performance of this prototype was studied in a muon test beam at CERN and the results obtained are presented here. (Author)

  2. Reproducibility of the results in nondestructive testing

    International Nuclear Information System (INIS)

    Launay, J.P.; Chalaye, H.; Thomas, A.

    1980-10-01

    Pressure vessels must comply with very severe safety criteria. In order to ensure that the required quality is attained, non destructive tests are used and these have to be highly reliable: magnetoscopy and liquid penetration for surface examinations, radiography and ultrasonics for voluminal examinations. In the case of ultrasonic examinations, a study of parameters has been made and a statistical analysis of the results has made it possible to calculate the dispersion due to the testing equipment [fr

  3. Acknowledging the results of blood tests

    DEFF Research Database (Denmark)

    Torkilsheyggi, Arnvør Martinsdottir á; Hertzum, Morten

    At the studied hospital, physicians from the Medical and Surgical Departments work some of their shifts in the Emergency Department (ED). Though icons showing the blood-test process were introduced on electronic whiteboards in the ED, these icons did not lead to increased attention to test acknow...... acknowledgement. Rather, the physicians, trans-ferred work practices from their own departments, which did not have electronic white-boards, to the ED. This finding suggests a challenge to the cross-disciplinary work and norms for how to follow up on blood-test results in the ED....

  4. KNK I Test Program, Final Report Part 1

    International Nuclear Information System (INIS)

    Kathol, W.

    1976-01-01

    The compact sodium cooled nuclear reactor KNK I of the Karlsruhe Research Center reached full power for the first time in February 1974. The goal of KNK I is to collect experience for the construction and operation of larger reactors, such as SNR 300. In order to deepen these experiences, a test program was drawn up and conducted from 1973 until 1975 within the framework of R and D work on the development of fast breeder reactors. The program included individual tasks concerning reactor design, safety instrumentation, irradiation and post-examination as well as behavior of components during operation. The performance of the tests was essentially governed by the licensing procedure imposed under the atomic energy act for the construction and operation of nuclear facilities. This report is the first part of the final report of the test program

  5. Results of interlaboratory tests regarding TXRF

    International Nuclear Information System (INIS)

    Klockenkaemper, R.; Bohlen, A. von

    2000-01-01

    Interlaboratory or intercomparison tests can be performed for proficiency testing of individual laboratories, for the certification of a special sample material and for the validation of a certain method. We participated in two interlaboratory tests in order to validate total reflection x-ray fluorescence analysis (TXRF). We used our results to evaluate TXRF and to compare it with other competing methods, particularly with respect of precision and accuracy. The first interlaboratory test was organized by IAEA (International Atomic Energy Agency, Vienna, Austria). As a candidate for reference material, a lichen (IAEA-336 Lichen) was distributed among 27 participants. In our laboratory, the powdered biogenic material was digested with nitric acid under high pressure and analyzed by TXRF. - The second interlaboratory test was organized by IRMM (Institute for Reference Materials and Measurements, Geel, Belgium). As a certified test sample with undisclosed values, a sediment (IMEP-14) was delivered to 220 laboratories. We digested the geogenic material again by nitric acid and additionally by hydrofluoric acid and analyzed it by TXRF. - In both test samples, six or eight different trace elements, respectively, were determined by TXRF with a content between 2 and 2000 mg/kg. Calibration was carried out by internal standardization. For that purpose, Ga or Se, respectively, was added as standard element. The measurement uncertainty of TXRF was estimated by the method of error propagation. In our paper we will report on the results of the two interlaboratory tests. It will be shown that TXRF is highly reliable for a correct determination of trace elements in biogenic and geogenic samples. It is competitive with the established methods of trace analyses which were involved in these tests and it is even superior to them in certain aspects. (author)

  6. Test Results of PBMR Fuel Spheres

    International Nuclear Information System (INIS)

    Koshcheev, Konstantin; Diakov, Alexander; Beltyukov, Igor; Barybin, Andrey; Chernetsov, Mikhail

    2014-01-01

    Results of pre-irradiation testing of fuel spheres (FS) and coated particles (CP) manufactured by PBMR SOC (Republic of South Africa) are described. The stable high quality level of major characteristics (dimensions, CP coating structure, uranium-235 contamination of the FS matrix graphite and the outer PyC layer of the CP coating) are shown. Results of a methodical irradiation test of two FS in helium and neon medium at temperatures of 800 to 1300 °C with simultaneous determination of release-to-birth ratios for major gaseous fission products (GFP) are described. (author)

  7. Cascade Distiller System Performance Testing Interim Results

    Science.gov (United States)

    Callahan, Michael R.; Pensinger, Stuart; Sargusingh, Miriam J.

    2014-01-01

    The Cascade Distillation System (CDS) is a rotary distillation system with potential for greater reliability and lower energy costs than existing distillation systems. Based upon the results of the 2009 distillation comparison test (DCT) and recommendations of the expert panel, the Advanced Exploration Systems (AES) Water Recovery Project (WRP) project advanced the technology by increasing reliability of the system through redesign of bearing assemblies and improved rotor dynamics. In addition, the project improved the CDS power efficiency by optimizing the thermoelectric heat pump (TeHP) and heat exchanger design. Testing at the NASA-JSC Advanced Exploration System Water Laboratory (AES Water Lab) using a prototype Cascade Distillation Subsystem (CDS) wastewater processor (Honeywell d International, Torrance, Calif.) with test support equipment and control system developed by Johnson Space Center was performed to evaluate performance of the system with the upgrades as compared to previous system performance. The system was challenged with Solution 1 from the NASA Exploration Life Support (ELS) distillation comparison testing performed in 2009. Solution 1 consisted of a mixed stream containing human-generated urine and humidity condensate. A secondary objective of this testing is to evaluate the performance of the CDS as compared to the state of the art Distillation Assembly (DA) used in the ISS Urine Processor Assembly (UPA). This was done by challenging the system with ISS analog waste streams. This paper details the results of the AES WRP CDS performance testing.

  8. Final Physics Report for the Engineering Test Reactor

    International Nuclear Information System (INIS)

    Wolfe, I. B.

    1956-01-01

    order to reduce as much as possible the cost of the physics analysis and in order to obtain information otherwise unavailable, considerable use was made of perturbation techniques. These perturbation computations were initially performed using the one-dimensional approximation and were extended to two dimensions in stages 3 and 4. To do this a method of obtaining adjoint fluxes; using available reactor computer codes, was developed. Only the physics which bears on the final design of the ETR is summarized. This volume, together with the Physics Progress Report, represents a complete account of the studies undertaken,. methods used, and results obtained in the physics work on the ETR

  9. A Dynamic Alignment System for the Final Focus Test Beam

    International Nuclear Information System (INIS)

    Ruland, R.E.; Bressler, V.E.; Fischer, G.; Plouffe, D.; SLAC

    2005-01-01

    The Final Focus Test Beam (FFTB) was conceived as a technological stepping stone on the way to the next linear collider. Nowhere is this more evident than with the alignment subsystems. Alignment tolerances for components prior to beam turn are almost an order of magnitude smaller than for previous projects at SLAC. Position monitoring systems which operate independent of the beam are employed to monitor motions of the components locally and globally with unprecedented precision. An overview of the FFTB alignment system is presented herein

  10. ALICE TRD results from prototype tests

    CERN Document Server

    Andronic, A; Blume, C; Braun-Munzinger, P; Bucher, D; Catanescu, G; Ciobanu, M; Daues, H W; Devismes, A; Finck, C; Herrmann, N; Lister, T A; Mahmoud, Tariq; Peitzmann, Thomas; Petrovici, M; Reygers, K; Santo, R; Schicker, R; Sedykha, S; Simon, R S; Stachel, J; Stelzer, H; Wessels, J P; Winkelmann, O; Windelband, B; Xu, C

    2002-01-01

    We present results from tests of a prototype of the TRD for the ALICE experiment at LHC. We investigate the performance-of different radiator types, composed of foils, fibres and foams. The pion rejection performance for different methods of analysis over a momentum range from 0.7 to 2 GeV/c is presented. (8 refs).

  11. SLD liquid argon calorimeter prototype test results

    International Nuclear Information System (INIS)

    Dubois, R.; Eigen, G.; Au, Y.

    1985-10-01

    The results of the SLD test beam program for the selection of a calorimeter radiator composition within a liquid argon system are described, with emphasis on the study of the use of uranium to obtain equalization of pion and electron responses

  12. Cone Penetrometer N Factor Determination Testing Results

    Energy Technology Data Exchange (ETDEWEB)

    Follett, Jordan R.

    2014-03-05

    This document contains the results of testing activities to determine the empirical 'N Factor' for the cone penetrometer in kaolin clay simulant. The N Factor is used to releate resistance measurements taken with the cone penetrometer to shear strength.

  13. Ball Aerospace SBMD Coating Test Results

    Science.gov (United States)

    Brown, Robert; Lightsey, Paul; Russell, J. Kevin (Technical Monitor)

    2002-01-01

    The Sub-scale Beryllium Mirror Demonstrator that was successfully tested to demonstrate cryogenic figuring of a bare mirror has been coated with a protected gold reflective surface and retested at cryogenic temperatures. Results showing less than 9 nm rms surface distortion attributable to the added coating are presented.

  14. Experimental results with boosted top quarks in the final state

    CERN Document Server

    Erdmann, Johannes

    2014-01-01

    An overview of analyses using data at sqrt(s) = 7 TeV and 8 TeV of proton-proton collisions at the LHC is presented. These analyses use boosted techniques to search for new phenomena involving top quarks and to measure the production of top quarks at high transverse momenta. Such techniques involve top-quark tagging algorithms, boson-tagging algorithms, and strategies for b-tagging and lepton identification in the environment where the top quark decay products are close to each other. The strategies are optimized for the different final states and for different ranges of the transverse momenta of the particles involved, improving on traditional resolved analysis strategies.

  15. In-vessel Retention Strategy for High Power Reactors - K-INERI Final Report (includes SBLB Test Results for Task 3 on External Reactor Vessel Cooling (ERVC) Boiling Data and CHF Enhancement Correlations)

    Energy Technology Data Exchange (ETDEWEB)

    F. B. Cheung; J. Yang; M. B. Dizon; J. Rempe

    2005-01-01

    In-vessel retention (IVR) of core melt is a key severe accident management strategy adopted by some operating nuclear power plants and proposed for some advanced light water reactors (ALWRs). If there were inadequate cooling during a reactor accident, a significant amount of core material could become molten and relocate to the lower head of the reactor vessel, as happened in the Three Mile Island Unit 2 (TMI-2) accident. If it is possible to ensure that the vessel head remains intact so that relocated core materials are retained within the vessel, the enhanced safety associated with these plants can reduce concerns about containment failure and associated risk. For example, the enhanced safety of the Westinghouse Advanced 600 MWe PWR (AP600), which relied upon External Reactor Vessel Cooling (ERVC) for IVR, resulted in the U.S. Nuclear Regulatory Commission (US NRC) approving the design without requiring certain conventional features common to existing LWRs. However, it is not clear that currently proposed external reactor vessel cooling (ERVC) without additional enhancements could provide sufficient heat removal for higher-power reactors (up to 1500 MWe). Hence, a collaborative, three-year, U.S. - Korean International Nuclear Energy Research Initiative (INERI) project was completed in which the Idaho National Engineering and Environmental Laboratory (INEEL), Seoul National University (SNU), Pennsylvania State University (PSU), and the Korea Atomic Energy Research Institute (KAERI) investigated the performance of ERVC and an in-vessel core catcher (IVCC) to determine if IVR is feasible for reactors up to 1500 MWe.

  16. AMORE Mo-99 Spike Test Results

    Energy Technology Data Exchange (ETDEWEB)

    Youker, Amanda J. [Argonne National Lab. (ANL), Argonne, IL (United States); Krebs, John F. [Argonne National Lab. (ANL), Argonne, IL (United States); Quigley, Kevin J. [Argonne National Lab. (ANL), Argonne, IL (United States); Byrnes, James P. [Argonne National Lab. (ANL), Argonne, IL (United States); Rotsch, David A [Argonne National Lab. (ANL), Argonne, IL (United States); Brossard, Thomas [Argonne National Lab. (ANL), Argonne, IL (United States); Wesolowski, Kenneth [Argonne National Lab. (ANL), Argonne, IL (United States); Alford, Kurt [Argonne National Lab. (ANL), Argonne, IL (United States); Chemerisov, Sergey [Argonne National Lab. (ANL), Argonne, IL (United States); Vandegrift, George F. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2017-09-27

    With funding from the National Nuclear Security Administrations Material Management and Minimization Office, Argonne National Laboratory (Argonne) is providing technical assistance to help accelerate the U.S. production of Mo-99 using a non-highly enriched uranium (non-HEU) source. A potential Mo-99 production pathway is by accelerator-initiated fissioning in a subcritical uranyl sulfate solution containing low enriched uranium (LEU). As part of the Argonne development effort, we are undertaking the AMORE (Argonne Molybdenum Research Experiment) project, which is essentially a pilot facility for all phases of Mo-99 production, recovery, and purification. Production of Mo-99 and other fission products in the subcritical target solution is initiated by putting an electron beam on a depleted uranium (DU) target; the fast neutrons produced in the DU target are thermalized and lead to fissioning of U-235. At the end of irradiation, Mo is recovered from the target solution and separated from uranium and most of the fission products by using a titania column. The Mo is stripped from the column with an alkaline solution. After acidification of the Mo product solution from the recovery column, the Mo is concentrated (and further purified) in a second titania column. The strip solution from the concentration column is then purified with the LEU Modified Cintichem process. A full description of the process can be found elsewhere [1–3]. The initial commissioning steps for the AMORE project include performing a Mo-99 spike test with pH 1 sulfuric acid in the target vessel without a beam on the target to demonstrate the initial Mo separation-and-recovery process, followed by the concentration column process. All glovebox operations were tested with cold solutions prior to performing the Mo-99 spike tests. Two Mo-99 spike tests with pH 1 sulfuric acid have been performed to date. Figure 1 shows the flow diagram for the remotely operated Mo-recovery system for the AMORE project

  17. Laboratory results of the AOF system testing

    Science.gov (United States)

    Kolb, Johann; Madec, Pierre-Yves; Arsenault, Robin; Oberti, Sylvain; Paufique, Jérôme; La Penna, Paolo; Ströbele, Stefan; Donaldson, Robert; Soenke, Christian; Suárez Valles, Marcos; Kiekebusch, Mario; Argomedo, Javier; Le Louarn, Miska; Vernet, Elise; Haguenauer, Pierre; Duhoux, Philippe; Aller-Carpentier, Emmanuel; Valenzuela, Jose Javier; Guerra, Juan Carlos

    2016-07-01

    For two years starting in February 2014, the AO modules GRAAL for HAWK-I and GALACSI for MUSE of the Adaptive Optics Facility project have undergone System Testing at ESO's Headquarters. They offer four different modes: NGS SCAO, LGS GLAO in the IR, LGS GLAO and LTAO in the visible. A detailed characterization of those modes was made possible by the existence of ASSIST, a test bench emulating an adaptive VLT including the Deformable Secondary Mirror, a star simulator and turbulence generator and a VLT focal plane re-imager. This phase aimed at validating all the possible components and loops of the AO modules before installation at the actual VLT that comprises the added complexity of real LGSs, a harsher non-reproducible environment and the adaptive telescope control. In this paper we present some of the major results obtained and challenges encountered during the phase of System Tests, like the preparation of the Acquisition sequence, the testing of the Jitter loop, the performance optimization in GLAO and the offload of low-order modes from the DSM to the telescope (restricted to the M2 hexapod). The System Tests concluded with the successful acceptance, shipping, installation and first commissioning of GRAAL in 2015 as well as the acceptance and shipping of GALACSI, ready for installation and commissioning early 2017.

  18. arXiv Final results of the OPERA experiment on $\

    CERN Document Server

    Agafonova, N.; Anokhina, A.; Aoki, S.; Ariga, A.; Ariga, T.; Bertolin, A.; Bozza, C.; Brugnera, R.; Buonaura, A.; Buontempo, S.; Chernyavskiy, M.; Chukanov, A.; Consiglio, L.; D'Ambrosio, N.; De Lellis, G.; De Serio, M.; del Amo Sanchez, P.; Di Crescenzo, A.; Di Ferdinando, D.; Di Marco, N.; Dmitrievsky, S.; Dracos, M.; Duchesneau, D.; Dusini, S.; Dzhatdoev, T.; Ebert, J.; Ereditato, A.; Favier, J.; Fini, R.A.; Fornari, F.; Fukuda, T.; Galati, G.; Garfagnini, A.; Gentile, V.; Goldberg, J.; Gornushkin, Y.; Gorbunov, S.; Grella, G.; Guler, A.M.; Gustavino, C.; Hagner, C.; Hara, T.; Hayakawa, T.; Hollnagel, A.; Ishiguro, K.; Iuliano, A.; Jakovcic, K.; Jollet, C.; Kamiscioglu, C.; Kamiscioglu, M.; Kim, S.H.; Kitagawa, N.; Klicek, B.; Kodama, K.; Komatsu, M.; Kose, U.; Kreslo, I.; Laudisio, F.; Lauria, A.; Ljubicic, A.; Longhin, A.; Loverre, P.; Malgin, A.; Malenica, M.; Mandrioli, G.; Matsuo, T.; Matveev, V.; Mauri, N.; Medinaceli, E.; Meregaglia, A.; Mikado, S.; Miyanishi, M.; Mizutani, F.; Monacelli, P.; Montesi, M.C.; Morishima, K.; Muciaccia, M.T.; Naganawa, N.; Naka, T.; Nakamura, M.; Nakano, T.; Niwa, K.; Okateva, N.; Olchevsky, A.; Ogawa, S.; Ozaki, K.; Paoloni, A.; Paparella, L.; Park, B.D.; Pasqualini, L.; Pastore, A.; Patrizii, L.; Pessard, H.; Pistillo, C.; Podgrudkov, D.; Polukhina, N.; Pozzato, M.; Pupilli, F.; Roda, M.; Roganova, T.; Rokujo, H.; Rosa, G.; Ryazhskaya, O.; Sadovsky, A.; Sato, O.; Schembri, A.; Shakiryanova, I.; Shchedrina, T.; Shibuya, H.; Shibayama, E.; Shiraishi, T.; Simone, S.; Sirignano, C.; Sirri, G.; Sotnikov, A.; Spinetti, M.; Stanco, L.; Starkov, N.; Stellacci, S.M.; Stipcevic, M.; Strolin, P.; Takahashi, S.; Tenti, M.; Terranova, F.; Tioukov, V.; Tufanli, S.; Ustyuzhanin, A.; Vasina, S.; Vilain, P.; Voevodina, E.; Votano, L.; Vuilleumier, J.L.; Wilquet, G.; Wonsak, B.; Yoon, C.S.

    2018-05-23

    The OPERA experiment was designed to study νμ→ντ oscillations in the appearance mode in the CERN to Gran Sasso Neutrino beam (CNGS). In this Letter, we report the final analysis of the full data sample collected between 2008 and 2012, corresponding to 17.97×1019 protons on target. Selection criteria looser than in previous analyses have produced ten ντ candidate events, thus reducing the statistical uncertainty in the measurement of the oscillation parameters and of ντ properties. A multivariate approach for event identification has been applied to the candidate events and the discovery of ντ appearance is confirmed with an improved significance level of 6.1σ. |Δm322| has been measured, in appearance mode, with an accuracy of 20%. The measurement of the ντ charged-current cross section, for the first time with a negligible contamination from ν¯τ, and the first direct evidence for the ντ lepton number are also reported.

  19. Construction details and test results from RHIC sextupoles

    International Nuclear Information System (INIS)

    Lindner, M.; Anerella, M.; Ganetis, G.

    1993-01-01

    Four 8 cm aperture sextupoles have been built at BNL to verify the magnetic performance of this magnet in the RHIC installation. Two significantly different mechanical configurations have been designed, and two magnets of each design have been built, and successfully tested, and have exceeded the required minimum quench current by a substantial margin. This report describes the assembly details of the second configuration, which is the final production configuration. In addition the first industry built production sextupole has been delivered and tested. This report presents the results of quench tests on all 5 magnets and field measurements on the first production sextupole

  20. CAISI Operational Assessment (OA) data collection results. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-01-31

    One of the lessons learned from Operation Desert Shield/Storm was the inability of deployed Combat Service Support (CSS) computers to exchange data effectively in a battlefield environment. The work-around solution to this previously identified problem has been to physically carry floppy disks between computers. A General Officer Steering Committee, directed by the Vice Chief of Staff of the Army, determined that immediate corrective action was necessary to ensure viability of the CSS Battlefield Mission Area. The study recommended that a three-phased system development plan address short-, mid- and long-term CSS automation communication interface requirements. In response to this study, Program Executive Office (PEO) Standard Army Management Information System (STAMIS) authorized the development of the CSS Automated Information System Interface (CAISI). Phase I (Near-Term) equipped the {open_quotes}first to fight{close_quotes} Contingency Corps units. Phase II (Mid-Term) is being fielded to the remainder of Force Package One units in the active force. Phase III (Long-Term) will equip the remaining units. CAISI is now in the early stages of Phase II fielding. Prior to full Phase II fielding, CAISI must be approved for production by a Milestone III decision authority. Part of the data that will be used in the Milestone III decision is a demonstration of the CAISI`s operational suitability, as assessed by the US Army Operational Test and Evaluation Command (OPTEC). This assessment will be performed through an Operational Assessment (OA) using data provided from previous technical testing, such as the CAISI Customer User Test (CUT), and a field training exercise conducted by units of the XVIII Airborne Corps. The field training exercise data collection took place during two events.

  1. FINAL SIMULATION RESULTS FOR DEMONSTRATION CASE 1 AND 2

    Energy Technology Data Exchange (ETDEWEB)

    David Sloan; Woodrow Fiveland

    2003-10-15

    The goal of this DOE Vision-21 project work scope was to develop an integrated suite of software tools that could be used to simulate and visualize advanced plant concepts. Existing process simulation software did not meet the DOE's objective of ''virtual simulation'' which was needed to evaluate complex cycles. The overall intent of the DOE was to improve predictive tools for cycle analysis, and to improve the component models that are used in turn to simulate equipment in the cycle. Advanced component models are available; however, a generic coupling capability that would link the advanced component models to the cycle simulation software remained to be developed. In the current project, the coupling of the cycle analysis and cycle component simulation software was based on an existing suite of programs. The challenge was to develop a general-purpose software and communications link between the cycle analysis software Aspen Plus{reg_sign} (marketed by Aspen Technology, Inc.), and specialized component modeling packages, as exemplified by industrial proprietary codes (utilized by ALSTOM Power Inc.) and the FLUENT{reg_sign} computational fluid dynamics (CFD) code (provided by Fluent Inc). A software interface and controller, based on an open CAPE-OPEN standard, has been developed and extensively tested. Various test runs and demonstration cases have been utilized to confirm the viability and reliability of the software. ALSTOM Power was tasked with the responsibility to select and run two demonstration cases to test the software--(1) a conventional steam cycle (designated as Demonstration Case 1), and (2) a combined cycle test case (designated as Demonstration Case 2). Demonstration Case 1 is a 30 MWe coal-fired power plant for municipal electricity generation, while Demonstration Case 2 is a 270 MWe, natural gas-fired, combined cycle power plant. Sufficient data was available from the operation of both power plants to complete the cycle

  2. Structural fatigue test results for large wind turbine blade sections

    Science.gov (United States)

    Faddoul, J. R.; Sullivan, T. L.

    1982-01-01

    In order to provide quantitative information on the operating life capabilities of wind turbine rotor blade concepts for root-end load transfer, a series of cantilever beam fatigue tests was conducted. Fatigue tests were conducted on a laminated wood blade with bonded steel studs, a low cost steel spar (utility pole) with a welded flange, a utility pole with additional root-end thickness provided by a swaged collar, fiberglass spars with both bonded and nonbonded fittings, and, finally, an aluminum blade with a bolted steel fitting (Lockheed Mod-0 blade). Photographs, data, and conclusions for each of these tests are presented. In addition, the aluminum blade test results are compared to field failure information; these results provide evidence that the cantilever beam type of fatigue test is a satisfactory method for obtaining qualitative data on blade life expectancy and for identifying structurally underdesigned areas (hot spots).

  3. Boeing's STAR-FODB test results

    Science.gov (United States)

    Fritz, Martin E.; de la Chapelle, Michael; Van Ausdal, Arthur W.

    1995-05-01

    Boeing has successfully concluded a 2 1/2 year, two phase developmental contract for the STAR-Fiber Optic Data Bus (FODB) that is intended for future space-based applications. The first phase included system analysis, trade studies, behavior modeling, and architecture and protocal selection. During this phase we selected AS4074 Linear Token Passing Bus (LTPB) protocol operating at 200 Mbps, along with the passive, star-coupled fiber media. The second phase involved design, build, integration, and performance and environmental test of brassboard hardware. The resulting brassboard hardware successfully passed performance testing, providing 200 Mbps operation with a 32 X 32 star-coupled medium. This hardware is suitable for a spaceflight experiment to validate ground testing and analysis and to demonstrate performace in the intended environment. The fiber bus interface unit (FBIU) is a multichip module containing transceiver, protocol, and data formatting chips, buffer memory, and a station management controller. The FBIU has been designed for low power, high reliability, and radiation tolerance. Nine FBIUs were built and integrated with the fiber optic physical layer consisting of the fiber cable plant (FCP) and star coupler assembly (SCA). Performance and environmental testing, including radiation exposure, was performed on selected FBIUs and the physical layer. The integrated system was demonstrated with a full motion color video image transfer across the bus while simultaneously performing utility functions with a fiber bus control module (FBCM) over a telemetry and control (T&C) bus, in this case AS1773.

  4. Results from the CLIC Test Facility

    CERN Document Server

    Braun, H; Bossart, Rudolf; Chautard, F; Corsini, R; Delahaye, J P; Godot, J C; Hutchins, S; Kamber, I; Madsen, J H B; Rinolfi, Louis; Rossat, G; Schreiber, S; Suberlucq, Guy; Thorndahl, L; Wilson, Ian H; Wuensch, Walter

    1996-01-01

    In order to study the principle of the Compact Linear Collider (CLIC) based on the Two Beam Acceleration (TBA) scheme at high frequency, a CLIC Test Facility (CTF) has been set-up at CERN. After four years of successful running, the experimental programme is now fully completed and all its objectives reached, particularly the generation of a high intensity drive beam with short bunches by a photo-injector, the production of 30 GHz RF power and the acceleration of a probe beam by 30 GHz structures. A summary of the CTF results and their impact on linear collider design is given. This covers 30 GHz high power testing, study of intense, short single bunches; as well as RF-Gun, photocathode and beam diagnostic developments. A second phase of the test facility (CTF2) is presently being installed to demonstrate the feasibility of the TBA scheme by constructing a fully engineered, 10 m long, test section very similar to the CLIC drive and main linacs, producing up to 480 MW of peak RF power at 30 GHz and acceleratin...

  5. 75 FR 19357 - Honey From the People's Republic of China: Notice of Amended Final Results Pursuant to Final...

    Science.gov (United States)

    2010-04-14

    ... and Animal By-Products Import & Export Group Corp. v. United States, 2009 U.S. App. LEXIS 24374 (Fed... or Scot T. Fullerton, AD/CVD Operations, Office 9, Import Administration, U.S. Department of Commerce... Republic of China: Notice of Amended Final Results Pursuant to Final Court Decision AGENCY: Import...

  6. Final focus test beam alignment: A draft proposal

    International Nuclear Information System (INIS)

    Fischer, G.E.; Ruland, R.E.

    1989-03-01

    The Final Focus Test Beam is a transport line designed to transmit 50 GeV electron beams of SLC emittance (3 x 10 -10 radian-meters) straight through the central arm of the Beam Switchyard (BSY C line) with a final focus point out in the Research Yard but relatively near the end of the switchyard tunnel. The hardware, methods and procedures outlined in this proposal are dedicated to measuring the placement of mechanical objects with respect to certain defined geometric axes. We wish to emphasize that the very difficult problems of locating the effective magnetic axes of focusing elements, the effective electrical center of beam position monitors and even the effective axis of the incident beam relative to mechanical reference surfaces is outside the scope of this work. Further, this proposal is restricted to the act of measurement and does not consider the vital task of on-line mechanical repositioning of elements that will, in likelihood, be called upon during operation of the system. 16 refs., 16 figs., 4 tabs

  7. Clinical Trial Results Summary for Laypersons: A User Testing Study.

    Science.gov (United States)

    Raynor, D K; Myers, L; Blackwell, K; Kress, B; Dubost, A; Joos, A

    2018-01-01

    To apply "user testing" to maximize readability and acceptability of a Clinical Trial Results Laypersons Summary-a new European requirement. "User testing" (using questionnaire and semistructured interview) assessed whether people could find and understand key points. Findings were used to improve content and design, prior to retesting. Participants had a range of levels of health literacy and there was a higher education group. Participants accessed the summary on screen. In round 1 we tested 12 points of information. In round 2 a revised summary addressing round 1 findings was tested, leading to a third final version. In round 1, 2 of 12 points of information did not reach the target and interviews raised further format and content issues (some distracting technical explanations and inability to find or understand the 2 main study purposes). These findings informed revisions for the version tested in round 2, with 2 different points not reaching the target (inclusion criteria relating to duration of seasonal allergies and how researchers found out about participants' symptoms). Identified problems in both rounds were addressed and reflected in the final version. Despite improvements, participants did not consistently understand that summaries were intended for the public, or to only interpret results of single trials in the context of additional trials. All readers, including those with higher education, found the clear and straightforward language acceptable. Applying "user testing" resulted in a largely health-literate summary suitable for people across a range of backgrounds.

  8. Pretreatment Engineering Platform Phase 1 Final Test Report

    International Nuclear Information System (INIS)

    Kurath, Dean E.; Hanson, Brady D.; Minette, Michael J.; Baldwin, David L.; Rapko, Brian M.; Mahoney, Lenna A.; Schonewill, Philip P.; Daniel, Richard C.; Eslinger, Paul W.; Huckaby, James L.; Billing, Justin M.; Sundar, Parameshwaran S.; Josephson, Gary B.; Toth, James J.; Yokuda, Satoru T.; Baer, Ellen B.K.; Barnes, Steven M.; Golovich, Elizabeth C.; Rassat, Scot D.; Brown, Christopher F.; Geeting, John G.H.; Sevigny, Gary J.; Casella, Amanda J.; Bontha, Jagannadha R.; Aaberg, Rosanne L.; Aker, Pamela M.; Guzman-Leong, Consuelo E.; Kimura, Marcia L.; Sundaram, S.K.; Pires, Richard P.; Wells, Beric E.; Bredt, Ofelia P.

    2009-01-01

    Pacific Northwest National Laboratory (PNNL) was tasked by Bechtel National Inc. (BNI) on the River Protection Project, Hanford Tank Waste Treatment and Immobilization Plant (RPP-WTP) project to conduct testing to demonstrate the performance of the WTP Pretreatment Facility (PTF) leaching and ultrafiltration processes at an engineering-scale. In addition to the demonstration, the testing was to address specific technical issues identified in Issue Response Plan for Implementation of External Flowsheet Review Team (EFRT) Recommendations - M12, Undemonstrated Leaching Processes. Testing was conducted in a 1/4.5-scale mock-up of the PTF ultrafiltration system, the Pretreatment Engineering Platform (PEP). Parallel laboratory testing was conducted in various PNNL laboratories to allow direct comparison of process performance at an engineering-scale and a laboratory-scale. This report presents and discusses the results of those tests.

  9. Pretreatment Engineering Platform Phase 1 Final Test Report

    Energy Technology Data Exchange (ETDEWEB)

    Kurath, Dean E.; Hanson, Brady D.; Minette, Michael J.; Baldwin, David L.; Rapko, Brian M.; Mahoney, Lenna A.; Schonewill, Philip P.; Daniel, Richard C.; Eslinger, Paul W.; Huckaby, James L.; Billing, Justin M.; Sundar, Parameshwaran S.; Josephson, Gary B.; Toth, James J.; Yokuda, Satoru T.; Baer, Ellen BK; Barnes, Steven M.; Golovich, Elizabeth C.; Rassat, Scot D.; Brown, Christopher F.; Geeting, John GH; Sevigny, Gary J.; Casella, Amanda J.; Bontha, Jagannadha R.; Aaberg, Rosanne L.; Aker, Pamela M.; Guzman-Leong, Consuelo E.; Kimura, Marcia L.; Sundaram, S. K.; Pires, Richard P.; Wells, Beric E.; Bredt, Ofelia P.

    2009-12-23

    Pacific Northwest National Laboratory (PNNL) was tasked by Bechtel National Inc. (BNI) on the River Protection Project, Hanford Tank Waste Treatment and Immobilization Plant (RPP-WTP) project to conduct testing to demonstrate the performance of the WTP Pretreatment Facility (PTF) leaching and ultrafiltration processes at an engineering-scale. In addition to the demonstration, the testing was to address specific technical issues identified in Issue Response Plan for Implementation of External Flowsheet Review Team (EFRT) Recommendations - M12, Undemonstrated Leaching Processes.( ) Testing was conducted in a 1/4.5-scale mock-up of the PTF ultrafiltration system, the Pretreatment Engineering Platform (PEP). Parallel laboratory testing was conducted in various PNNL laboratories to allow direct comparison of process performance at an engineering-scale and a laboratory-scale. This report presents and discusses the results of those tests.

  10. The Benchmark Test Results of QNX RTOS

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jang Yeol; Lee, Young Jun; Cheon, Se Woo; Lee, Jang Soo; Kwon, Kee Choon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2010-10-15

    A Real-Time Operating System(RTOS) is an Operating System(OS) intended for real-time applications. Benchmarking is a point of reference by which something can be measured. The QNX is a Real Time Operating System(RTOS) developed by QSSL(QNX Software Systems Ltd.) in Canada. The ELMSYS is the brand name of commercially available Personal Computer(PC) for applications such as Cabinet Operator Module(COM) of Digital Plant Protection System(DPPS) and COM of Digital Engineered Safety Features Actuation System(DESFAS). The ELMSYS PC Hardware is being qualified by KTL(Korea Testing Lab.) for use as a Cabinet Operator Module(COM). The QNX RTOS is being dedicated by Korea Atomic Energy Research Institute (KAERI). This paper describes the outline and benchmarking test results on Context Switching, Message Passing, Synchronization and Deadline Violation of QNX RTOS under the ELMSYS PC platform

  11. The Benchmark Test Results of QNX RTOS

    International Nuclear Information System (INIS)

    Kim, Jang Yeol; Lee, Young Jun; Cheon, Se Woo; Lee, Jang Soo; Kwon, Kee Choon

    2010-01-01

    A Real-Time Operating System(RTOS) is an Operating System(OS) intended for real-time applications. Benchmarking is a point of reference by which something can be measured. The QNX is a Real Time Operating System(RTOS) developed by QSSL(QNX Software Systems Ltd.) in Canada. The ELMSYS is the brand name of commercially available Personal Computer(PC) for applications such as Cabinet Operator Module(COM) of Digital Plant Protection System(DPPS) and COM of Digital Engineered Safety Features Actuation System(DESFAS). The ELMSYS PC Hardware is being qualified by KTL(Korea Testing Lab.) for use as a Cabinet Operator Module(COM). The QNX RTOS is being dedicated by Korea Atomic Energy Research Institute (KAERI). This paper describes the outline and benchmarking test results on Context Switching, Message Passing, Synchronization and Deadline Violation of QNX RTOS under the ELMSYS PC platform

  12. Synthesis of low cycle fatigue test results

    International Nuclear Information System (INIS)

    Andrews, R.M.

    1990-01-01

    Axial strain controlled cycle fatigue tests were carried out on type 316 stainless steel parent metal, vacuum and non-vacuum electron beams welds, submerged arc welds and gas shielded metal arc welds. Testing covered total strains in the range 0.6% to 2%, and was at room temperature and 550 0 C. Parent metal and the electron beam welds showed rapid cyclic hardening, while arc welds showed little hardening. The weld metal cyclic stress-strain response was above that obtained for the parent metal, although below data obtained by other workers for similar parent materials. Weld metal endurances were above the ASME N47 continuous cycling design line at both temperatures, and comparable with parent metal data. However, the weld metal data approached the design line at low strain ranges (around 0.5%). Endurances were predicted from crack growth rates estimated from striation spacings, giving acceptable results except for the gas shielded metal arc weldments. (author)

  13. Results from the STAR TPC system test

    International Nuclear Information System (INIS)

    Betts, W.

    1996-01-01

    A system test of various components of the Solenoidal Tracker at RHIC (STAR) detector, operating in concern, has recently come on-line. Communication between a major sub-detector, a sector of the Time Projection Chamber (TPC), and the trigger, data acquisition and slow controls systems has been established, enabling data from cosmic ray muons to be collected. First results from an analysis of the TPC data are presented. These include measurements of system noise, electronic parameters such as amplifier gains and pedestal values, and tracking resolution for cosmic ray muons and laser induced ionization tracks. A discussion on the experience gained in integrating the different components for the system test is also given

  14. Multijet final states: exact results and the leading pole approximation

    International Nuclear Information System (INIS)

    Ellis, R.K.; Owens, J.F.

    1984-09-01

    Exact results for the process gg → ggg are compared with those obtained using the leading pole approximation. Regions of phase space where the approximation breaks down are discussed. A specific example relevant for background estimates to W boson production is presented. It is concluded that in this instance the leading pole approximation may underestimate the standard QCD background by more than a factor of two in certain kinematic regions of physical interest

  15. Nuclear Power Safety Reporting System. Final evaluation results

    International Nuclear Information System (INIS)

    Finlayson, F.C.; Newton, R.D.

    1986-02-01

    This document presents the results of a study conducted by the US Nuclear Regulatory Commission of an unobtrusive, voluntary, anonymous third-party managed, nonpunitive human factors data gathering system (the Nuclear power Safety Reporting System - NPSRS) for the nuclear electric power production industry. The data to be gathered by the NPSRS are intended for use in identifying and quantifying the factors that contribute to the occurrence of significant safety incidents involving humans in nuclear power plants. The NPSRS has been designed to encourage participation in the System through guarantees of reporter anonymity provided by a third-party organization that would be responsible for NPSRS management. As additional motivation to reporters for contributing data to the NPSRS, conditional waivers of NRC disciplinary action would be provided to individuals. These conditional waivers of immunity would apply to potential violations of NRC regulations that might be disclosed through reports submitted to the System about inadvertent, noncriminal incidents in nuclear plants. This document summarizes the overall results of the study of the NPSRS concept. In it, a functional description of the NPSRS is presented together with a review and assessment of potential problem areas that might be met if the System were implemented. Conclusions and recommendations resulting from the study are also presented. A companion volume (NUREG/CR-4133, Nuclear Power Safety Reporting System: Implementation and Operational Specifications'') presented in detail the elements, requirements, forms, and procedures for implementing and operating the System. 13 refs

  16. Evaluation of ring tensile test results

    International Nuclear Information System (INIS)

    Chatterjee, S.; Anantharaman, S.; Balakrishnan, K.S.; Sivaramakrish, K.S.

    1990-01-01

    Ring specimens of 5-mm width cut from Zircaloy-2 cladding of reactor operated fuel elements that had experienced 5000 to 15,000 MWD/T of fuel burnup were subjected to ring tensile testing. The true stress-true strain data points up to the onset of necking from the individual load-elongation curves of these specimens were used as input data in Voce's equation. The results reveal that the uniform elongation (UE) values generated using Voce's equation were within (UE-2)% of the experimental percent uniform elongation (UE%). The corresponding ultimate tensile strength values were within ±1%. The uncertainty inherently associated in the determination of gauge length introduces extraneous deformation in the rings tested. Previous results had shown that a 14% increase in cladding diameter caused the gauge length to increase by 40%. To simulate the contribution of extraneous deformation due to an increase in cladding diameter, an analysis of the variation of the tensile parameters (uniform elongation and ultimate tensile strength) due to increase in the gauge length in the range of 10 to 40% was carried out. The results are discussed

  17. Dual color radiometer imagery and test results

    International Nuclear Information System (INIS)

    Silver, A.; Carlen, F.; Link, D.; Zegel, F.

    1989-01-01

    This paper presents a review of the technical characteristics of the Dual Color Radiometer and recent data and test results. The Dual Color Radiometer is a state-of-the-art device that provides simultaneous pixel to pixel registered thermal imagery in both the 3 to 5 and 8 to 12 micron regions. The device is unique in terms of its spatial and temperature resolution of less than 0.10 degrees C temperature and 0.10 milliradian spatial resolution. In addition, the device is tailored for use by the Automatic Target Recognizer (ATR) community

  18. AOF: standalone test results of GALACSI

    Science.gov (United States)

    La Penna, P.; Aller Carpentier, E.; Argomedo, J.; Arsenault, R.; Conzelmann, R. D.; Delabre, B.; Donaldson, R.; Gago, F.; Gutierrez-Cheetam, P.; Hubin, N.; Jolley, P.; Kiekebusch, M.; Kirchbauer, J. P.; Klein, B.; Kolb, J.; Kuntschner, H.; Le Louarn, M.; Lizon, J.-L.; Madec, P.-Y.; Manescau, A.; Mehrgan, L.; Oberti, S.; Quentin, J.; Sedghi, B.; Ströbele, S.; Suárez Valles, M.; Soenke, C.; Tordo, S.; Vernet, J.

    2016-07-01

    GALACSI is the Adaptive Optics (AO) module that will serve the MUSE Integral Field Spectrograph. In Wide Field Mode it will enhance the collected energy in a 0.2"×0.2" pixel by a factor 2 at 750 nm over a Field of View (FoV) of 1'×1' using the Ground Layer AO (GLAO) technique. In Narrow Field Mode, it will provide a Strehl Ratio of 5% (goal 10%) at 650 nm, but in a smaller FoV (7.5"×7.5" FoV), using Laser Tomography AO (LTAO). Before being ready for shipping to Paranal, the system has gone through an extensive testing phase in Europe, first in standalone mode and then in closed loop with the DSM in Europe. After outlining the technical features of the system, we describe here the first part of that testing phase and the integration with the AOF ASSIST (Adaptive Secondary Setup and Instrument Stimulator) testbench, including a specific adapter for the IRLOS truth sensor. The procedures for the standalone verification of the main system performances are outlined, and the results of the internal functional tests of GALACSI after full integration and alignment on ASSIST are presented.

  19. Partial-array test results in IFSMTF

    International Nuclear Information System (INIS)

    Lue, J.W.; Dresner, L.; Koizumi, K.; Lubell, M.S.; Luton, J.N.; Shen, S.S.; Zahn, G.R.; Zichy, J.A.

    1985-01-01

    Preliminary performance tests of two large superconducting magnets have been carried out in the International Fusion Superconducting Magnet Test Facility (IFSMTF). Each of the Japanese (JA) and General Dynamics/Convair (GD) coils was operated up to its full design current of 10.2 kA with the other serving as an adjacent background coil at 40% of design current. Cryostatic stability was demonstrated for both coils by noting recovery from a full half-turn (5 m) driven normal. A new pick-up coil compensation scheme was successfully used for the quench detection system. Each coil remained superconducting when the other was dumped. Unique instrumentation was used to measure changes in bore dimensions and displacement of the winding from the coil case. Agreement between structural analysis and measurement of bore dimension changes resulting from magnetic loads is good. The Swiss (CH) coil underwent only a cryogenic test. The forced cooling worked well and an inlet temperature of 3.8 K was demonstrated

  20. Updated Results of Ultrasonic Transducer Irradiation Test

    Energy Technology Data Exchange (ETDEWEB)

    Daw, Joshua; Palmer, Joe [Idaho National Laboratory, P.O. Box 1625, MS 4112, Idaho Falls, ID, 38415-3840 (United States); Ramuhalli, Pradeep; Keller, Paul; Montgomery, Robert [Pacific Northwest National Laboratory, 902 Battelle Blvd. Richland, WA, 99354 (United States); Chien, Hual-Te [Argonne National Laboratory, 9700 S. Cass Avenue Argonne, IL, 60439 (United States); Tittmann, Bernhard; Reinhardt, Brian [Pennsylvania State University, 212 Earth and Engr. Sciences Building, University Park, PA, 16802 (United States); Kohse, Gordon [Massachusetts Institute of Technology, 77 Massachusetts Ave. Cambridge, MA 02139 (United States); Rempe, Joy [Rempe and Associates, LLC, 360 Stillwater, Idaho Falls, ID 83404 (United States); Villard, J.F. [Commissariat a l' energie atomique et aux energies alternatives, Centre d' etudes de Cadarache, 13108 Saint-Paul-lez-Durance (France)

    2015-07-01

    Ultrasonic technologies offer the potential for high accuracy and resolution in-pile measurement of a range of parameters, including geometry changes, temperature, crack initiation and growth, gas pressure and composition, and microstructural changes. Many Department of Energy-Office of Nuclear Energy (DOE-NE) programs are exploring the use of ultrasonic technologies to provide enhanced sensors for in-pile instrumentation during irradiation testing. For example, the ability of small diameter ultrasonic thermometers (UTs) to provide a temperature profile in candidate metallic and oxide fuel would provide much needed data for validating new fuel performance models. These efforts are limited by the lack of identified ultrasonic transducer materials capable of long term performance under irradiation test conditions. To address this need, the Pennsylvania State University (PSU) was awarded an Advanced Test Reactor National Scientific User Facility (ATR NSUF) project to evaluate the performance of promising magnetostrictive and piezoelectric transducers in the Massachusetts Institute of Technology Research Reactor (MITR) up to a fast fluence of at least 10{sup 21} n/cm{sup 2}. A multi-National Laboratory collaboration funded by the Nuclear Energy Enabling Technologies Advanced Sensors and Instrumentation (NEET-ASI) program also provided initial support for this effort. This irradiation, which started in February 2014, is an instrumented lead test and real-time transducer performance data are collected along with temperature and neutron and gamma flux data. The irradiation is ongoing and will continue to approximately mid-2015. To date, very encouraging results have been attained as several transducers continue to operate under irradiation. (authors)

  1. Final results of the Resonance spacecraft calibration effort

    Science.gov (United States)

    Sampl, Manfred; Macher, Wolfgang; Gruber, Christian; Oswald, Thomas; Rucker, Helmut O.

    2010-05-01

    We report our dedicated analyses of electrical field sensors onboard the Resonance spacecraft with a focus on the high-frequency electric antennas. The aim of the Resonance mission is to investigate wave-particle interactions and plasma dynamics in the inner magnetosphere of the Earth, with a focus on phenomena occurring along the same field line and within the same flux tube of the Earth's magnetic field. Four spacecraft will be launched, in the middle of the next decade, to perform these observations and measurements. Amongst a variety of instruments and probes several low- and high-frequency electric sensors will be carried which can be used for simultaneous remote sensing and in-situ measurements. The high-frequency electric sensors consist of cylindrical antennas mounted on four booms extruded from the central body of the spacecraft. In addition, the boom rods themselves are used together with the these sensors for mutual impedance measurements. Due to the parasitic effects of the conducting spacecraft body the electrical antenna representations (effective length vector, capacitances) do not coincide with their physical representations. The analysis of the reception properties of these antennas is presented, along with a contribution to the understanding of their impairment by other objects; in particular the influence of large magnetic loop sensors is studied. In order to analyse the antenna system, we applied experimental and numerical methods. The experimental method, called rheometry, is essentially an electrolytic tank measurement, where a scaled-down spacecraft model is immersed into an electrolytic medium (water) with corresponding measurements of voltages at the antennas. The numerical method consists of a numerical solution of the underlying field equations by means of computer programs, which are based on wire-grid and patch-grid models. The experimental and numerical results show that parasitic effects of the antenna-spacecraft assembly alter the

  2. Design, construction and testing of a DC bioeffects test enclosure for small animals. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Frazier, M J; Preache, M M

    1980-11-01

    This final report describes both the engineering development of a DC bioeffects test enclosure for small laboratory animals, and the biological protocol for the use of such enclosures in the testing of animals to determine possible biological effects of the environment associated with HVDC transmission lines. The test enclosure which has been designed is a modular unit, which will house up to eight rat-sized animals in individual compartments. Multiple test enclosures can be used to test larger numbers of animals. A prototype test enclosure has been fabricated and tested to characterize its electrical performance characteristics. The test enclosure provides a simulation of the dominant environment associated with HVDC transmission lines; namely, a static electric field and an ion current density. A biological experimental design has been developed for assessing the effects of the dominant components of the HVDC transmission line environment.

  3. Final model independent result of DAMA/LIBRA-phase1

    Energy Technology Data Exchange (ETDEWEB)

    Bernabei, R.; D' Angelo, S.; Di Marco, A. [Universita di Roma ' ' Tor Vergata' ' , Dipartimento di Fisica, Rome (Italy); INFN, sez. Roma ' ' Tor Vergata' ' , Rome (Italy); Belli, P. [INFN, sez. Roma ' ' Tor Vergata' ' , Rome (Italy); Cappella, F.; D' Angelo, A.; Prosperi, D. [Universita di Roma ' ' La Sapienza' ' , Dipartimento di Fisica, Rome (Italy); INFN, sez. Roma, Rome (Italy); Caracciolo, V.; Castellano, S.; Cerulli, R. [INFN, Laboratori Nazionali del Gran Sasso, Assergi (Italy); Dai, C.J.; He, H.L.; Kuang, H.H.; Ma, X.H.; Sheng, X.D.; Wang, R.G. [Chinese Academy, IHEP, Beijing (China); Incicchitti, A. [INFN, sez. Roma, Rome (Italy); Montecchia, F. [INFN, sez. Roma ' ' Tor Vergata' ' , Rome (Italy); Universita di Roma ' ' Tor Vergata' ' , Dipartimento di Ingegneria Civile e Ingegneria Informatica, Rome (Italy); Ye, Z.P. [Chinese Academy, IHEP, Beijing (China); University of Jing Gangshan, Jiangxi (China)

    2013-12-15

    The results obtained with the total exposure of 1.04 ton x yr collected by DAMA/LIBRA-phase1 deep underground at the Gran Sasso National Laboratory (LNGS) of the I.N.F.N. during 7 annual cycles (i.e. adding a further 0.17 ton x yr exposure) are presented. The DAMA/LIBRA-phase1 data give evidence for the presence of Dark Matter (DM) particles in the galactic halo, on the basis of the exploited model independent DM annual modulation signature by using highly radio-pure NaI(Tl) target, at 7.5{sigma} C.L. Including also the first generation DAMA/NaI experiment (cumulative exposure 1.33 ton x yr, corresponding to 14 annual cycles), the C.L. is 9.3{sigma} and the modulation amplitude of the single-hit events in the (2-6) keV energy interval is: (0.0112{+-}0.0012) cpd/kg/keV; the measured phase is (144{+-}7) days and the measured period is (0.998{+-}0.002) yr, values well in agreement with those expected for DM particles. No systematic or side reaction able to mimic the exploited DM signature has been found or suggested by anyone over more than a decade. (orig.)

  4. Permeability changes in coal resulting from gas desorption. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Levine, J.R.; Johnson, P.W.

    1992-11-30

    This report documents studies on the effects of gas sorption on coal, with the intent of eventually evaluating how sorption and strain affect permeability. These studies were, carried out at the University of Alabama during the period from 1989 through 1992. Two major experimental methods were developed and used. In the strain experiments, electronic strain gauges were attached to polished blocks of coal in order to measure linear and volumetric swelling due to gas sorption. The effects of bedding plane orientation, of gas type, and of coal type were investigated. In the gravimetric experiment the weight of small samples of coal was measured during exposure to high pressure gases. Sample measurements were corrected for buoyancy effects and for sample swelling, and the results were plotted in the form of Langmuir isotherms. Experiments were conducted to determine the effect of grain size, coal type, moisture, and of sorbant gas. The advantage of this method is that it can be applied to very small samples, and it enabled comparison liptinite versus vitrinite concentrates, and kerogen rich versus kerogen depleted oil shales. Also included is a detailed discussion of the makeup of coal and its effect on gas sorption behavior.

  5. Power-cooling mismatch test series. Test PCM-2A; test results report

    International Nuclear Information System (INIS)

    Cawood, G.W.; Holman, G.W.; Martinson, Z.R.; Legrand, B.L.

    1976-09-01

    The report describes the results of an in-pile experimental investigation of pre- and postcritical heat flux (CHF) behavior of a single 36-inch-long, pressurized water reactor (PWR) type, UO 2 -fueled, zircaloy-clad fuel rod. The nominal coolant conditions for pressure and temperature were representative of those found in a commercial PWR. Nine separate departures from nucleate boiling (DNB) cycles were performed by either of two different methods: (a) decreasing the coolant flow rate while the fuel rod power was held constant, or (b) increasing the fuel rod power while the coolant flow rate was held constant. DNB was obtained during eight of the nine cycles performed. For the final flow reduction, the mass flux was decreased to 6.1 x 10 5 lb/hr-ft 2 at a constant peak linear heat generation rate of 17.8 kW/ft. The fuel rod was allowed to remain in film boiling for about 210 seconds during this final flow reduction. The fuel rod remained intact during the test. Results of on-line measurements of the fuel rod behavior are presented together with discussion of instrument performance. A comparison of the data with Fuel Rod Analysis Program-Transient 2 (FRAP-T2) computer code calculations is included

  6. Final Results From the Circumarctic Lakes Observation Network (CALON) Project

    Science.gov (United States)

    Hinkel, K. M.; Arp, C. D.; Eisner, W. R.; Frey, K. E.; Grosse, G.; Jones, B. M.; Kim, C.; Lenters, J. D.; Liu, H.; Townsend-Small, A.

    2015-12-01

    Since 2012, the physical and biogeochemical properties of ~60 lakes in northern Alaska have been investigated under CALON, a project to document landscape-scale variability of Arctic lakes in permafrost terrain. The network has ten nodes along two latitudinal transects extending inland 200 km from the Arctic Ocean. A meteorological station is deployed at each node and six representative lakes instrumented and continuously monitored, with winter and summer visits for synoptic assessment of lake conditions. Over the 4-year period, winter and summer climatology varied to create a rich range of lake responses over a short period. For example, winter 2012-13 was very cold with a thin snowpack producing thick ice across the region. Subsequent years had relatively warm winters, yet regionally variable snow resulted in differing gradients of ice thickness. Ice-out timing was unusually late in 2014 and unusually early in 2015. Lakes are typically well-mixed and largely isothermal, with minor thermal stratification occurring in deeper lakes during calm, sunny periods in summer. Lake water temperature records and morphometric data were used to estimate the ground thermal condition beneath 28 lakes. Application of a thermal equilibrium steady-state model suggests a talik penetrating the permafrost under many larger lakes, but lake geochemical data do not indicate a significant contribution of subpermafrost groundwater. Biogeochemical data reveal distinct spatial and seasonal variability in chlorophyll biomass, chromophoric dissolved organic carbon (CDOM), and major cations/anions. Generally, waters sampled beneath ice in April had distinctly higher concentrations of inorganic solutes and methane compared with August. Chlorophyll concentrations and CDOM absorption were higher in April, suggesting significant biological/biogeochemical activity under lake ice. Lakes are a positive source of methane in summer, and some also emit nitrous oxide and carbon dioxide. As part of the

  7. Final Technical Report. Results of Phases 2-5

    Energy Technology Data Exchange (ETDEWEB)

    Narang, David [Arizona Public Service Company (APS), Phoenix, AZ (United States); Ayyanar, Raja [Arizona State Univ., Mesa, AZ (United States); Gemin, Paul [General Electric, Fairfield, CT (United States); Baggu, Murali [National Renewable Energy Lab. (NREL), Golden, CO (United States); Srinivasan, Devarajan [ViaSol Energy Solutions, LLC, Tempe, AZ (United States)

    2015-02-27

    APS’s renewable energy portfolio, driven in part by Arizona’s Renewable Energy Standard (RES) currently includes more than 1100 MW of installed capacity, equating to roughly 3000 GWh of annual production. Overall renewable production is expected to grow to 6000 GWh by 2025. It is expected that distributed photovoltaics, driven primarily by lower cost, will contribute to much of this growth and that by 2025, distributed installations will account for half of all renewable production (3000GHW). As solar penetration increases, additional analysis may be required for routine utility processes to ensure continued safe and reliable operation of the electric distribution network. Such processes include residential or commercial interconnection requests and load shifting during normal feeder operations. Circuits with existing high solar penetration will also have to be studied and results will need to be evaluated for adherence to utility practices or strategy. Increased distributed PV penetration may offer benefits such as load offsetting, but it also has the potential to adversely impact distribution system operation. These effects may be exacerbated by the rapid variability of PV production. Detailed effects of these phenomena in distributed PV applications continue to be studied. Comprehensive, high-resolution electrical models of the distribution system were developed to analyze the impacts of PV on distribution circuit protection systems (including coordination and anti-islanding), predict voltage regulation and phase balance issues, and develop volt/VAr control schemes. Modeling methods were refined by validating against field measurements. To augment the field measurements, methods were developed to synthesize high resolution load and PV generation data to facilitate quasi-static time series simulations. The models were then extended to explore boundary conditions for PV hosting capability of the feeder and to simulate common utility practices such as feeder

  8. Final state effects in liquid 4He: An experimental test

    International Nuclear Information System (INIS)

    Sokol, P.E.; Silver, R.N.; Sosnick, T.R.; Snow, W.M.

    1989-01-01

    Inelastic neutron scattering at high momentum transfers can provide direct information on the atomic momentum distribution n(p) when the Impulse Approximation (IA) is valid. In isotropic systems, the scattering in the IA is directly proportional to the longitudinal momentum distribution which is a function of a single scaling variable Y /triple bond/ (M/Q)(ω /minus/ ω/sub r/), where M is the mass of the scatterer, Q is the momentum transfer, and ω/sub r/ = Q 2 /2M is the recoiled energy. However, the experimentally attainable Q's are not large enough to reach the IA limit. Deviations from the IA due to final state scattering by neighboring atoms, known as final state effects, will distort the observed scattering from the IA prediction. Thus, an understanding of deviations from the IA is essential to accurate determination of n(p). Liquid helium provides an excellent testing ground for studying FSE in a dense, strongly interacting system for two reasons. First, theoretical calculations of the momentum distributions are available in both the normal liquid, and superfluid phases. These calculations are believed to be quite accurate, since they agree well with several other measured properties of the liquid. In addition, n(p) in the superfluid exhibits a very sharp feature, the Bose condensate peak, which should be very sensitive to FSE. Comparison of the predicted scattering obtained from the theoretical n(p) using the IA to the experimentally observed scattering can be used to study deviations due to FSE. 14 refs., 7 figs

  9. TANK 40 FINAL SB4 CHEMICAL CHARACTERIZATION RESULTS

    International Nuclear Information System (INIS)

    Best, J.

    2008-01-01

    from a settled sample. This decant was not filtered prior to performing a warm nitric acid digestion of the material in order to measure the Si content by ICP-AES. Three Si standards, a blank, and a matrix standard were prepared and submitted along with the Tank 40 samples. The following conclusions were drawn from the analytical results reported here: (1) The elemental composition of this sample and the analyses conducted here are reasonable and consistent with DWPF batch data measurements; (2) There was no measurable Si in samples of Tank 40 decant; and (3) Ag and the Ru, Rh, and Pd noble metal concentrations agree well with the estimate used for the SB4 70/30 blend of SB3 and Tank 51 performed in the SRNL Shielded Cells

  10. Validation Testing for Automated Solubility Measurement Equipment Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Lachut, J. S. [Washington River Protection Solutions LLC, Richland, WA (United States)

    2016-01-11

    Laboratory tests have been completed to test the validity of automated solubility measurement equipment using sodium nitrate and sodium chloride solutions (see test plan WRPS-1404441, “Validation Testing for Automated Solubility Measurement Equipment”). The sodium nitrate solution results were within 2-3% of the reference values, so the experiment is considered successful using the turbidity meter. The sodium chloride test was done by sight, as the turbidity meter did not work well using sodium chloride. For example, the “clear” turbidity reading was 53 FNU at 80 °C, 107 FNU at 55 °C, and 151 FNU at 20 °C. The sodium chloride did not work because it is granular and large; as the solution was stirred, the granules stayed to the outside of the reactor and just above the stir bar level, having little impact on the turbidity meter readings as the meter was aimed at the center of the solution. Also, the turbidity meter depth has an impact. The salt tends to remain near the stir bar level. If the meter is deeper in the slurry, it will read higher turbidity, and if the meter is raised higher in the slurry, it will read lower turbidity (possibly near zero) because it reads the “clear” part of the slurry. The sodium chloride solution results, as measured by sight rather than by turbidity instrument readings, were within 5-6% of the reference values.

  11. Results from the Cooler and Lead Tests

    International Nuclear Information System (INIS)

    Green, Michael A.

    2010-01-01

    The report presents the results of testing MICE spectrometer magnet current leads on a test apparatus that combines both the copper leads and the high temperature superconducting (HTS) leads with a single Cryomech PT415 cooler and liquid helium tank. The current is carried through the copper leads from 300 K to the top of the HTS leads. The current is then carried through the HTS leads to a feed-through from the vacuum space to the inside of a liquid helium tank. The experiment allows one to measure the performance of both cooler stages along with the performance of the leads. While the leads were powered we measured the voltage drops through the copper leads, through the HTS leads, through spliced to the feed-through, through the feed-through and through the low-temperature superconducting loop that connects one lead to the other. Measurements were made using the leads that were used in spectrometer magnet 1A and spectrometer magnet 2A. These are the same leads that were used for Superbend and Venus magnets at LBNL. The IL/A for these leads was 5.2 x 10 6 m -1 . The leads turned out to be too long. The same measurements were made using the leads that were installed in magnet 2B. The magnet 2B leads had an IL/A of 3.3 x 10 6 A m -1 . This report discusses the cooler performance and the measured electrical performance of the lead circuit that contains the copper leads and the superconducting leads. All of the HTS leads that were installed in magnet 2B were current tested using this apparatus.

  12. Tuned Chamber Core Panel Acoustic Test Results

    Science.gov (United States)

    Schiller, Noah H.; Allen, Albert R.

    2016-01-01

    This report documents acoustic testing of tuned chamber core panels, which can be used to supplement the low-frequency performance of conventional acoustic treatment. The tuned chamber core concept incorporates low-frequency noise control directly within the primary structure and is applicable to sandwich constructions with a directional core, including corrugated-, truss-, and fluted-core designs. These types of sandwich structures have long, hollow channels (or chambers) in the core. By adding small holes through one of the facesheets, the hollow chambers can be utilized as an array of low-frequency acoustic resonators. These resonators can then be used to attenuate low-frequency noise (below 400 Hz) inside a vehicle compartment without increasing the weight or size of the structure. The results of this test program demonstrate that the tuned chamber core concept is effective when used in isolation or combined with acoustic foam treatments. Specifically, an array of acoustic resonators integrated within the core of the panels was shown to improve both the low-frequency absorption and transmission loss of the structure in targeted one-third octave bands.

  13. Field Lysimeter Test Facility: Second year (FY 1989) test results

    International Nuclear Information System (INIS)

    Campbell, M.D.; Gee, G.W.; Kanyid, M.J.; Rockhold, M.L.

    1990-04-01

    The Record of Decision associated with the Hanford Defense Waste Environmental Impact Statement (53 FR 12449-53) commits to an evaluation of the use of protective barriers placed over near-surface wastes. The barrier must protect against wind and water erosion and limit plant and animal intrusion and infiltration of water. Successful conclusion of this program will yield the necessary protective barrier design for near-surface waste isolation. This report presents results from the second year of tests at the FLTF. The primary objective of testing protective barriers at the FLTF was to measure the water budgets within the various barriers and assess the effectiveness of their designs in limiting water intrusion into the zone beneath each barrier. Information obtained from these measurements is intended for use in refining barrier designs. Four elements of water budget were measured during the year: precipitation, evaporation, storage, and drainage. Run-off, which is a fifth element of a complete water budget, was made negligible by a lip on the lysimeters that protrudes 5 cm above the soil surface to prevent run-off. A secondary objective of testing protective barriers at the FLTF was to refine procedures and equipment to support data collection for verification of the computer model needed for long-term projections of barrier performance. 6 refs

  14. A prototype tap test imaging system: Initial field test results

    Science.gov (United States)

    Peters, J. J.; Barnard, D. J.; Hudelson, N. A.; Simpson, T. S.; Hsu, D. K.

    2000-05-01

    This paper describes a simple, field-worthy tap test imaging system that gives quantitative information about the size, shape, and severity of defects and damages. The system consists of an accelerometer, electronic circuits for conditioning the signal and measuring the impact duration, a laptop PC and data acquisition and processing software. The images are generated manually by tapping on a grid printed on a plastic sheet laid over the part's surface. A mechanized scanner is currently under development. The prototype has produced images for a variety of aircraft composite and metal honeycomb structures containing flaws, damages, and repairs. Images of the local contact stiffness, deduced from the impact duration using a spring model, revealed quantitatively the stiffness reduction due to flaws and damages, as well as the stiffness enhancement due to substructures. The system has been field tested on commercial and military aircraft as well as rotor blades and engine decks on helicopters. Field test results will be shown and the operation of the system will be demonstrated.—This material is based upon work supported by the Federal Aviation Administration under Contract #DTFA03-98-D-00008, Delivery Order No. IA016 and performed at Iowa State University's Center for NDE as part of the Center for Aviation Systems Reliability program.

  15. Fast Flux Test Facility final safety analysis report. Amendment 72

    Energy Technology Data Exchange (ETDEWEB)

    Gantt, D. A.

    1992-08-01

    This document provides the Final Safety Analysis Report (FSAR) Amendment 72 for incorporation into the Fast Flux Test Facility (FFTF) FSAR set. This amendment change incorporates Engineering Change Notices issued subsequent to Amendment 71 and approved for incorporation before June 24, 1992. These include changes in: Chapter 2, Site Characteristics; Chapter 3, Design Criteria Structures, Equipment, and Systems; Chapter 5B, Reactor Coolant System; Chapter 7, Instrumentation and Control Systems; Chapter 8, Electrical Systems - The description of the Class 1E, 125 Vdc systems is updated for the higher capacity of the newly installed, replacement batteries; Chapter 9, Auxiliary Systems - The description of the inert cell NASA systems is corrected to list the correct number of spare sample points; Chapter 11, Reactor Refueling System; Chapter 12, Radiation Protection and Waste Management; Chapter 13, Conduct of Operations; Chapter 16, Quality Assurance; Chapter 17, Technical Specifications; Chapter 19, FFTF Fire Specifications for Fire Detection, Alarm, and Protection Systems; Chapter 20, FFTF Criticality Specifications; and Appendix B, Primary Piping Integrity Evaluation.

  16. Full length prototype SSC dipole test results

    International Nuclear Information System (INIS)

    Strait, J.; Brown, B.C.; Carson, J.

    1987-01-01

    Results are presented from tests of the first full length prototype SSC dipole magnet. The cryogenic behavior of the magnet during a slow cooldown to 4.5K and a slow warmup to room temperature has been measured. Magnetic field quality was measured at currents up to 2000 A. Averaged over the body field all harmonics with the exception of b 2 and b 8 are at or within the tolerances specified by the SSC Central Design Group. (The values of b 2 and b 8 result from known design and construction defects which will be be corrected in later magnets.) Using an NMR probe the average body field strength is measured to be 10.283 G/A with point to point variations on the order of one part in 1000. Data are presented on quench behavior of the magnet up to 3500 A (approximately 55% of full field) including longitudinal and transverse velocities for the first 250 msec of the quench

  17. Guidelines to Interpret Results of Mechanical Blade Test

    International Nuclear Information System (INIS)

    Arias Vega, F.; Sanz Martin, J. C.

    1999-01-01

    This report shows the interpretation of full scale rotor blade test results and describes the engineering testing models and coefficients for any feasible rotor blade design, in order to accept and to certify any final manufactured blade as an allowable product, fit for use and working with a completely security during all the wind turbines lifetime. This work was carried out at the Wind Energy Division of the CIEMAT.DER and it is based on the authors technical experience in this field, after many years working on testing blades. Also, this paper contains results of the European wind turbine Standards II relevant to the European Project: JOULE III R.D. where the Wind Energy Division took part as participant too. (Author)

  18. Guidelines to Interpret Results of Mechanical Blade Test

    Energy Technology Data Exchange (ETDEWEB)

    Arias Vega, F.; Sanz Martin, J. C. [Ciemat, Madrid (Spain)

    2000-07-01

    This report shows the interpretation of full scale rotor blade test results and describes the engineering testing models and coefficients for any feasible rotor blade design, in order to accept and to certify any final manufactured blades as an allowable product, fit for use and working with a completely security during all the windturbine's lifetime. This work was carried out at the Wind Energy Division of the CIEMAT.DER and it is based on the author's technical experience in this field, after many years working on testing blades. Also, this paper contains results of the European wind turbine Standards II relevant to the European Project: JOULE III R.D. where the Wind Energy Division took part as participant too. (Author)

  19. Summary of CPAS EDU Testing Analysis Results

    Science.gov (United States)

    Romero, Leah M.; Bledsoe, Kristin J.; Davidson, John.; Engert, Meagan E.; Fraire, Usbaldo, Jr.; Galaviz, Fernando S.; Galvin, Patrick J.; Ray, Eric S.; Varela, Jose

    2015-01-01

    The Orion program's Capsule Parachute Assembly System (CPAS) project is currently conducting its third generation of testing, the Engineering Development Unit (EDU) series. This series utilizes two test articles, a dart-shaped Parachute Compartment Drop Test Vehicle (PCDTV) and capsule-shaped Parachute Test Vehicle (PTV), both of which include a full size, flight-like parachute system and require a pallet delivery system for aircraft extraction. To date, 15 tests have been completed, including six with PCDTVs and nine with PTVs. Two of the PTV tests included the Forward Bay Cover (FBC) provided by Lockheed Martin. Advancements in modeling techniques applicable to parachute fly-out, vehicle rate of descent, torque, and load train, also occurred during the EDU testing series. An upgrade from a composite to an independent parachute simulation allowed parachute modeling at a higher level of fidelity than during previous generations. The complexity of separating the test vehicles from their pallet delivery systems necessitated the use the Automatic Dynamic Analysis of Mechanical Systems (ADAMS) simulator for modeling mated vehicle aircraft extraction and separation. This paper gives an overview of each EDU test and summarizes the development of CPAS analysis tools and techniques during EDU testing.

  20. Automated Testing Infrastructure and Result Comparison for Geodynamics Codes

    Science.gov (United States)

    Heien, E. M.; Kellogg, L. H.

    2013-12-01

    The geodynamics community uses a wide variety of codes on a wide variety of both software and hardware platforms to simulate geophysical phenomenon. These codes are generally variants of finite difference or finite element calculations involving Stokes flow or wave propagation. A significant problem is that codes of even low complexity will return different results depending on the platform due to slight differences in hardware, software, compiler, and libraries. Furthermore, changes to the codes during development may affect solutions in unexpected ways such that previously validated results are altered. The Computational Infrastructure for Geodynamics (CIG) is funded by the NSF to enhance the capabilities of the geodynamics community through software development. CIG has recently done extensive work in setting up an automated testing and result validation system based on the BaTLab system developed at the University of Wisconsin, Madison. This system uses 16 variants of Linux and Mac platforms on both 32 and 64-bit processors to test several CIG codes, and has also recently been extended to support testing on the XSEDE TACC (Texas Advanced Computing Center) Stampede cluster. In this work we overview the system design and demonstrate how automated testing and validation occurs and results are reported. We also examine several results from the system from different codes and discuss how changes in compilers and libraries affect the results. Finally we detail some result comparison tools for different types of output (scalar fields, velocity fields, seismogram data), and discuss within what margins different results can be considered equivalent.

  1. Reactor calculation benchmark PCA blind test results

    International Nuclear Information System (INIS)

    Kam, F.B.K.; Stallmann, F.W.

    1980-01-01

    Further improvement in calculational procedures or a combination of calculations and measurements is necessary to attain 10 to 15% (1 sigma) accuracy for neutron exposure parameters (flux greater than 0.1 MeV, flux greater than 1.0 MeV, and dpa). The calculational modeling of power reactors should be benchmarked in an actual LWR plant to provide final uncertainty estimates for end-of-life predictions and limitations for plant operations. 26 references, 14 figures, 6 tables

  2. Reactor calculation benchmark PCA blind test results

    Energy Technology Data Exchange (ETDEWEB)

    Kam, F.B.K.; Stallmann, F.W.

    1980-01-01

    Further improvement in calculational procedures or a combination of calculations and measurements is necessary to attain 10 to 15% (1 sigma) accuracy for neutron exposure parameters (flux greater than 0.1 MeV, flux greater than 1.0 MeV, and dpa). The calculational modeling of power reactors should be benchmarked in an actual LWR plant to provide final uncertainty estimates for end-of-life predictions and limitations for plant operations. 26 references, 14 figures, 6 tables.

  3. 78 FR 78812 - Purified Carboxymethylcellulose From the Netherlands: Final Results of Antidumping Duty...

    Science.gov (United States)

    2013-12-27

    ... Carboxymethylcellulose From the Netherlands: Final Results of Antidumping Duty Administrative Review and Final No... Netherlands. For the final results, we continue to find that sales of subject merchandise by Akzo Nobel... of the AD order on purified CMC from the Netherlands.\\1\\ We invited interested parties to comment on...

  4. Construction and test of the final CMS Barrel Drift Tube Muon Chamber prototype

    Energy Technology Data Exchange (ETDEWEB)

    Aguilar-Benitez, M.; Alberdi, J.; Arneodo, M.; Banicz, K.; Benettoni, M.; Benvenuti, A.; Bethke, S.; Cerrada, M. E-mail: cerrada@ciemat.es; Cirio, R.; Colino, N.; Conti, E.; Dallavalle, M.; Daniel, M.; Dattola, D.; Daudo, F.; De Giorgi, M.; Dosselli, U.; Fanfani, A.; Fanin, C.; Fouz, M.C.; Gasparini, F.; Gasparini, U.; Giacomelli, P.; Giordano, V.; Gonella, F.; Grandi, C.; Guaita, P.; Guerzoni, M.; Lacaprara, S.; Lippi, I.; Marcellini, S.; Marin, J.; Martinelli, R.; Maselli, S.; Meneguzzo, A.; Migliore, E.; Mocholi, J.; Monaco, V.; Montanari, A.; Montanari, C.; Odorici, F.; Oller, J.C.; Paoletti, S.; Passaseo, M.; Pegoraro, M.; Peroni, C.; Puerta, J.; Reithler, H.; Romero, A.; Romero, L.; Ronchese, P.; Rossi, A.M.; Rovelli, T.; Sacchi, R.; Salicio, J.M.; Staiano, A.; Steinbeck, T.; Torassa, E.; Travaglini, R.; Ventura, L.; Ventura, S.; Vitelli, A.; Voetee, F.; Wegner, M.; Willmott, C.; Zotto, P.; Zumerle, G

    2002-03-21

    A prototype of the CMS Barrel Muon Detector incorporating all the features of the final chambers was built using the mass production assembly procedures and tools. The performance of this prototype was studied in a muon test beam at CERN and the results obtained are presented in this paper.

  5. Initial Burn Pan (JMTF) Testing Results

    Science.gov (United States)

    2016-03-01

    burn pan and one located high on the Ex-USS Shadwell. There were also a number of GoPro cameras (3-4) that were positioned to observe specific...locations around the test area. A remote control drone equipped with a GoPro camera was also used to video the third test. All recorded video and still

  6. AGR-2 Irradiation Test Final As-Run Report

    Energy Technology Data Exchange (ETDEWEB)

    Collin, Blaise P. [Idaho National Lab. (INL), Idaho Falls, ID (United States). VHTR Program

    2014-08-01

    This document presents the as-run analysis of the AGR-2 irradiation experiment. AGR-2 is the second of the planned irradiations for the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. Funding for this program is provided by the U.S. Department of Energy as part of the Very High Temperature Reactor (VHTR) Technology Development Office (TDO) program. The objectives of the AGR-2 experiment are to: 1. Irradiate UCO (uranium oxycarbide) and UO2 (uranium dioxide) fuel produced in a large coater. Fuel attributes are based on results obtained from the AGR-1 test and other project activities. 2. Provide irradiated fuel samples for post-irradiation experiment (PIE) and safety testing. 3. Support the development of an understanding of the relationship between fuel fabrication processes, fuel product properties, and irradiation performance. The primary objective of the test was to irradiate both UCO and UO2 TRISO (tristructural isotropic) fuel produced from prototypic scale equipment to obtain normal operation and accident condition fuel performance data. The UCO compacts were subjected to a range of burnups and temperatures typical of anticipated prismatic reactor service conditions in three capsules. The test train also includes compacts containing UO2 particles produced independently by the United States, South Africa, and France in three separate capsules. The range of burnups and temperatures in these capsules were typical of anticipated pebble bed reactor service conditions. The results discussed in this report pertain only to U.S.-produced fuel.

  7. AGR-2 Irradiation Test Final As-Run Report

    Energy Technology Data Exchange (ETDEWEB)

    Collin, Blaise P. [Idaho National Lab. (INL), Idaho Falls, ID (United States). VHTR Program

    2014-08-01

    This document presents the as-run analysis of the AGR-2 irradiation experiment. AGR-2 is the second of the planned irradiations for the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. Funding for this program is provided by the U.S. Department of Energy as part of the Very High Temperature Reactor (VHTR) Technical Development Office (TDO) program. The objectives of the AGR-2 experiment are to: (a) Irradiate UCO (uranium oxycarbide) and UO2 (uranium dioxide) fuel produced in a large coater. Fuel attributes are based on results obtained from the AGR-1 test and other project activities. (b) Provide irradiated fuel samples for post-irradiation experiment (PIE) and safety testing. (c) Support the development of an understanding of the relationship between fuel fabrication processes, fuel product properties, and irradiation performance. The primary objective of the test was to irradiate both UCO and UO2 TRISO (tri-structural isotropic) fuel produced from prototypic scale equipment to obtain normal operation and accident condition fuel performance data. The UCO compacts were subjected to a range of burnups and temperatures typical of anticipated prismatic reactor service conditions in three capsules. The test train also includes compacts containing UO2 particles produced independently by the United States, South Africa, and France in three separate capsules. The range of burnups and temperatures in these capsules were typical of anticipated pebble bed reactor service conditions. The results discussed in this report pertain only to U.S. produced fuel.

  8. 7X performance results - final report : ASCI Red vs Red Storm.

    Energy Technology Data Exchange (ETDEWEB)

    Dinge, Dennis C. (Cray Inc., Albuquerque, NM); Davis, Michael E. (Cray Inc., Albuquerque, NM); Haskell, Karen H.; Ballance, Robert A.; Gardiner, Thomas Anthony; Stevenson, Joel O.; Noe, John P.

    2011-04-01

    The goal of the 7X performance testing was to assure Sandia National Laboratories, Cray Inc., and the Department of Energy that Red Storm would achieve its performance requirements which were defined as a comparison between ASCI Red and Red Storm. Our approach was to identify one or more problems for each application in the 7X suite, run those problems at multiple processor sizes in the capability computing range, and compare the results between ASCI Red and Red Storm. The first part of this report describes the two computer systems, the applications in the 7X suite, the test problems, and the results of the performance tests on ASCI Red and Red Storm. During the course of the testing on Red Storm, we had the opportunity to run the test problems in both single-core mode and dual-core mode and the second part of this report describes those results. Finally, we reflect on lessons learned in undertaking a major head-to-head benchmark comparison.

  9. Supercritical CO2 test loop operation and first test results

    International Nuclear Information System (INIS)

    Wright, Steven A.; Pickard, Paul S.

    2009-01-01

    The DOE Office of Nuclear Energy is investigating advanced Brayton cycles for use with next generation nuclear power plants. The focus of this work is on the supercritical CO 2 Brayton cycle which has the potential for high efficiency, and for reduced capital costs due to very compact turbomachinery. Sandia has fabricated and is operating a supercritical CO 2 (S-CO 2 ) test loop to investigate the key technology issues associated with this cycle. This loop is part of a multi-year phased development program to develop a megawatt (MW) class closed S-CO 2 Brayton cycle to demonstrate the applicability of this cycle for DOE Gen-IV program. The current loop has been configured as both a compression loop and as simple heated but unrecuperated Brayton cycle. A second split-flow or re-compression Brayton cycle is currently under development that will use approximately 1 MW of heat to run the Brayton cycle. Early configurations of this split-flow Brayton cycle will be operational later this fiscal year. The key issues for this cycle include the fundamental issues of compressor fluid performance and system control near the critical point, but also the supporting technology issues of bearings, sealing technologies, and rotor windage losses which are also essential to achieving efficiency and cost objectives. These tests are providing the first measurements and information on these key supercritical CO 2 power conversion systems questions. Important data for all these issues has been obtained. This report presents the major results of the testing by showing and comparing the measured compressor performance map with the predicted performance. The compression loop uses a ∼50 kWe motor driven compressor to spin a 37 mm OD compressor at design speeds up to 75,000 rpm with a pressure ratio of 1.8 and a flow rate of 3.53 kg/s for a compressor inlet condition of 305.3 K and 7690 kPa. The most recent configuration of this loop has added a small turbine and 260 kW of heater power is

  10. SCTF Core-I test results

    International Nuclear Information System (INIS)

    Adachi, Hiromichi; Sudo, Yukio; Iwamura, Takamichi; Osakabe, Masahiro; Ohnuki, Akira; Hirano, Kemmei

    1982-07-01

    The Slab Core Test Facility (SCTF) of Japan Atomic Energy Research Institute (JAERI) was constructed to investigate two-dimensional thermohydrodynamics in the core and the communication in fluid behavior between the core and the upper plenum during the last part of blowdown, refill and reflood phases of a posturated loss-of-coolant accident (LOCA) of a pressurized water reactor (PWR). In the present report, effects of system pressure on reflooding phenomena shall be discussed based on the data of Tests S1-SH2, S1-01 and S1-02 which are the parameteris tests for system pressure effects belonging to the SCTF Core-I forced flooding test series. Major items discussed in this report are (1) hydrodynamic behavior in the system, (2) core thermal behavior, (3) core heat transfer and (4) two-dimensional hydrodynamic behavior in the pressure vessel including the core. (author)

  11. Reliability Estimation Based Upon Test Plan Results

    National Research Council Canada - National Science Library

    Read, Robert

    1997-01-01

    The report contains a brief summary of aspects of the Maximus reliability point and interval estimation technique as it has been applied to the reliability of a device whose surveillance tests contain...

  12. Test OPTRAN 1-1 results

    International Nuclear Information System (INIS)

    Martinson, Z.R.

    1982-01-01

    The objective of the OPT 1-1 Test Series was to evaluate the extent of damage and the threshold for failure during simulated BWR anticipated transients. Four power transient tests with progressively higher power levels were performed with preirradiated fuel rods at power ramp rates as high as 550 kW/m per second. Six separately shrouded fuel rods fabricated by the General Electric Co., and preirradiated in the Monticello BWR to burnups of about 5000 to 23,000 MWd/t were tested, four at a time. Four of the fuel rods were of typical GE 8 x 8 design, except for fuel length (0.75 m). Two of the rods included design modifications to improve their PCI-resistant characteristics. A lengthy fuel conditioning preceded the transient testing of the fuel rods

  13. Visual perception skills testing: preliminary results

    CSIR Research Space (South Africa)

    Smith, Andrew C

    2009-02-01

    Full Text Available Good visual perception skills are important in the effective manipulation of Tangible User Interfaces. This paper reports on the application of a test set researchers have developed specifically to quantify the visual perception skills of children...

  14. Final report : testing and evaluation for solar hot water reliability.

    Energy Technology Data Exchange (ETDEWEB)

    Caudell, Thomas P. (University of New Mexico, Albuquerque, NM); He, Hongbo (University of New Mexico, Albuquerque, NM); Menicucci, David F. (Building Specialists, Inc., Albuquerque, NM); Mammoli, Andrea A. (University of New Mexico, Albuquerque, NM); Burch, Jay (National Renewable Energy Laboratory, Golden CO)

    2011-07-01

    Solar hot water (SHW) systems are being installed by the thousands. Tax credits and utility rebate programs are spurring this burgeoning market. However, the reliability of these systems is virtually unknown. Recent work by Sandia National Laboratories (SNL) has shown that few data exist to quantify the mean time to failure of these systems. However, there is keen interest in developing new techniques to measure SHW reliability, particularly among utilities that use ratepayer money to pay the rebates. This document reports on an effort to develop and test new, simplified techniques to directly measure the state of health of fielded SHW systems. One approach was developed by the National Renewable Energy Laboratory (NREL) and is based on the idea that the performance of the solar storage tank can reliably indicate the operational status of the SHW systems. Another approach, developed by the University of New Mexico (UNM), uses adaptive resonance theory, a type of neural network, to detect and predict failures. This method uses the same sensors that are normally used to control the SHW system. The NREL method uses two additional temperature sensors on the solar tank. The theories, development, application, and testing of both methods are described in the report. Testing was performed on the SHW Reliability Testbed at UNM, a highly instrumented SHW system developed jointly by SNL and UNM. The two methods were tested against a number of simulated failures. The results show that both methods show promise for inclusion in conventional SHW controllers, giving them advanced capability in detecting and predicting component failures.

  15. Overview of the PBF test results

    International Nuclear Information System (INIS)

    Zeile, H.J.

    1980-01-01

    The Thermal Fuels Behavior Program (TFBP) of EG and G Idaho conducts fuel behavior research in the Power Burst Facility (PBF) at INEL and at the Halden Reactor in Norway. The fuels behavior research in the PBF is directed toward providing a detailed understanding of the response of light water reactor (LWR) nuclear fuel assemblies to off-normal and hypothesized accident conditions. Single fuel rods and clusters of highly instrumented fuel rods are installed within a central test space of the PBF core for testing. The core can be operated in various modes to provide test conditions typical of accidents and off-normal conditions that may be experienced in a pressurized water reactor or a boiling water reactor

  16. Tests results of skutterudite based thermoelectric unicouples

    International Nuclear Information System (INIS)

    Saber, Hamed H.; El-Genk, Mohamed S.; Caillat, Thierry

    2007-01-01

    Tests were performed of skutterudite based unicouples with (MAY-04) and without (MAR-03) metallic coating on the legs near the hot junction to quantify the effect on reducing performance degradation with operation time. The p-legs in the unicouples were made of CeFe 3.5 Co 0.5 Sb 12 and the n-legs of CoSb 3 . The MAY-04 test was performed in vacuum (∼9 x 10 -7 torr) for ∼2000 h at hot and cold junction temperatures of 892.1 ± 11.9 K and 316.1 ± 5.5 K, respectively, while the MAR-03 test was performed in argon cover gas (0.051-0.068 MPa) at 972.61 ± 10.0 K and 301.1 ± 5.1 K, respectively. The argon cover gas decreased antimony loss from the legs in the MAR-03 test, but marked degradation in performance occurred over time. Conversely, the metallic coating in the MAY-04 test was very effective in reducing performance degradation of the unicouple. Because the cross sectional areas of the legs in MAY-04 were larger than those in MAR-03, the measured electrical power of the former is much higher than that of the latter, but the Beginning of Test (BOT) open circuit voltages, V oc (204.2 mV) for both unicouples were almost the same. The peak electrical power of the MAY-04 unicouple decreased 12.35% from 1.62W e at BOT to 1.42W e after ∼2000 h of testing, while that of the MAR-03 unicouple decreased 25.37% from 0.67 to 0.5W e after 261 h of testing at the above temperatures. The estimated peak efficiency of the MAY-04 unicouple, shortly after BOT (10.65%), was only ∼0.37% points lower than the theoretical value, calculated assuming zero side heat losses and zero contact resistance per leg

  17. 75 FR 50992 - Wooden Bedroom Furniture From the People's Republic of China: Final Results and Final Rescission...

    Science.gov (United States)

    2010-08-18

    ... polyethylene sheet inputs based on Philippine imports of HTS subheading 3921.19.19. See Comment 6 of the Issues... Analysis Memorandum (Final Results Analysis Memo). We have corrected coding errors in our calculation of... 6: Expanded Polyethylene Sheet Comment 7: Bon Feet Comment 8: Poly Vinyl Chloride Veneer Comment 9...

  18. MFTF-B PACE tests and final cost report

    International Nuclear Information System (INIS)

    Krause, K.H.; Kozman, T.A.; Smith, J.L.; Horan, R.J.

    1986-10-01

    The Mirror Fusion Test Facility (MFTF-B) construction project was successfully completed in February 1986, with the conclusion of the Plant and Capital Equipment (PACE) Tests. This series of tests, starting in September 1985 and running through February 1986, demonstrated the overall machine capabilities and special facilities accomplishments for the Mirror Fusion Test Facility Project

  19. Tests and final integration of the ATLAS semiconductor tracker

    CERN Document Server

    Mikulec, Bettina

    2005-01-01

    The Silicon Tracker (SCT) is part of the Inner Detector at the ATLAS experiment at CERN. Its basic building blocks are 5 different types of silicon strip modules. In total more than 15000 p-on-n single-sided silicon strip sensors of an area of about 61 m2 were used to produce 4088 SCT modules. An overall module production yield of 92% could be achieved, where the silicon modules comply with the tight electrical, thermal and mechanical specifications. The macro-assembly of 2112 barrel modules to the four barrel support cylinders was successfully carried out. The nine disks of one endcap are fully populated with 988 modules, and for the second endcap more than 50% of the modules are already mounted. Test results operating complete barrels will be presented as well as a description of the test setup. The different integration steps of the SCT with the surrounding Transition Radiation Tracker (TRT) will be explained. The installation of SCT and TRT into the ATLAS pit will happen during 2006.

  20. Conventional fuel tank blunt impact tests : test and analysis results

    Science.gov (United States)

    2014-04-02

    The Federal Railroad Administrations Office of Research : and Development is conducting research into fuel tank : crashworthiness. A series of impact tests are planned to : measure fuel tank deformation under two types of dynamic : loading conditi...

  1. Results of workplace drug testing in Norway

    Directory of Open Access Journals (Sweden)

    Hilde Marie Erøy Lund

    2011-12-01

    Full Text Available Workplace drug testing is less common in Norway than in many other countries. During the period from 2000-2006, 13469 urine or blood samples from employees in the offshore industry, shipping companies and aviation industry were submitted to the Norwegian Institute of Public Health for drug testing. The samples were analysed for benzodiazepines, illicit drugs, muscle relaxants with sedating properties, opioids and z-hypnotics. In total, 2.9% of the samples were positive for one or more substances. During the study period the prevalence decreased for morphine (from 1.9% to 1.1% and increased for amphetamine (from 0.04% to 0.6%, clonazepam (from 0% to 0.1%, methamphetamine (from 0.04% to 0.6%, nitrazepam (from 0% to 0.4% and oxazepam (from 0.5% to 1.3% (p<0.05. There was no significant change in prevalence for the other substances included in the analytical programme. Illicit drugs were significantly associated with lower age (OR: 0.93, p<0.05. This study found low prevalence of drugs among employees in companies with workplace drug testing programmes in Norway.

  2. New energy test procedures for refrigerators and other appliances; FINAL

    International Nuclear Information System (INIS)

    Meier, Alan; Ernebrant, Stefan; Kawamoto, Kaoru; Wihlborg, Mats

    1999-01-01

    Many innovations in refrigerator design rely on microprocessors, sensors, and algorithms to control automatic defrost, variable speed,and other features. Even though these features strongly influence energy consumption, the major energy test procedures presently test only a refrigerator's mechanical efficiency and ignore the ''software'' aspects. We describe a new test procedure where both ''hardware'' and ''software'' tests are fed into a dynamic simulation model. A wide range of conditions can be tested and simulated. This approach promotes international harmonization because the simulation model can also be programmed to estimate energy use for the ISO, DOE, or JIS test. The approach outlined for refrigerators can also be applied to other appliances

  3. Nevada Test Site, Nye County, Nevada. Final environmental impact statement

    International Nuclear Information System (INIS)

    1977-09-01

    This environmental statement for the Nevada Test Site (NTS) considers underground nuclear detonations with yields of one megaton or less, along with the preparations necessary for such detonations. The testing activities considered also include other continuing and intermittent activities, both nuclear and nonnuclear, which can best be conducted in the remote and controlled area of the Nevada Test Site. These activities are listed, with emphasis on weapons testing programs which do not remain static

  4. Nevada Test Site, Nye County, Nevada. Final environmental impact statement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-09-01

    This environmental statement for the Nevada Test Site (NTS) considers underground nuclear detonations with yields of one megaton or less, along with the preparations necessary for such detonations. The testing activities considered also include other continuing and intermittent activities, both nuclear and nonnuclear, which can best be conducted in the remote and controlled area of the Nevada Test Site. These activities are listed, with emphasis on weapons testing programs which do not remain static.

  5. Achilles tests finally nail PWR fuel clad ballooning fears

    International Nuclear Information System (INIS)

    Dore, P.; McMinn, K.

    1992-01-01

    A conclusive series of experiments carried out by AEA Reactor Services at its Achilles rig in the UK has finally allayed fears that fuel clad ballooning is a major safety problem for Sizewell B, Britain's first Pressurized Water Reactor. The experiments are described in this article. (author)

  6. SURVEY RESULTS AND TESTING OF RAILWAY BRIDGES

    Directory of Open Access Journals (Sweden)

    I. H. Haniiev

    2010-03-01

    Full Text Available The article is devoted to the survey and testing of railway bridges by the State Joint-Stock Railway Company «Uzbekiston Temir Yollari» («Uzbekistan Railways». It is stated that in the existing rules on determination of the capacity of bridges the recommendations on taking into account the cumulative deflection to the moment of technical diagnostics of spans on the bridge capacity are absent. The author states on the need to develop a method for determining the wear of spans on restriction of the residual deflection in the bridge floor slabs.

  7. WSEAT Shock Testing Margin Assessment Using Energy Spectra Final Report.

    Energy Technology Data Exchange (ETDEWEB)

    Sisemore, Carl; Babuska, Vit; Booher, Jason

    2018-02-01

    Several programs at Sandia National Laboratories have adopted energy spectra as a metric to relate the severity of mechanical insults to structural capacity. The purpose being to gain insight into the system's capability, reliability, and to quantify the ultimate margin between the normal operating envelope and the likely system failure point -- a system margin assessment. The fundamental concern with the use of energy metrics was that the applicability domain and implementation details were not completely defined for many problems of interest. The goal of this WSEAT project was to examine that domain of applicability and work out the necessary implementation details. The goal of this project was to provide experimental validation for the energy spectra based methods in the context of margin assessment as they relate to shock environments. The extensive test results concluded that failure predictions using energy methods did not agree with failure predictions using S-N data. As a result, a modification to the energy methods was developed following the form of Basquin's equation to incorporate the power law exponent for fatigue damage. This update to the energy-based framework brings the energy based metrics into agreement with experimental data and historical S-N data.

  8. Final results of the XR2-1 BWR metallic melt relocation experiment

    International Nuclear Information System (INIS)

    Gauntt, R.O.; Humphries, L.L.

    1997-08-01

    This report documents the final results of the XR2-1 boiling water reactor (BWR) metallic melt relocation experiment, conducted at Sandia National Laboratories for the U.S. Nuclear Regulatory Commission. The objective of this experiment was to investigate the material relocation processes and relocation pathways in a dry BWR core following a severe nuclear reactor accident such as an unrecovered station blackout accident. The imposed test conditions (initial thermal state and the melt generation rates) simulated the conditions for the postulated accident scenario and the prototypic design of the lower core test section (in composition and in geometry) ensured that thermal masses and physical flow barriers were modeled adequately. The experiment has shown that, under dry core conditions, the metallic core materials that melt and drain from the upper core regions can drain from the core region entirely without formation of robust coherent blockages in the lower core. Temporary blockages that suspended pools of molten metal later melted, allowing the metals to continue draining downward. The test facility and instrumentation are described in detail. The test progression and results are presented and compared to MERIS code analyses. 6 refs., 55 figs., 4 tabs

  9. Fort St. Vrain hot functional test results

    International Nuclear Information System (INIS)

    Phelps, R.D.

    1974-01-01

    A description is given of Fort St. Vrain hot functional tests performed to evaluate the initial nonnuclear performance of the primary coolant system and the associated effects on the various internal components of the reactor vessel and primary coolant system. The components included the twelve steam generator modules, the four helium circulators, the PCRV thermal barrier and liner coolant system, the helium purification system, and the primary and secondary closures at each of the PCRV penetrations. Additional objectives included analysis of the parallel operation of the four helium circulators and the performance of several circulator start/stop transients under various conditions of primary coolant temperature and pressure. Vibration and acoustical phenomena within the vessel were measured, recorded, and compared to theoretical analyses; a verification of reverse flow in the shutdown loop steam generator during one loop operation was performed; the PCRV was again observed for its structural response to internal pressure; and comparisons were made relative to data recorded during the initial pressure test completed in July 1971. (U.S.)

  10. Structural damping results from vibration tests of straight piping sections

    International Nuclear Information System (INIS)

    Ware, A.G.; Thinnes, G.L.

    1984-01-01

    EG and G Idaho is assisting the USNRC and the Pressure Vessel Research Committee in supporting a final position on revised damping values for structural analyses of nuclear piping systems. As part of this program, a series of vibrational tests on 76-mm and 203-mm (3-in. amd 8-in.) Schedule 40 carbon steel piping was conducted to determine the changes in structural damping due to various parametric effects. The 10-m (33-ft) straight sections of piping were rigidly supported at the ends. Spring, rod, and constant force hangers, as well as a sway brace and snubbers were included as intermediate supports. Excitation was provided by low-force level hammer inpacts, a hydraulic shaker, and a 445-kN (50-ton) overhead crane. Data was recorded using acceleration, strain, and displacement time histories. This paper presents results from the testing showing the effect of stress level and type of supports on structural damping in piping

  11. LEDA RF distribution system design and component test results

    International Nuclear Information System (INIS)

    Roybal, W.T.; Rees, D.E.; Borchert, H.L.; McCarthy, M.; Toole, L.

    1998-01-01

    The 350 MHz and 700 MHz RF distribution systems for the Low Energy Demonstration Accelerator (LEDA) have been designed and are currently being installed at Los Alamos National Laboratory. Since 350 MHz is a familiar frequency used at other accelerator facilities, most of the major high-power components were available. The 700 MHz, 1.0 MW, CW RF delivery system designed for LEDA is a new development. Therefore, high-power circulators, waterloads, phase shifters, switches, and harmonic filters had to be designed and built for this applications. The final Accelerator Production of Tritium (APT) RF distribution systems design will be based on much of the same technology as the LEDA systems and will have many of the RF components tested for LEDA incorporated into the design. Low power and high-power tests performed on various components of these LEDA systems and their results are presented here

  12. Tests of a photovoltaic pump: first results

    International Nuclear Information System (INIS)

    Petroselli, A.; Pica, M.; Biondi, P.

    2005-01-01

    The paper deals with a first series of tests conducted in Viterbo (42 deg 25 min North, 12 deg 06 min East) on a PV-DC pump. This series lasted eight months - from the first days of January to the end of August 2003 - and involved measurements of: air and PV-module temperatures; solar radiations, both on horizontal surface and tilted module surface; voltage and intensity of the DC currents from the panel; pump pressures and flow rates. In total, as much as 3,150 data were collected every day. The analysis of the data allowed to obtain some simple empirical relations expressing daily pumped water volumes, instantaneous flow rates and system efficiencies as a function of both radiations and total dynamic heads [it

  13. RESULTS OF INITIAL AMMONIA OXIDATION TESTING

    Energy Technology Data Exchange (ETDEWEB)

    Nash, C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Fowley, M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2016-12-30

    This memo presents an experimental survey of aqueous phase chemical processes to remove aqueous ammonia from waste process streams. Ammonia is generated in both the current Hanford waste flowsheet and in future waste processing. Much ammonia will be generated in the Low Activity Waste (LAW) melters.i Testing with simulants in glass melters at Catholic University has demonstrated the significant ammonia production.ii The primary reaction there is the reducing action of sugar on nitrate in the melter cold cap. Ammonia has been found to be a problem in secondary waste stabilization. Ammonia vapors are noxious and destruction of ammonia could reduce hazards to waste treatment process personnel. It is easily evolved especially when ammonia-bearing solutions are adjusted to high pH.

  14. Final Test at the Surface of the ATLAS Endcap Muon Trigger Chamber Electronics

    CERN Document Server

    Kubota, T; Kanaya, N; Kawamoto, T; Kobayashi, T; Kuwabara, T; Nomoto, H; Sakamoto, H; Yamaguchi, T; Fukunaga, C; Ikeno, M; Iwasaki, H; Nagano, K; Nozaki, M; Sasaki, O; Tanaka, S; Yasu, Y; Hasegawa, Y; Oshita, H; Takeshita, T; Nomachi, M; Sugaya, Y; Sugimoto, T; Okumura, Y; Takahashi, Y; Tomoto, M; Kadosaka, T; Kawagoe, K; Kiyamura, H; Kurashige, H; Niwa, T; Ochi, A; Omachi, C; Takeda, H; Lifshitz, R; Lupu, N; Bressler, S; Tarem, S; Kajomovitz, E; Ben Ami, S; Bahat Treidel, O; Benhammou, Ya; Etzion, E; Lellouch, D; Levinson, L; Mikenberg, G; Roich, A

    2007-01-01

    For the detector commissioning planned in 2007, sector assembly of the ATLAS muon-endcap trigger chambers and final test at the surface for the assembled electronics are being done in CERN and almost completed. For the test, we built up the Data Acquisition (DAQ) system using test pulse of two types and cosmic rays in order to check functionality of the various aspects of the electronics mounted on a sector. So far, 99% of all 320,000 channels have been tested and most of them were installed into the ATLAS cavern. In this presentation, we will describe the DAQ systems and mass-test procedure in detail, and report the result of electronics test with some actual experiences

  15. Middleware for big data processing: test results

    Science.gov (United States)

    Gankevich, I.; Gaiduchok, V.; Korkhov, V.; Degtyarev, A.; Bogdanov, A.

    2017-12-01

    Dealing with large volumes of data is resource-consuming work which is more and more often delegated not only to a single computer but also to a whole distributed computing system at once. As the number of computers in a distributed system increases, the amount of effort put into effective management of the system grows. When the system reaches some critical size, much effort should be put into improving its fault tolerance. It is difficult to estimate when some particular distributed system needs such facilities for a given workload, so instead they should be implemented in a middleware which works efficiently with a distributed system of any size. It is also difficult to estimate whether a volume of data is large or not, so the middleware should also work with data of any volume. In other words, the purpose of the middleware is to provide facilities that adapt distributed computing system for a given workload. In this paper we introduce such middleware appliance. Tests show that this middleware is well-suited for typical HPC and big data workloads and its performance is comparable with well-known alternatives.

  16. INTRAVAL test case 1b - modelling results

    International Nuclear Information System (INIS)

    Jakob, A.; Hadermann, J.

    1991-07-01

    This report presents results obtained within Phase I of the INTRAVAL study. Six different models are fitted to the results of four infiltration experiments with 233 U tracer on small samples of crystalline bore cores originating from deep drillings in Northern Switzerland. Four of these are dual porosity media models taking into account advection and dispersion in water conducting zones (either tubelike veins or planar fractures), matrix diffusion out of these into pores of the solid phase, and either non-linear or linear sorption of the tracer onto inner surfaces. The remaining two are equivalent porous media models (excluding matrix diffusion) including either non-linear sorption onto surfaces of a single fissure family or linear sorption onto surfaces of several different fissure families. The fits to the experimental data have been carried out by Marquardt-Levenberg procedure yielding error estimates of the parameters, correlation coefficients and also, as a measure for the goodness of the fits, the minimum values of the χ 2 merit function. The effects of different upstream boundary conditions are demonstrated and the penetration depth for matrix diffusion is discussed briefly for both alternative flow path scenarios. The calculations show that the dual porosity media models are significantly more appropriate to the experimental data than the single porosity media concepts. Moreover, it is matrix diffusion rather than the non-linearity of the sorption isotherm which is responsible for the tailing part of the break-through curves. The extracted parameter values for some models for both the linear and non-linear (Freundlich) sorption isotherms are consistent with the results of independent static batch sorption experiments. From the fits, it is generally not possible to discriminate between the two alternative flow path geometries. On the basis of the modelling results, some proposals for further experiments are presented. (author) 15 refs., 23 figs., 7 tabs

  17. Supercritical water oxidation data acquisition testing. Final report, Volume I

    International Nuclear Information System (INIS)

    1996-11-01

    This report discusses the phase one testing of a data acquisition system for a supercritical water waste oxidation system. The system is designed to destroy a wide range of organic materials in mixed wastes. The design and testing of the MODAR Oxidizer is discussed. An analysis of the optimized runs is included

  18. Accelerated corrosion test for metal drainage pipes : final report.

    Science.gov (United States)

    1987-06-01

    This study represents an attempt to develop an accelerated test which would assist the highway engineer in evaluating the usefulness of a new type of coated steel culvert. The test method was to be short in duration (in the order of days), and the re...

  19. 78 FR 58520 - Extruded Rubber Thread From Malaysia; Notice of Amended Final Results of Antidumping Duty...

    Science.gov (United States)

    2013-09-24

    ... Malaysia; Notice of Amended Final Results of Antidumping Duty Administrative Review AGENCY: Import... from Malaysia.\\1\\ The period of review (POR) is October 1, 1995, through September 30, 1996. \\1\\ See Extruded Rubber Thread From Malaysia; Final Results of Antidumping Duty Administrative Review, 63 FR 12752...

  20. 76 FR 70965 - Polyethylene Retail Carrier Bags From Thailand: Correction to the Amended Final Results of...

    Science.gov (United States)

    2011-11-16

    ... Bags From Thailand: Correction to the Amended Final Results of Antidumping Duty Administrative Review... bags from Thailand for the period August 1, 2009, through July 31, 2010. The notice did not include the... bags from Thailand. See Polyethylene Retail Carrier Bags From Thailand: Amended Final Results of...

  1. Large bundle BWR test CORA-18: Test results

    International Nuclear Information System (INIS)

    Hagen, S.; Hofmann, P.; Noack, V.; Sepold, L.; Schanz, G.; Schumacher, G.

    1998-04-01

    The CORA out-of-pile experiments are part of the international Severe Fuel Damage (SFD) Program. They were performed to provide information on the damage progression of Light Water Reactor (LWR) fuel elements in Loss-of-coolant Accidents in the temperature range 1200 C to 2400 C. CORA-18 was the large BWR bundle test corresponding to the PWR test CORA-7. It should investigate if there exists an influence of the BWR bundle size on the fuel damage behaviour. Therefore, the standard-type BWR CORA bundle with 18 fuel rod simulators was replaced by a large bundle with two additional surrounding rows of 30 rods (48 rods total). Power input and steam flow were increased proportionally to the number of fuel rod simulators to give the same initial heat-up rate of about 1 K/s as in the smaller bundles. Emphasis was put on the initial phase of the damage progression. More information on the chemical composition of initial and intermediate interaction products and their relocation behaviour should be obtained. Therefore, power and steam input were terminated after the onset of the temperature escalation. (orig.) [de

  2. Stirling convertor performance mapping test results

    Science.gov (United States)

    Qiu, Songgang; Peterson, Allen A.; White, Maurice A.; Faultersack, Franklyn; Redinger, Darin L.; Petersen, Stephen L.

    2002-01-01

    The Department of Energy (DOE) has selected Free-Piston Stirling Convertors as a technology for future advanced radioisotope space power systems. In August 2000, DOE awarded competitive Phase I, Stirling Radioisotope Generator (SRG) power system integration contracts to three major aerospace contractors, resulting in SRG conceptual designs in February 2001. All three contractors based their designs on the Technology Demonstration Convertor (TDC) developed by Stirling Technology Company (STC) for DOE. The contract award to a single system integration contractor for Phases II and III of the SRG program is anticipated in late 2001. The first potential SRG mission is targeted for a Mars rover. Recent TDC performance data are provided in this paper, together with predictions from Stirling simulation models. .

  3. Sheath insulator final test report, TFE Verification Program

    International Nuclear Information System (INIS)

    1994-07-01

    The sheath insulator in a thermionic cell has two functions. First, the sheath insulator must electrically isolate the collector form the outer containment sheath tube that is in contact with the reactor liquid metal coolant. Second, The sheath insulator must provide for high uniform thermal conductance between the collector and the reactor coolant to remove away waste heat. The goals of the sheath insulator test program were to demonstrate that suitable ceramic materials and fabrication processes were available, and to validate the performance of the sheath insulator for TFE-VP requirements. This report discusses the objectives of the test program, fabrication development, ex-reactor test program, in-reactor test program, and the insulator seal specifications

  4. SMART operational field test evaluation : dispatchers survey report : final report

    Science.gov (United States)

    1997-06-01

    The Suburban Mobility Authority for Regional Transportation (SMART) has installed an automaticscheduling and dispatch system (ASD) in Southeast Michigan in accordance with their plans toimplement ITS as a site for an operational field test. The purpo...

  5. SMART operational field test evaluation : scheduler survey report : final report

    Science.gov (United States)

    1997-06-01

    The Suburban Mobility Authority for Regional Transportation (SMART) has installed an automatic scheduling and dispatch system (ASD) in Southeast Michigan in accordance with their plans to implement ITS as a site for an operational field test. The pur...

  6. Sheath insulator final test report, TFE Verification Program

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    The sheath insulator in a thermionic cell has two functions. First, the sheath insulator must electrically isolate the collector form the outer containment sheath tube that is in contact with the reactor liquid metal coolant. Second, The sheath insulator must provide for high uniform thermal conductance between the collector and the reactor coolant to remove away waste heat. The goals of the sheath insulator test program were to demonstrate that suitable ceramic materials and fabrication processes were available, and to validate the performance of the sheath insulator for TFE-VP requirements. This report discusses the objectives of the test program, fabrication development, ex-reactor test program, in-reactor test program, and the insulator seal specifications.

  7. Introduction of e-learning in dental radiology reveals significantly improved results in final examination.

    Science.gov (United States)

    Meckfessel, Sandra; Stühmer, Constantin; Bormann, Kai-Hendrik; Kupka, Thomas; Behrends, Marianne; Matthies, Herbert; Vaske, Bernhard; Stiesch, Meike; Gellrich, Nils-Claudius; Rücker, Martin

    2011-01-01

    Because a traditionally instructed dental radiology lecture course is very time-consuming and labour-intensive, online courseware, including an interactive-learning module, was implemented to support the lectures. The purpose of this study was to evaluate the perceptions of students who have worked with web-based courseware as well as the effect on their results in final examinations. Users (n(3+4)=138) had access to the e-program from any networked computer at any time. Two groups (n(3)=71, n(4)=67) had to pass a final exam after using the e-course. Results were compared with two groups (n(1)=42, n(2)=48) who had studied the same content by attending traditional lectures. In addition a survey of the students was statistically evaluated. Most of the respondents reported a positive attitude towards e-learning and would have appreciated more access to computer-assisted instruction. Two years after initiating the e-course the failure rate in the final examination dropped significantly, from 40% to less than 2%. The very positive response to the e-program and improved test scores demonstrated the effectiveness of our e-course as a learning aid. Interactive modules in step with clinical practice provided learning that is not achieved by traditional teaching methods alone. To what extent staff savings are possible is part of a further study. Copyright © 2010 European Association for Cranio-Maxillo-Facial Surgery. Published by Elsevier Ltd. All rights reserved.

  8. Setup, tests and results for the ATLAS TileCal Read Out Driver production

    CERN Document Server

    Valero, Alberto; Castillo, V; Cuenca, C; Ferrer, A; Fullana, E; González, V; Higón, E; Munar, A; Poveda, J; Ruiz-Martínez, A; Salvachúa, B; Sanchís, E; Solans, C; Soret, J; Torres, J; Valls, J A

    2007-01-01

    In this paper we describe the performance and test results of the production of the 38 ATLAS TileCal Read Out Drivers (RODs). We first describe the basic hardware specifications and firmware functionality of the modules, the test-bench setup used for production and the test procedure to qualify the boards. We then finally show and discuss the performance results.

  9. Continued research, development and test of SOFC Technology. Final report

    Energy Technology Data Exchange (ETDEWEB)

    2008-09-15

    The aim of the project was to further develop the SOFC cell and stack technology and drive down manufacturing costs in order to accomplish the performance and economic targets set forward in the SOFC road map, which has been developed in collaboration with the national Danish SOFC Strategy group. The project was divided into four parts. Part 1, Continued cell development covered the successful development of larger cells with a 500 cm2 footprint. Part 2, Cell manufacturing covered the production of 9.859 equivalents (12x12 cm2 standard cells) that were used in the stacks for demonstration projects (EFP 33033-0050)and for in-house research, development and testing in this project. Part 3, Continued stack development covered the successful test of a 3 kW{sub e} stack as well as the planning of a >8.000 hours stack test with new stack technology. The >8.000 hours test that started after the end date for this project will last for 12 months and be reported in the PSO 2008-1-010049 project. Part 4, Stack manufacturing covered a number of small stacks for in-house research, development and testing. (auther)

  10. Human performance in nondestructive inspections and functional tests: Final report

    International Nuclear Information System (INIS)

    Harris, D.H.

    1988-10-01

    Human performance plays a vital role in the inspections and tests conducted to assure the physical integrity of nuclear power plants. Even when technically-sophisticated equipment is employed, the outcome is highly dependent on human control actions, calibrations, observations, analyses, and interpretations. The principal consequences of inadequate performance are missed or falsely-reported defects. However, the cost-avoidance that stems from addressing potential risks promptly, and the increasing costs likely with aging plants, emphasize that timeliness and efficiency are important inspection-performance considerations also. Human performance issues were studied in a sample of inspections and tests regularly conducted in nuclear power plants. These tasks, selected by an industry advisory panel, were: eddy-current inspection of steam-generator tubes; ultrasonic inspection of pipe welds; inservice testing of pumps and valves; and functional testing of shock suppressors. Information was obtained for the study from industry and plant procedural documents; training materials; research reports and related documents; interviews with training specialists, inspectors, supervisory personnel, and equipment designers; and first-hand observations of task performance. Eleven recommendations are developed for improving human performance on nondestructive inspections and functional tests. Two recommendations were for the more-effective application of existing knowledge; nine recommendations were for research projects that should be undertaken to assure continuing improvements in human performance on these tasks. 25 refs., 9 figs., 1 tab

  11. Leach testing of Idaho Chemical Processing Plant final waste forms

    International Nuclear Information System (INIS)

    Schuman, R.P.

    1980-01-01

    A number of pellets and highly durable glasses prepared from nonradioactive-simulated high-level wasste calcines have been leach tested. The leach tests are patterned on the IAEA standard test and the proposed Materials Characterization Center tests. Most tests are made with static distilled water at 25, 70, 95, 250, and 350 0 C and in refluxing distilled water, Soxhlet, at 95 0 C. Leach rates are determined by analyzing the leachate by instrumental activation analysis or spectrochemical analysis and from weight loss. Leaches are run on glass using cast and core drilled cylinders, broken pieces and coarse ground material. Sample form has a considerable effect on leach rates; solid pieces gave higher leach rates than ground glass when expressed in g/cm 2 /day. Cesium, molybdenum and weight loss leach rates of cast glass cylinders in distilled water varied from -7 g/cm 7 /day at 25 0 C to approx. 10 -3 g/cm 2 /day at 250 0 C. The leach rates in static distilled water at 95 0 C were considerably lower than those in refluxing distilled water, Soxhlet, at the same temperature. Even at 25 0 C, sodium, cesium, and molybdenum readily leached from the porous pellets, but the pellets showed no visible attack, even at 250 0 C

  12. Production circulator fabrication and testing for core flow test loop. Final report, Phase III

    Energy Technology Data Exchange (ETDEWEB)

    1981-05-01

    The performance testing of two production helium circulators utilizing gas film lubrication is described. These two centrifugal-type circulators plus an identical circulator prototype will be arranged in series to provide the helium flow requirements for the Core Flow Test Loop which is part of the Gas-Cooled Fast Breeder Reactor Program (GCFR) at the Oak Ridge National Laboratory. This report presents the results of the Phase III performance and supplemental tests, which were carried out by MTI during the period of December 18, 1980 through March 19, 1981. Specific test procedures are outlined and described, as are individual tests for measuring the performance of the circulators. Test data and run descriptions are presented.

  13. Production circulator fabrication and testing for core flow test loop. Final report, Phase III

    International Nuclear Information System (INIS)

    1981-05-01

    The performance testing of two production helium circulators utilizing gas film lubrication is described. These two centrifugal-type circulators plus an identical circulator prototype will be arranged in series to provide the helium flow requirements for the Core Flow Test Loop which is part of the Gas-Cooled Fast Breeder Reactor Program (GCFR) at the Oak Ridge National Laboratory. This report presents the results of the Phase III performance and supplemental tests, which were carried out by MTI during the period of December 18, 1980 through March 19, 1981. Specific test procedures are outlined and described, as are individual tests for measuring the performance of the circulators. Test data and run descriptions are presented

  14. HANFORD CONTAINERIZED CAST STONE FACILITY TASK 1 PROCESS TESTING & DEVELOPMENT FINAL TEST REPORT

    Energy Technology Data Exchange (ETDEWEB)

    LOCKREM, L L

    2005-07-13

    Laboratory testing and technical evaluation activities on Containerized Cast Stone (CCS) were conducted under the Scope of Work (SOW) contained in CH2M HILL Hanford Group, Inc. (CHG) Contract No. 18548 (CHG 2003a). This report presents the results of testing and demonstration activities discussed in SOW Section 3.1, Task I--''Process Development Testing'', and described in greater detail in the ''Containerized Grout--Phase I Testing and Demonstration Plan'' (CHG, 2003b). CHG (2003b) divided the CCS testing and evaluation activities into six categories, as follows: (1) A short set of tests with simulant to select a preferred dry reagent formulation (DRF), determine allowable liquid addition levels, and confirm the Part 2 test matrix. (2) Waste form performance testing on cast stone made from the preferred DRF and a backup DRF, as selected in Part I, and using low activity waste (LAW) simulant. (3) Waste form performance testing on cast stone made from the preferred DRF using radioactive LAW. (4) Waste form validation testing on a selected nominal cast stone formulation using the preferred DRF and LAW simulant. (5) Engineering evaluations of explosive/toxic gas evolution, including hydrogen, from the cast stone product. (6) Technetium ''getter'' testing with cast stone made with LAW simulant and with radioactive LAW. In addition, nitrate leaching observations were drawn from nitrate leachability data obtained in the course of the Parts 2 and 3 waste form performance testing. The nitrate leachability index results are presented along with other data from the applicable activity categories.

  15. Wireless Roadside Inspection Proof of Concept Test Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Capps, Gary J [ORNL; Franzese, Oscar [ORNL; Knee, Helmut E [ORNL; Plate, Randall S [ORNL; Lascurain, Mary Beth [ORNL

    2009-03-01

    The U.S. Department of Transportation (DOT) FMCSA commissioned the Wireless Roadside Inspection (WRI) Program to validate technologies and methodologies that can improve safety through inspections using wireless technologies that convey real-time identification of commercial vehicles, drivers, and carriers, as well as information about the condition of the vehicles and their drivers. It is hypothesized that these inspections will: -- Increase safety -- Decrease the number of unsafe commercial vehicles on the road; -- Increase efficiency -- Speed up the inspection process, enabling more inspections to occur, at least on par with the number of weight inspections; -- Improve effectiveness -- Reduce the probability of drivers bypassing CMV inspection stations and increase the likelihood that fleets will attempt to meet the safety regulations; and -- Benefit industry -- Reduce fleet costs, provide good return-on-investment, minimize wait times, and level the playing field. The WRI Program is defined in three phases which are: Phase 1: Proof of Concept Test (POC) Testing of commercially available off-the-shelf (COTS) or near-COTS technology to validate the wireless inspection concept. Phase 2: Pilot Test Safety technology maturation and back office system integration Phase 3: Field Operational Test Multi-vehicle testing over a multi-state instrumented corridor This report focuses on Phase 1 efforts that were initiated in March, 2006. Technical efforts dealt with the ability of a Universal Wireless Inspection System (UWIS) to collect driver, vehicle, and carrier information; format a Safety Data Message Set from this information; and wirelessly transmit a Safety Data Message Set to a roadside receiver unit or mobile enforcement vehicle.

  16. Final report proficiency test on the determination of α, β and γ-emitting radionuclides

    International Nuclear Information System (INIS)

    Shakhashiro, A.; Trinkl, A.; Benesch, T.; Sansone, U.

    2005-06-01

    A proficiency test on the determination of α, β and γ-emitting radionuclides was organised within the frame of the Technical Cooperation project: RAS/9/024 'Environmental Radiation Monitoring and Regional Data Base' to evaluate the analytical performance of 14 laboratories from 12 Asian countries. This report summarises the performance evaluation of the participating laboratories. Analytical data evaluation of this proficiency test showed that 58% of all reported results obtained a 'Passed' final score for both the trueness and precision criteria applied to this exercise. (author)

  17. 76 FR 2336 - Dynamic Random Access Memory Semiconductors From the Republic of Korea: Final Results of...

    Science.gov (United States)

    2011-01-13

    ... Semiconductors From the Republic of Korea: Final Results of Countervailing Duty Administrative Review AGENCY... administrative review of the countervailing duty order on dynamic random access memory semiconductors from the... to a change in the net subsidy rate. The final net subsidy rate for Hynix Semiconductor, Inc. is...

  18. 78 FR 9884 - Purified Carboxymethylcellulose From the Netherlands: Final Results of Antidumping Duty...

    Science.gov (United States)

    2013-02-12

    ... Carboxymethylcellulose From the Netherlands: Final Results of Antidumping Duty Administrative Review and Final No... carboxymethylcellulose (purified CMC) from the Netherlands.\\1\\ This review covers two respondents, Akzo Nobel Functional... Review'' section of this notice. \\1\\ See Purified Carboxymethylcellulose From the Netherlands...

  19. Radiation Tolerance Qualification Tests of the Final Source Interface Unit for the ALICE Experiment

    CERN Document Server

    Dénes, E; Futó, E; Kerék, A; Kiss, T; Molnár, J; Novák, D; Soós, C; Tölyhi, T; Van de Vyvre, P

    2007-01-01

    The ALICE Detector Data Link (DDL) is a high-speed optical link designed to interface the readout electronics of ALICE sub-detectors to the DAQ computers. The Source Interface Unit (SIU) of the DDL will operate in radiation environment. Previous tests showed that a configuration loss of SRAM-based FPGA devices may happen and the frequency of undetected data errors in the FPGA user memory area is also not acceptable. Therefore, we redesigned the SIU card using another FPGA based on flash technology. In order to detect bit errors in the user memory we added parity check logic to the design. The new SIU has been extensively tested using neutron and proton irradiation to verify its radiation tolerance. In this paper we summarize the design changes, introduce the final design, and the results of the radiation tolerance measurements on the final card.

  20. Supercritical water oxidation data acquisition testing. Final report, Volume II

    International Nuclear Information System (INIS)

    1996-11-01

    Supercritical Water Oxidation (SCWO) technology holds great promise for treating mixed wastes, in an environmentally safe and efficient manner. In the spring of 1994 the US Department of Energy (DOE), Idaho Operations Office awarded Stone ampersand Webster Engineering Corporation, of Boston Massachusetts and its sub-contractor MODAR, Inc. of Natick Massachusetts a Supercritical Water Oxidation Data Acquisition Testing (SCWODAT) program. The SCWODAT program was contracted through a Cooperative Agreement that was co-funded by the US Department of Energy and the Strategic Environmental Research and Development Program. The SCWODAT testing scope outlined by the DOE in the original Cooperative Agreement and amendments thereto was initiated in June 1994 and successfully completed in December 1995. The SCWODAT program provided further information and operational data on the effectiveness of treating both simulated mixed waste and typical Navy hazardous waste using the MODAR SCWO technology

  1. NMSBA: Aken Technologies Final Report: Toxicity Testing of Liquidoff

    Energy Technology Data Exchange (ETDEWEB)

    Ruffing, Anne [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Jensen, Travis [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Strickland, Lucas [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-02-01

    To determine the effect of Liquidoff on bacteria, three bacterial strains were tested: Escherichia coli DH5α, Synechococcus sp. PCC 7002, and Synechococcus elongatus PCC 7942. E. coli DH5α is a Gram-negative, aerobic bacterium that is often found in normal gut flora and is commonly used the laboratory due to its fast growth rate. Synechococcus sp. PCC 7002 and S. elongatus PCC 7942 are Gram-negative, aquatic, autophototrophic cyanobacteria. Synechococcus sp. PCC 7002 is a marine cyanobacterium isolated from ‘fish pens’ on Magueyes Island, Puerto Rico in 1962, while S. elongatus PCC 7942 is a freshwater cyanobacterium. It should be noted that no Gram-positive bacterium was tested in this study.

  2. Cooperative field test program for wind systems. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Bollmeier, W.S. II; Dodge, D.M.

    1992-03-01

    The objectives of the Federal Wind Energy Program, managed by the US Department of Energy (DOE), are (1) to assist industry and utilities in achieving a multi-regional US market penetration of wind systems, and (2) to establish the United States as the world leader in the development of advanced wind turbine technology. In 1984, the program conducted a series of planning workshops with representatives from the wind energy industry to obtain input on the Five-Year Research Plan then being prepared by DOE. One specific suggestion that came out of these meetings was that the federal program should conduct cooperative research tests with industry to enhance the technology transfer process. It was also felt that the active involvement of industry in DOE-funded research would improve the state of the art of wind turbine technology. DOE established the Cooperative Field Test Program (CFTP) in response to that suggestion. This program was one of the first in DOE to feature joint industry-government research test teams working toward common objectives.

  3. Expose : procedure and results of the joint experiment verification tests

    Science.gov (United States)

    Panitz, C.; Rettberg, P.; Horneck, G.; Rabbow, E.; Baglioni, P.

    The International Space Station will carry the EXPOSE facility accommodated at the universal workplace URM-D located outside the Russian Service Module. The launch will be affected in 2005 and it is planned to stay in space for 1.5 years. The tray like structure will accomodate 2 chemical and 6 biological PI-experiments or experiment systems of the ROSE (Response of Organisms to Space Environment) consortium. EXPOSE will support long-term in situ studies of microbes in artificial meteorites, as well as of microbial communities from special ecological niches, such as endolithic and evaporitic ecosystems. The either vented or sealed experiment pockets will be covered by an optical filter system to control intensity and spectral range of solar UV irradiation. Control of sun exposure will be achieved by the use of individual shutters. To test the compatibility of the different biological systems and their adaptation to the opportunities and constraints of space conditions a profound ground support program has been developed. The procedure and first results of this joint Experiment Verification Tests (EVT) will be presented. The results will be essential for the success of the EXPOSE mission and have been done in parallel with the development and construction of the final hardware design of the facility. The results of the mission will contribute to the understanding of the organic chemistry processes in space, the biological adaptation strategies to extreme conditions, e.g. on early Earth and Mars, and the distribution of life beyond its planet of origin.

  4. Aluminized film, seam sealing tests and observations. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-16

    The purpose of this work was to investigate various seam sealing techniques, reinforcing methods, fitting installations, seam tolerances and geometric configurations pertinent to an aluminized plastic laminate. The program seeks a successful fabricating method for producing low-diffusion, cylindrical, spar liners to contain pressurized GH{sub 2} and GO{sub 2}. The test plan included: (1) seaming techniques on metallized Mylar film; (2) ``double patches`` for end fittings; (3) stainless steel bulkhead fitting assembly with seals; (4) minimum run tolerance on linear shear seam; (5) peel seam vs. inverted seal seam fabrication.

  5. GSDO Program Hexavalent Chrome Alternatives: Final Pretreatments Test Report

    Science.gov (United States)

    Kessel, Kurt

    2013-01-01

    Hexavalent chrome free pretreatments should be considered for use on Ground Support Equipment (OSE) and Electrical Ground Support Equipment (EOSE). Both of the hexavalent chrome free pretreatments (Metalast TCP HF and SurTec 650C) evaluated by this project met, and in some instances exceeded, the requirements ofMIL-DTL-5541 "Chemical Conversion Coatings on Aluminum and Aluminum Alloys". For DC resistance measurements, both Metalast TCP HF and SurTec (!50C met initial requirements following assembly and in many cases continued to maintain passing readings for the duration of testing.

  6. AGR 3/4 Irradiation Test Final As Run Report

    Energy Technology Data Exchange (ETDEWEB)

    Collin, Blaise P. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-06-01

    Several fuel and material irradiation experiments have been planned for the Idaho National Laboratory Advanced Reactor Technologies Technology Development Office Advanced Gas Reactor Fuel Development and Qualification Program (referred to as the INL ART TDO/AGR fuel program hereafter), which supports the development and qualification of tristructural-isotropic (TRISO) coated particle fuel for use in HTGRs. The goals of these experiments are to provide irradiation performance data to support fuel process development, qualify fuel for normal operating conditions, support development and validation of fuel performance and fission product transport models and codes, and provide irradiated fuel and materials for post irradiation examination and safety testing (INL 05/2015). AGR-3/4 combined the third and fourth in this series of planned experiments to test TRISO coated low enriched uranium (LEU) oxycarbide fuel. This combined experiment was intended to support the refinement of fission product transport models and to assess the effects of sweep gas impurities on fuel performance and fission product transport by irradiating designed-to-fail fuel particles and by measuring subsequent fission metal transport in fuel-compact matrix material and fuel-element graphite. The AGR 3/4 fuel test was successful in irradiating the fuel compacts to the burnup and fast fluence target ranges, considering the experiment was terminated short of its initial 400 EFPD target (Collin 2015). Out of the 48 AGR-3/4 compacts, 42 achieved the specified burnup of at least 6% fissions per initial heavy-metal atom (FIMA). Three capsules had a maximum fuel compact average burnup < 10% FIMA, one more than originally specified, and the maximum fuel compact average burnup was <19% FIMA for the remaining capsules, as specified. Fast neutron fluence fell in the expected range of 1.0 to 5.5×1025 n/m2 (E >0.18 MeV) for all compacts. In addition, the AGR-3/4 experiment was globally successful in keeping the

  7. Do continuous assessment results affect final exam outcomes? Evidence from a microeconomics course

    Directory of Open Access Journals (Sweden)

    Juan Carlos Reboredo

    2017-04-01

    Full Text Available Continuous assessment aims to enhance student learning and understanding of a subject and so achieve better educational outcomes. We investigated how continuous assessment grades affected final exam grades. Using a dataset for six academic post-Bologna Process years (2009-2015 for a first-year undergraduate microeconomics course offered at a Spanish public university, we examined conditional dependence between continuous assessment and final exam grades. Our results would indicate a limited contribution of continuous assessment results to final exam results: the probability of the final exam performance improving on the continuous assessment grade was lower than the probability of the opposite occurring. A consistent exception, however, was students who obtained an A grade for continuous assessment. Our results would cast some doubt on the beneficial effects of continuous assessment advocated by the Bologna Process.

  8. Communicating radon risk effectively: Radon testing in Maryland. Final report

    International Nuclear Information System (INIS)

    Desvousges, W.H.; Smith, V.K.; Rink, H.H.

    1988-10-01

    Two sets of materials and corresponding delivery strategies for communicating radon risk were evaluated, compared with a 'no-special-treatment' strategy in a comparison community. One community received radio public-service announcements and utility bill inserts. The second received these plus posters, local government sponsorship of a radon awareness week, and local slide presentations. The most-intensive efforts (multiple channels, multiple hits) were more effective than the less intensive effort, which had little impact compared with no special treatment. From a marketing perspective, the effort was very successful, increasing the share of homeowners who tested for radon from 5% to 15%. This may not be viewed as sufficiently effective from a public-health perspective, however

  9. Final project report: High energy rotor development, test and evaluation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-01

    Under the auspices of the {open_quotes}Government/Industry Wind Technology Applications Project{close_quotes} [{open_quotes}Letter of Interest{close_quotes} (LOI) Number RC-1-11101], Flo Wind Corp. has successfully developed, tested, and delivered a high-energy rotor upgrade candidate for their 19-meter Vertical Axis Wind Turbine. The project included the demonstration of the innovative extended height-to-diameter ratio concept, the development of a continuous span single-piece composite blade, the demonstration of a continuous blade manufacturing technique, the utilization of the Sandia National Laboratories developed SNLA 2150 natural laminar flow airfoil and the reuse of existing wind turbine and wind power plant infrastructure.

  10. Engine testing of ceramic cam-roller followers. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Kalish, Y. [Detroit Diesel Corp., MI (United States)

    1992-04-01

    For several years, DDC has been developing monolithic ceramic heat engine components. One of the components, developed for an application in our state-of-the-art on-highway, heavy-duty diesel engine, the Series 60, is a silicon nitride cam-roller follower. Prior to starting this program, each valve train component in the Series 60 was considered for conversion to a ceramic material. Many advantages and disadvantages (benefits and risks) were considered. From this effort, one component was selected, the cam-roller follower. Using a system design approach, a ceramic cam-roller follower offered functional improvement at a reasonable cost. The purpose of the project was to inspect and test 100 domestically produced silicon nitride cam-roller followers built to the requirements of the DDC series 60 engine.

  11. Qualitative pre-test of Energy Star advertising : final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-01-01

    Natural Resources Canada launched a print advertising campaign and one 30-second television commercial to promote the Energy Star symbol and to acquaint the public with the program that identifies energy efficient products that reduce energy use, save money and reduce greenhouse gas emissions that contribute to climate change. The Communications Branch of Natural Resources Canada wanted to pre-test the television and print ads. Each print ad focused on a particular product category, including home comfort, appliances, electronics and office equipment. The qualitative research methodology was used in the pre-testing because it is the best learning tool for understanding the range and depth of reactions toward a subject at any given time. The findings were not quantifiable because they are not representative of the population at large. Ten focus groups were surveyed in January 2003 in 5 Canadian centres with a total of 83 participants aged 18 to 54. The target groups included people who were informed about climate change issues as well as those who were note. Participants were questioned about the Energy Star Product. Findings were consistent across all 5 locations. There was some general awareness of EnerGuide on appliances in all groups, but generally a low awareness of the Energy Star symbol. Most people did not place energy efficiency as a high priority when purchasing appliances. This report presented the main findings of attitudes towards climate change, Kyoto and energy efficiency. The reaction to the television and print ads was also included along with opinions regarding their main weaknesses and strengths. Some recommendations for improvement were also included. Samples of the print advertisements were included in both English and French. tabs., figs.

  12. Interpreting Results from the Standardized UXO Test Sites

    National Research Council Canada - National Science Library

    May, Michael; Tuley, Michael

    2007-01-01

    ...) and the Environmental Security Technology Certification Program (ESCTP) to complete a detailed analysis of the results of testing carried out at the Standardized Unexploded Ordnance (UXO) Test Sites...

  13. Fast Flux Test Facility performance monitoring management information: [Final report

    International Nuclear Information System (INIS)

    Newland, D.J.

    1987-09-01

    The purpose of this report is to provide management with performance data on key performance indicators for the month of July, 1987. This report contains the results for key performance indicators divided into two categories of ''overall'' and ''other''. The ''overall'' performance indicators, when considered in the aggregate, provide one means of monitoring overall plant performance

  14. Final report of fuel dynamics Test E7

    International Nuclear Information System (INIS)

    Doerner, R.C.; Murphy, W.F.; Stanford, G.S.; Froehle, P.H.

    1977-04-01

    Test data from an in-pile failure experiment of high-power LMFBR-type fuel pins in a simulated $3/s transient-overpower (TOP) accident are reported and analyzed. Major conclusions are that (1) a series of cladding ruptures during the 100-ms period preceding fuel release injected small bursts of fission gas into the flow stream; (2) gas release influenced subsequent cladding melting and fuel release [there were no measurable FCI's (fuel-coolant interactions), and all fuel motion observed by the hodoscope was very slow]; (3) the predominant postfailure fuel motion appears to be radial swelling that left a spongy fuel crust on the holder wall; (4) less than 4 to 6 percent of the fuel moved axially out of the original fuel zone, and most of this froze within a 10-cm region above the original top of the fuel zone to form the outlet blockage. An inlet blockage approximately 1 cm long was formed and consisted of large interconnected void regions. Both blockages began just beyond the ends of the fuel pellets

  15. Photocatalytic pavement blocks. Air purification by pavement blocks. Final results of the research at BRRC

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-01

    The use of materials can influence to a large extent the environmental impact of traffic and of road infrastructure. Especially in urban areas, where the risk on smog formation during hot summer days is high, the use of photocatalytic pavement blocks can reduce the air pollution significantly. A project on environmental friendly concrete pavement blocks is conducted at the Belgian Road Research Centre. The use of photocatalytic material in the surface of pavement blocks to obtain air purifying materials is investigated. In contact with light, TiO2 as photocatalyst, is able to reduce the NO and NO2 content in the air, caused by the exhaust of traffic. The efficiency is tested on pavement blocks, but the technique can as well be applied on other road elements (e.g. noise reducing walls, linear elements) or as a coating on new materials or existing structures. At the previous TRA conference in Gotenborgh, Sweden, the principle of photocatalysis was presented. In this paper, emphasis will be put on the final results of the 4-year project obtained in laboratory as well as on site at the Leien of Antwerp (10,000 m{sup 2}). The results indicate a durable efficiency towards NOx reduction, which is in favour for the diminishing of the risk on ozone formation. However, the precise translation from the laboratory towards the site is still in question. The results obtained during the project are discussed in this paper.

  16. Photocatalytic pavement blocks. Air purification by pavement blocks. Final results of the research at BRRC

    International Nuclear Information System (INIS)

    2009-01-01

    The use of materials can influence to a large extent the environmental impact of traffic and of road infrastructure. Especially in urban areas, where the risk on smog formation during hot summer days is high, the use of photocatalytic pavement blocks can reduce the air pollution significantly. A project on environmental friendly concrete pavement blocks is conducted at the Belgian Road Research Centre. The use of photocatalytic material in the surface of pavement blocks to obtain air purifying materials is investigated. In contact with light, TiO2 as photocatalyst, is able to reduce the NO and NO2 content in the air, caused by the exhaust of traffic. The efficiency is tested on pavement blocks, but the technique can as well be applied on other road elements (e.g. noise reducing walls, linear elements) or as a coating on new materials or existing structures. At the previous TRA conference in Gotenborgh, Sweden, the principle of photocatalysis was presented. In this paper, emphasis will be put on the final results of the 4-year project obtained in laboratory as well as on site at the Leien of Antwerp (10,000 m 2 ). The results indicate a durable efficiency towards NOx reduction, which is in favour for the diminishing of the risk on ozone formation. However, the precise translation from the laboratory towards the site is still in question. The results obtained during the project are discussed in this paper

  17. Smart Infrared Inspection System Field Operational Test Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Siekmann, Adam [ORNL; Capps, Gary J [ORNL; Franzese, Oscar [ORNL; Lascurain, Mary Beth [ORNL

    2011-06-01

    The Smart InfraRed Inspection System (SIRIS) is a tool designed to assist inspectors in determining which vehicles passing through the SIRIS system are in need of further inspection by measuring the thermal data from the wheel components. As a vehicle enters the system, infrared cameras on the road measure temperatures of the brakes, tires, and wheel bearings on both wheel ends of commercial motor vehicles (CMVs) in motion. This thermal data is then presented to enforcement personal inside of the inspection station on a user friendly interface. Vehicles that are suspected to have a violation are automatically alerted to the enforcement staff. The main goal of the SIRIS field operational test (FOT) was to collect data to evaluate the performance of the prototype system and determine the viability of such a system being used for commercial motor vehicle enforcement. From March 2010 to September 2010, ORNL facilitated the SIRIS FOT at the Greene County Inspection Station (IS) in Greeneville, Tennessee. During the course of the FOT, 413 CMVs were given a North American Standard (NAS) Level-1 inspection. Of those 413 CMVs, 384 were subjected to a SIRIS screening. A total of 36 (9.38%) of the vehicles were flagged by SIRIS as having one or more thermal issues; with brakes issues making up 33 (91.67%) of those. Of the 36 vehicles flagged as having thermal issues, 31 (86.11%) were found to have a violation and 30 (83.33%) of those vehicles were placed out-of-service (OOS). Overall the enforcement personnel who have used SIRIS for screening purposes have had positive feedback on the potential of SIRIS. With improvements in detection algorithms and stability, the system will be beneficial to the CMV enforcement community and increase overall trooper productivity by accurately identifying a higher percentage of CMVs to be placed OOS with minimal error. No future evaluation of SIRIS has been deemed necessary and specifications for a production system will soon be drafted.

  18. Final report on graphite irradiation test OG-2

    International Nuclear Information System (INIS)

    Price, R.J.; Beavan, L.A.

    1975-01-01

    Results are presented of dimensional, thermal expansivity, thermal conductivity, Young's modulus, and tensile strength measurements on specimens of nuclear graphites irradiated in capsule OG-2. About half the irradiation space was allocated to H-451 near-isotropic petroleum-coke-based graphite or its subsized prototype grade H-429. Most of these specimens had been previously irradiated. Virgin specimens of another near-isotropic graphite, grade TS-1240, were irradiated. Some previously irradiated specimens of needle-coke-based H-327 graphite and pitch-coke-based P 3 JHAN were also included

  19. Test of job performance aids for power plants. Final report

    International Nuclear Information System (INIS)

    Shriver, E.L.; Zach, S.E.; Foley, J.P. Jr.

    1982-10-01

    The objective of EPRI Research Project 1396-1 was to evaluate the applicability and effectiveness of Job Performance Aids (JPAs) in nuclear power plant situations. For over twenty years, JPAs have been developed in military situations to meet the problems of confusing, incomplete, and inaccurate procedures on maintenance jobs. Kinton, Incorporated of Alexandria, Virginia applied the military experience with JPAs to nuclear power plant situations and identified potential benefits in terms of cost reductions and improved performance. Sample JPAs were developed for Control Room Operations, Maintenance, Plant Operations, Instrumentation and Control, Health Physics, and Quality Assurance tasks (procedures) in selected nuclear plants. JPAs were also developed for a prototype condenser tube leak detection system in the design stage, as well as for generic classes of circuit breaker equipment. Based on the results of the study, the use of JPAs is recommended for plant procedures of medium to high difficulty and for those tasks performed infrequently, even if fairly simple

  20. SLAC FASTBUS Snoop Module: test results and support software

    International Nuclear Information System (INIS)

    Gustavson, D.B.; Walz, H.V.

    1985-09-01

    The development of a diagnostic module for FASTBUS has been completed. The Snoop Module is designed to reside on a Crate Segment and provide high-speed diagnostic monitoring and testing capabilities. Final hardware details and testing of production prototype modules are reported. Features of software under development for a stand-alone single Snoop diagnostic system and Multi-Snoop networks will be discussed. 3 refs., 2 figs

  1. Development of Test-Analysis Models (TAM) for correlation of dynamic test and analysis results

    Science.gov (United States)

    Angelucci, Filippo; Javeed, Mehzad; Mcgowan, Paul

    1992-01-01

    The primary objective of structural analysis of aerospace applications is to obtain a verified finite element model (FEM). The verified FEM can be used for loads analysis, evaluate structural modifications, or design control systems. Verification of the FEM is generally obtained as the result of correlating test and FEM models. A test analysis model (TAM) is very useful in the correlation process. A TAM is essentially a FEM reduced to the size of the test model, which attempts to preserve the dynamic characteristics of the original FEM in the analysis range of interest. Numerous methods for generating TAMs have been developed in the literature. The major emphasis of this paper is a description of the procedures necessary for creation of the TAM and the correlation of the reduced models with the FEM or the test results. Herein, three methods are discussed, namely Guyan, Improved Reduced System (IRS), and Hybrid. Also included are the procedures for performing these analyses using MSC/NASTRAN. Finally, application of the TAM process is demonstrated with an experimental test configuration of a ten bay cantilevered truss structure.

  2. Cryogenic Orbital Testbed (CRYOTE) Ground Test Article, Final Report

    Science.gov (United States)

    Johnson, Wesley L.; Rhys, Noah O.; Bradley, David E.; Wollen, Mark; Kutter, Bernard; Gravlee, Mari; Walls, Laurie K.

    2015-01-01

    Liquid propulsion has been used since Robert Goddard started developing a liquid oxygen (LO2) and gasoline powered rocket and fired it in 1923 (Ref. 1). In the following decades engineers settled on the combination of liquid hydrogen (LH2) and LO2 as the most efficient propellant combination for in-space travel. Due to their low temperatures (LH2 at 20 K and LO2 at 90 K), they require special handling and procedures. General Dynamics began developing LO2 and LH2 upper stages in 1956 in the form of Centaur, these efforts were soon funded by the Department of Defense in conjunction with NASA (beginning in 1958) (Ref. 2). Meanwhile NASA also worked with McDonnell Douglas to develop the SIV-B stage for the Saturn V rocket. In the subsequent years, the engineers were able to push the Centaur to up to 9 hr of orbital lifetime and the SIV-B to up to 6 hr. Due to venting the resultant boil-off from the high heat loads through the foam insulation on the upper stages, both vehicles remained in a settled configuration throughout the flights, thus the two phases of propellant (liquid and vapor) were separated at a known location. The one exception to this were the Titan/Centaur missions, which thanks to the lower boil-off using three layers of multilayer insulation (MLI), were able to coast unsettled for up to 5.25 hr during direct geosynchronous orbit insertion missions. In the years since there has been a continuous effort to extend the life of these upper stages from hours to days or even months.

  3. Final report on graphite irradiation test OG-3

    International Nuclear Information System (INIS)

    Price, R.J.; Beavan, L.A.

    1977-01-01

    The results of dimensional, thermal expansivity, thermal conductivity, Young's modulus, and tensile strength measurements on graphite specimens irradiated in capsule OG-3 are presented. The graphite grades investigated included near-isotropic H-451 (three different preproduction lots), TS-1240, and SO818; needle coke H-327; and European coal tar pitch coke grades P 3 JHA 2 N, P 3 JHAN, and ASI2-500. Data were obtained in the temperature range 823 0 K to 1673 0 K. The peak fast neutron fluence in the experiment was 3 x 10 25 n/m 3 (E greater than 29 fJ)/sub HTGR/; the total accumulated fluence exceeded 9 x 10 25 n/m 2 on some H-451 specimens and 6 x 10 25 n/m 2 on some TS-1240 specimens. Irradiation-induced dimensional changes on H-451 graphite differed slightly from earlier predictions. For an irradiation temperature of about 1225 0 K, axial shrinkage rates at high fluences were somewhat higher than predicted, and the fluence at which radial expansion started (about 9 x 10 25 n/m 2 at 1275 0 K) was lower. TS-1240 graphite underwent smaller dimensional changes than H-451 graphite, while limited data on SO818 and ASI2-500 graphites showed similar behavior to H-451. P 3 JHAN and P 3 JHA 2 N graphites displayed anisotropic behavior with rapid axial shrinkage. Comparison of dimensional changes between specimens from three logs of H-451 and of TS-1240 graphites showed no significant log-to-log variations for H-451, and small but significant log-to-log variations for TS-1240. The thermal expansivity of the near-isotropic graphites irradiated at 865-1045 0 K first increased by 5 percent to 10 percent and then decreased. At higher irradiation temperatures the thermal expansivity decreased by up to 50 percent. Changes in thermal conductivity were consistent with previously established curves. Specimens which were successively irradiated at two different temperatures took on the saturation conductivity for the new temperature

  4. Final design of the neutral beam lines for the Tokamak Fusion Test Reactor

    International Nuclear Information System (INIS)

    Pittenger, L.C.; Valby, L.E.; Stone, R.R.; Pedrotti, L.R.; Denhoy, B.; Yoard, R.

    1979-01-01

    Final design of the neutral beam lines for TFTR has been completed. A prototype has been assembled at Lawrence Berkeley Laboratory and is undergoing testing as part of the Neutral Beam System Test Facility (NBSTF). The final neutral beam line (NBL) configuration differs in several details from that previously reported upon; certain components have been added; and testing of the cryopump system has led to some design simplification. It is these developments which are reported herein

  5. HTR 500: Final report of the project '' uniaxial creep tests at controlled temperature''

    International Nuclear Information System (INIS)

    1992-03-01

    The report presents the results of creep trials with HTR-concrete, which were carried out in the scope of development of prestressed concrete - reactor pressure vessels at the ETH Lausanne Institute for Steel and Prestressed Concrete. With temperature, an increase of creep and shrinkage was observed, a lesser dependence on exhaustion and type of concrete. The point in time of reaching the final value is not dependent on temperature for creep, but is for shrinkage. The modulus of elasticity depends on the temperature pre-treatment, but only insignificantly on the test temperature. figs., tabs

  6. 75 FR 62763 - Ball Bearings and Parts Thereof From Germany: Amended Final Results of Antidumping Duty...

    Science.gov (United States)

    2010-10-13

    ...On July 7, 2010, the United States Court of International Trade (CIT) sustained the Department of Commerce's (the Department) results of redetermination on remand concerning the final results of the administrative review of the antidumping duty order on ball bearings and parts thereof from Germany. See SKF USA Inc. v. United States, Slip Op. 10-76 (CIT 2010). The Department is amending the final results of the administrative review of the antidumping duty order on ball bearings and parts thereof from Germany covering the period of review May 1, 2006, through April 30, 2007, to reflect the CIT's order.

  7. Computer-aided dispatch--traffic management center field operational test final detailed test plan : WSDOT deployment

    Science.gov (United States)

    2003-10-01

    The purpose of this document is to expand upon the evaluation components presented in "Computer-aided dispatch--traffic management center field operational test final evaluation plan : WSDOT deployment". This document defines the objective, approach,...

  8. Computer-aided dispatch--traffic management center field operational test final test plans : state of Utah

    Science.gov (United States)

    2004-01-01

    The purpose of this document is to expand upon the evaluation components presented in "Computer-aided dispatch--traffic management center field operational test final evaluation plan : state of Utah". This document defines the objective, approach, an...

  9. Relationship between ultrasonic pulse velocity test result and ...

    African Journals Online (AJOL)

    Ultrasonic Pulse Velocity test result showed an inverse relationship (of -0.935) with the crushed concrete compressive strength. Correlation test, multiple regression analysis, graphs and visual inspection were used to analyze the results. The conclusion drawn is that there exists a relationship between UPV test results and ...

  10. Mathematics Placement Test: Typical Results with Unexpected Outcomes

    Science.gov (United States)

    Ingalls, Victoria

    2011-01-01

    Based on the results of a prior case-study analysis of mathematics placement at one university, the mathematics department developed and piloted a mathematics placement test. This article describes the implementation process for a mathematics placement test and further analyzes the test results for the pilot group. As an unexpected result, the…

  11. 76 FR 67146 - Certain Preserved Mushrooms From the People's Republic of China: Final Results of Antidumping...

    Science.gov (United States)

    2011-10-31

    ... DEPARTMENT OF COMMERCE International Trade Administration [A-570-851] Certain Preserved Mushrooms... results of the new shipper reviews (NSRs) of the antidumping duty order on certain preserved mushrooms.... (Hongda) in the Final Results of New Shipper Review of the Antidumping Duty Order on Preserved Mushrooms...

  12. 78 FR 56860 - Honey From the People's Republic of China: Final Results of Antidumping Duty Administrative...

    Science.gov (United States)

    2013-09-16

    ... (``Preliminary Results''). DATES: Effective Date: September 16, 2013. FOR FURTHER INFORMATION CONTACT: Emeka... and rice syrup, regardless of the percentage of honey contained in the blend. PRC-Wide Entity In the... CBP 15 days after the date of publication of these final results of review. The Department recently...

  13. 75 FR 74684 - Notice of Final Results of Antidumping Duty Changed Circumstances Review: Certain Frozen...

    Science.gov (United States)

    2010-12-01

    ...., Limited (A Foods) is the successor-in-interest to May Ao Company Limited (May Ao) for purposes of... requested a public hearing to discuss, the Initiation and Preliminary Results. For these final results, the... with an opportunity to comment or request a public hearing regarding our finding that A Foods is the...

  14. Irradiation effects test series, test IE-5. Test results report. [PWR

    Energy Technology Data Exchange (ETDEWEB)

    Croucher, D. W.; Yackle, T. R.; Allison, C. M.; Ploger, S. A.

    1978-01-01

    Test IE-5, conducted in the Power Burst Facility at the Idaho National Engineering Laboratory, employed three 0.97-m long pressurized water reactor type fuel rods, fabricated from previously irradiated zircaloy-4 cladding and one similar rod fabricated from unirradiated cladding. The objectives of the test were to evaluate the influence of simulated fission products, cladding irradiation damage, and fuel rod internal pressure on pellet-cladding interaction during a power ramp and on fuel rod behavior during film boiling operation. The four rods were subjected to a preconditioning period, a power ramp to an average fuel rod peak power of 65 kW/m, and steady state operation for one hour at a coolant mass flux of 4880 kg/s-m/sup 2/ for each rod. After a flow reduction to 1800 kg/s-m/sup 2/, film boiling occurred on one rod. Additional flow reductions to 970 kg/s-m/sup 2/ produced film boiling on the three remaining fuel rods. Maximum time in film boiling was 80s. The rod having the highest initial internal pressure (8.3 MPa) failed 10s after the onset of film boiling. A second rod failed about 90s after reactor shutdown. The report contains a description of the experiment, the test conduct, test results, and results from the preliminary postirradiation examination. Calculations using a transient fuel rod behavior code are compared with the test results.

  15. New test methods for BIPV. Results from IP performance

    International Nuclear Information System (INIS)

    Jol, J.C.; Van Kampen, B.J.M.; De Boer, B.J.; Reil, F.; Geyer, D.

    2009-11-01

    Within the Performance project new test procedures for PV building products and the building performance as a whole when PV is applied in buildings have been drafted. It has resulted in a first draft of new test procedures for PV building products and proposals for tests for novel BIPV technology like thin film. The test proposed are a module breakage test for BIPV products, a fire safety test for BIPV products and a dynamic load test for BIPV products. Furthermore first proposals of how flexible PV modules could be tested in an appropriate way to ensure long time quality and safety of these new products are presented.

  16. Legal provisions governing the acknowledgment of test results

    International Nuclear Information System (INIS)

    Strecker, A.

    1982-01-01

    The legal provisions governing the acknowledgment of test results are most frequently applied by administrative orders (design and qualification approvals or specimen testing and approval) and are thus claimable and voidable in accordance with general administrative law. The acknowledgment of test certificates requires a legal basis. Test results, however, can be acknowledged also by administrative bodies. Recently, the Federal Government began to delegate more of its legal authority in this field to private institutions, allowing test results to be acknowledged and test certificates to be issued by government controlled private institutions. (orig.) [de

  17. Spent fuel sabotage test program, characterization of aerosol dispersal : interim final report

    International Nuclear Information System (INIS)

    Gregson, Michael Warren; Brockmann, John E.; Loiseau, Olivier; Klennert, Lindsay A.; Nolte, Oliver; Molecke, Martin Alan; Autrusson, Bruno A.; Koch, Wolfgang; Pretzsch, Gunter Guido; Brucher, Wenzel; Steyskal, Michele D.

    2008-01-01

    This multinational, multi-phase spent fuel sabotage test program is quantifying the aerosol particles produced when the products of a high energy density device (HEDD) interact with and explosively particulate test rodlets that contain pellets of either surrogate materials or actual spent fuel. This program provides source-term data that are relevant to plausible sabotage scenarios in relation to spent fuel transport and storage casks and associated risk assessments. We present details and significant results obtained from this program from 2001 through 2007. Measured aerosol results include: respirable fractions produced; amounts, nuclide content, and produced particle size distributions and morphology; measurements of volatile fission product species enhanced sorption--enrichment factors onto respirable particles; and, status on determination of the spent fuel ratio, SFR, needed for scaling studies. Emphasis is provided on recent Phase 3 tests using depleted uranium oxide pellets plus non-radioactive fission product dopants in surrogate spent fuel test rodlets, plus the latest surrogate cerium oxide results and aerosol laboratory supporting calibration work. The DUO 2 , CeO 2 , plus fission product dopant aerosol particle results are compared with available historical data. We also provide a status review on continuing preparations for the final Phase 4 in this program, tests using individual short rodlets containing actual spent fuel from U.S. PWR reactors, with both high- and lower-burnup fuel. The source-term data, aerosol results, and program design have been tailored to support and guide follow-on computer modeling of aerosol dispersal hazards and radiological consequence assessments. This spent fuel sabotage, aerosol test program was performed primarily at Sandia National Laboratories, with support provided by both the U.S. Department of Energy and the Nuclear Regulatory Commission. This program has significant input from, and is cooperatively supported and

  18. Preliminary irradiation test results from the Yankee Atomic Electric Company reactor vessel test irradiation program

    International Nuclear Information System (INIS)

    Biemiller, E.C.; Fyfitch, S.; Campbell, C.A.

    1993-01-01

    The Yankee Atomic Electric Company test irradiation program was implemented to characterize the irradiation response of representative Yankee Rowe reactor vessel beltline plate materials and to remove uncertainties in the analysis of existing irradiation data on the Yankee Rowe reactor vessel steel. Plate materials each containing 0.24 w/o copper, but different nickel contents at 0.63 w/o and 0.19 w/o, were heat treated to simulate the Yankee vessel heat treatment (austenitized at 1800 deg F) and to simulate Regulatory Guide 1.99 database materials (austenitized at 1600 deg. F). These heat treatments produced different microstructures so the effect of microstructure on irradiation damage sensitivity could be tested. Because the nickel content of the test plates varied and the copper level was constant, the effect of nickel on irradiation embrittlement was also tested. Correlation monitor material, HSST-02, was included in the program to benchmark the Ford Nuclear Reactor (U. of Michigan Test Reactor) which had never been used for this type of irradiation program. Materials taken from plate surface locations (vs. 1/4T) were included to test whether or not the improved toughness properties of the plate surface layer, resulting from the rapid quench, is maintained after irradiation. If the improved properties are maintained, pressurized thermal shock calculations could utilize this margin. Finally, for one experiment, irradiations were conducted at two irradiation temperatures (500 deg. F and 550 deg. F) to determine the effect of irradiation temperature on embrittlement. The preliminary results of the irradiation program show an increase in T 30 shift of 69 deg. F for a decrease in irradiation temperature of 50 deg. F. The results suggest that for nickel bearing steels, the superior toughness of plate surface material is maintained after irradiation and for the copper content tested, nickel had no apparent effect on irradiation response. No apparent microstructure

  19. 42 CFR 493.1281 - Standard: Comparison of test results.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 5 2010-10-01 2010-10-01 false Standard: Comparison of test results. 493.1281 Section 493.1281 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN... Testing Analytic Systems § 493.1281 Standard: Comparison of test results. (a) If a laboratory performs the...

  20. Test results on systems developed for SST-1 tokamak

    International Nuclear Information System (INIS)

    Bora, D.

    2003-01-01

    Steady state Superconducting Tokamak (SST-1) is a large aspect ratio tokamak, configured to run double null diverted plasmas with significant elongation (κ) and triangularity Superconducting (SC) magnets are deployed for both the toroidal and poloidal field coils in SST-1. A NbTi based cable-in-conduit conductor (CICC) has been fabricated by M/S Hitachi Cables Ltd., Japan under specification and supervision of IPR. The suitability of this CICC for the SST-1 magnets has been validated through test carried out on a model coil (MC) wound from this CICC. Toroidal and poloidal SC magnets have been fabricated and factory acceptance tests have been performed. SC magnets require liquid helium (LHe) cooled current leads, electrical isolators at LHe temperature, superconducting bus bars and LHe transfer lines. Full scale prototypes of these have been developed and tested successfully. SC magnets will be cooled to 4.5K by forced flow of supercritical Helium through the CICC. A 1 kW grade liquefier/refrigerator has been installed and is in final stages of commissioning at IPR. SST-1 deploys a fully welded ultra high vacuum vessel, made up of 16 vessel sectors having ports and 16 rings with D-shaped cross-section. To establish the fabrication methodology for this, a full scale proto-type of the vessel with two vessel sectors and three rings has been fabricated and tested successfully. Based on this the fabrication of the vessel sectors and rings is in final stage of fabrication. Liquid nitrogen cooled radiation shield are deployed between the vacuum vessel and SC magnets as well as SC magnets and cryostat, to minimize the radiation losses at the SC magnets. SST-1 will have three different high power radio frequency (RF) systems to additionally heat and non-inductively drive plasma current to sustain the plasma in steady state for a duration of up to 1000 sec. Ion cyclotron resonance frequency (ICRF) and electron cyclotron resonance frequency (ECRF) systems will primarily be

  1. Irradiation Effects Test Series: Test IE-3. Test results report. [PWR

    Energy Technology Data Exchange (ETDEWEB)

    Farrar, L. C.; Allison, C. M.; Croucher, D. W.; Ploger, S. A.

    1977-10-01

    The objectives of the test reported were to: (a) determine the behavior of irradiated fuel rods subjected to a rapid power increase during which the possibility of a pellet-cladding mechanical interaction failure is enhanced and (b) determine the behavior of these fuel rods during film boiling following this rapid power increase. Test IE-3 used four 0.97-m long pressurized water reactor type fuel rods fabricated from previously irradiated fuel. The fuel rods were subjected to a preconditioning period, followed by a power ramp to 69 kW/m at a coolant mass flux of 4920 kg/s-m/sup 2/. After a flow reduction to 2120 kg/s-m/sup 2/, film boiling occurred on the fuel rods. One rod failed approximately 45 seconds after the reactor was shut down as a result of cladding embrittlement due to extensive cladding oxidation. Data are presented on the behavior of these irradiated fuel rods during steady-state operation, the power ramp, and film boiling operation. The effects of a power ramp and power ramp rates on pellet-cladding interaction are discussed. Test data are compared with FRAP-T3 computer model calculations and data from a previous Irradiation Effects test in which four irradiated fuel rods of a similar design were tested. Test IE-3 results indicate that the irradiated state of the fuel rods did not significantly affect fuel rod behavior during normal, abnormal (power ramp of 20 kW/m per minute), and accident (film boiling) conditions.

  2. Results from the 2013 drug and alcohol testing survey.

    Science.gov (United States)

    2015-12-01

    This report summarizes the results of the 2013 Federal Motor Carrier Safety Administration (FMCSA) Drug and Alcohol Testing Survey. This annual survey measures the percentage of drivers with commercial drivers licenses (CDLs) that test positive fo...

  3. Results from the 2008 Drug and Alcohol Testing Survey

    Science.gov (United States)

    2010-01-01

    This report summarizes the results of the 2008 Federal Motor Carrier Safety Administration Drug and Alcohol Testing Survey. This annual survey measures the percentage of drivers with commercial drivers licenses who test positive for controlled sub...

  4. Computer-aided dispatch--traffic management center field operational test : state of Utah final report

    Science.gov (United States)

    2006-07-01

    This document provides the final report for the evaluation of the USDOT-sponsored Computer-Aided Dispatch Traffic Management Center Integration Field Operations Test in the State of Utah. The document discusses evaluation findings in the followin...

  5. Computer-aided dispatch--traffic management center field operational test : Washington State final report

    Science.gov (United States)

    2006-05-01

    This document provides the final report for the evaluation of the USDOT-sponsored Computer-Aided Dispatch - Traffic Management Center Integration Field Operations Test in the State of Washington. The document discusses evaluation findings in the foll...

  6. Prototypical Rod Construction Demonstration Project. Phase 3, Final report: Volume 1, Cold checkout test report, Book 3

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    The objective of Phase 3 of the Prototypical Rod consolidation Demonstration Project (PRCDP) was to procure, fabricate, assemble, and test the Prototypical Rod consolidation System as described in the NUS Phase 2 Final Design Report. This effort required providing the materials, components, and fabricated parts which makes up all of the system equipment. In addition, it included the assembly, installation, and setup of this equipment at the Cold Test Facility. During the Phase 3 effort the system was tested on a component, subsystem, and system level. This volume 1, discusses the PRCDP Phase 3 Test Program that was conducted by the HALLIBURTON NUS Environmental Corporation under contract AC07-86ID12651 with the United States Department of Energy. This document, Volume 1, Book 3 discusses the following topics: Downender Test Results and Analysis Report; NFBC Canister Upender Test Results and Analysis Report; Fuel Assembly Handling Fixture Test Results and Analysis Report; and Fuel Canister Upender Test Results and Analysis Report.

  7. Experimental test results of multi-channel test rig of T1 test section, 5

    International Nuclear Information System (INIS)

    Hino, Ryutaro; Takase, Kazuyuki; Miyamoto, Yoshiaki

    1990-09-01

    Channel blockage test on a fuel column of the high temperature engineering test reactor (HTTR) has been performed under the helium gas atmosphere at a high temperature and a high pressure in order to obtain safety data on flow rate and temperature distributions in the fuel column with the multi-channel test rig of the fuel stack test section (T 1 ) in HENDEL. In the test, one of 12 fuel channels was blockaded to 90% of flow area at the channel inlet. Experimental results showed that the helium gas flow rate in the blockaded channel was 28%∼33% lower than the average flow rate for Reynolds number from 2300 to 14000 in isothermal flow. When simulated fuel rods were heated, the flow rate in the blockaded channel did not decrease down in comparison with the isothermal flow. This is due to that the heat generated in the fuel rods conducts to the other fuel channels in graphite fuel blocks, so that accelerated pressure losses in the fuel channels change with helium gas temperatures. (author)

  8. 78 FR 34989 - Sodium Hexametaphosphate From the People's Republic of China: Final Results of Expedited First...

    Science.gov (United States)

    2013-06-11

    ... From the People's Republic of China: Final Results of Expedited First Sunset Review of the Antidumping.... SUMMARY: On February 1, 2013, the Department of Commerce (the ``Department'') initiated the first five-year (``sunset'') review of the antidumping duty order on sodium hexametaphosphate from the People's...

  9. 77 FR 55808 - Certain Preserved Mushrooms From the People's Republic of China: Final Results of Antidumping...

    Science.gov (United States)

    2012-09-11

    ... DEPARTMENT OF COMMERCE International Trade Administration [A-570-851] Certain Preserved Mushrooms... preserved mushrooms from the People's Republic of China (PRC).\\1\\ Based upon our analysis of comments... is listed in the ``Final Results of Review'' section below. \\1\\ See Certain Preserved Mushrooms From...

  10. 76 FR 70112 - Certain Preserved Mushrooms From the People's Republic of China: Amended Final Results of...

    Science.gov (United States)

    2011-11-10

    ... DEPARTMENT OF COMMERCE International Trade Administration [A-570-851] Certain Preserved Mushrooms... duty order on certain preserved mushrooms from the People's Republic of China (PRC). See Certain Preserved Mushrooms From the People's Republic of China: Final Results of Antidumping Duty Administrative...

  11. 78 FR 36168 - Fresh Garlic From the People's Republic of China: Final Results of Antidumping Duty...

    Science.gov (United States)

    2013-06-17

    ...- Market Economy Unit regarding ``Fresh Garlic from the People's Republic of China: Extension of Deadline...'s Republic of China: Final Results of Antidumping Duty Administrative Review; 2010-2011 AGENCY... administrative review of the antidumping duty order on fresh garlic from the People's Republic of China (PRC...

  12. 77 FR 59377 - Solid Agricultural Grade Ammonium Nitrate from Ukraine: Final Results of the Expedited Second...

    Science.gov (United States)

    2012-09-27

    ... Ammonium Nitrate from Ukraine: Final Results of the Expedited Second Sunset Review of the Antidumping Duty... duty order on solid agricultural grade ammonium nitrate from Ukraine. The Department has conducted an... revocation of the antidumping duty order would be likely to lead to continuation or recurrence of dumping at...

  13. 76 FR 39847 - Solid Fertilizer Grade Ammonium Nitrate From the Russian Federation; Final Results of the...

    Science.gov (United States)

    2011-07-07

    ... duty order on ammonium nitrate from Russia would be likely to lead to continuation or recurrence of... Ammonium Nitrate From the Russian Federation; Final Results of the Expedited Sunset Review of Antidumping... review of the suspended antidumping duty investigation on solid fertilizer grade ammonium nitrate...

  14. 76 FR 57713 - Wooden Bedroom Furniture From the People's Republic of China: Amended Final Results of...

    Science.gov (United States)

    2011-09-16

    ... appearance on behalf of Liberty Furniture Industries Inc. (``Liberty'') on August 17, 2011. The law firm also... Department: (1) Left out the word ``Dongguan'' when it listed the entity ``Dongguan Cambridge Furniture Co., Ltd., Glory Oceanic Co., Ltd.'' (``Cambridge'') in the rate table of the Final Results; (2) did not...

  15. 76 FR 12700 - Polyethylene Retail Carrier Bags From Thailand: Final Results of Antidumping Duty Administrative...

    Science.gov (United States)

    2011-03-08

    .... (Sahachit Watana), Thai Plastic Bags Industries Co., Ltd. (TPBI), and Thantawan Industry Public Co., Ltd... stores, and restaurants, to their customers to package and carry their purchased products. The scope of... Industries Co., Ltd., Final Results Analysis Memorandum'' dated concurrently with this notice for details...

  16. 78 FR 56211 - Certain Frozen Warmwater Shrimp From the Socialist Republic of Vietnam: Final Results of...

    Science.gov (United States)

    2013-09-12

    ... rate, the cash deposit rate will be that for the Vietnam-wide entity; and (4) for all non-Vietnam... the surrogate values for certain export-related expenses incurred by Minh Phu Group and Nha Trang. The...\\ See Issues and Decision Memorandum at Appendix. Rate for Non-Selected Companies For the final results...

  17. 76 FR 66687 - Purified Carboxymethylcellulose From the Netherlands: Final Results of Antidumping Duty...

    Science.gov (United States)

    2011-10-27

    ... cellulose, or cellulose gum, which is a white to off-white, non-toxic, odorless, biodegradable powder... ANFC's U.S. packing expenses by converting the Euro-denominated expenses into U.S. dollars; and (2) we... directly to CBP 15 days after publication of these final results of review. Cash Deposit Requirements The...

  18. 76 FR 68137 - Polyethylene Retail Carrier Bags From Thailand: Amended Final Results of Antidumping Duty...

    Science.gov (United States)

    2011-11-03

    ... Bags From Thailand: Amended Final Results of Antidumping Duty Administrative Review AGENCY: Import..., the Department of Commerce (the Department) published Polyethylene Retail Carrier Bags From Thailand... 351.224(c) from the Polyethylene Retail Carrier Bag Committee and its individual members, Hilex Poly...

  19. 78 FR 47276 - Polyethylene Terephthalate (PET) Film, Sheet, and Strip From India: Final Results of the...

    Science.gov (United States)

    2013-08-05

    ... (PET) Film, Sheet, and Strip From India: Final Results of the Expedited Second Sunset Review of the... terephthalate (PET) film, sheet, and strip (``PET film'') from India. The Department finds that revocation of... INFORMATION CONTACT: Sean Carey or Dana Mermelstein, AD/CVD Operations, Office 6, Import Administration...

  20. Tank 241-BY-109, cores 201 and 203, analytical results for the final report

    International Nuclear Information System (INIS)

    Esch, R.A.

    1997-01-01

    This document is the final laboratory report for tank 241-BY-109 push mode core segments collected between June 6, 1997 and June 17, 1997. The segments were subsampled and analyzed in accordance with the Tank Push Mode Core Sampling and Analysis Plan (Bell, 1997), the Tank Safety Screening Data Quality Objective (Dukelow, et al, 1995). The analytical results are included

  1. 75 FR 62100 - Purified Carboxymethylcellulose From Mexico: Final Results of Antidumping Duty Administrative Review

    Science.gov (United States)

    2010-10-07

    ... 15, 2010) (Preliminary Results). The review covers one producer/exporter, Quimica Amtex, S.A. de C.V... Carboxymethylcellulose from Mexico: Final Determination Analysis Memorandum for Quimica Amtex, S.A. de C.V.,'' dated... June 30, 2009, is as follows: Weighted- average Producer/exporter margin (percentage) Quimica Amtex, S...

  2. First Kepler results on compact pulsators - VI. Targets in the final half of the survey phase

    DEFF Research Database (Denmark)

    Østensen, Roy H.; Silvotti, Roberto; Charpinet, S.

    2011-01-01

    We present results from the final 6 months of a survey to search for pulsations in white dwarfs (WDs) and hot subdwarf stars with the Kepler spacecraft. Spectroscopic observations are used to separate the objects into accurate classes, and we explore the physical parameters of the subdwarf B (sdB...

  3. 78 FR 27185 - Magnesium Metal From the People's Republic of China: Final Results of Antidumping Duty...

    Science.gov (United States)

    2013-05-09

    ... People's Republic of China: Final Results of Antidumping Duty Administrative Review; 2011-2012 AGENCY...-2012 administrative review of the antidumping duty order on magnesium metal from the People's Republic of China (``PRC''), in which it found that the one respondent company, Tianjin Magnesium...

  4. 78 FR 9034 - Silicomanganese From India, Kazakhstan, and Venezuela: Final Results of the Expedited Second...

    Science.gov (United States)

    2013-02-07

    ...] Silicomanganese From India, Kazakhstan, and Venezuela: Final Results of the Expedited Second Sunset Reviews of the... India, Kazakhstan, and Venezuela. The Department finds that revocation of these antidumping duty orders... INFORMATION: Background The antidumping duty orders on silicomanganese from India, Kazakhstan, and Venezuela...

  5. Final comparison report on ISP-35: Nupec hydrogen mixing and distribution test (Test M-7-1)

    International Nuclear Information System (INIS)

    1994-12-01

    This final comparison report summarizes the results of the OECD/CSNI sponsored ISP-35 exercise which was based on NUPEC's Hydrogen Mixing and Distribution Test M-7-1. 12 organizations from 10 different countries took part in the exercise. For the ISP-35 test, a steam/light gas (helium) mixture was released into the lower region of a simplified model of a PWR containment. At the same time, the dome cooling spray was also activated. the transient time histories for gas temperature and concentrations were recorded for each of the 25 compartments of the model containment. The wall temperatures as well as the dome pressure were also recorded. The ISP-35 participants simulated the test conditions and attempted to predict the time histories using their accident analysis codes. Results of these analyses are presented, and comparisons are made between the experimental data and the calculated data. In general, predictions for pressure, helium concentration and gas distribution patterns were achieved with acceptable accuracy

  6. Tank 241-SY-102, January 2000 Compatibility Grab Samples Analytical Results for the Final Report

    International Nuclear Information System (INIS)

    BELL, K.E.

    2000-01-01

    This document is the format IV, final report for the tank 241-SY-102 (SY-102) grab samples taken in January 2000 to address waste compatibility concerns. Chemical, radiochemical, and physical analyses on the tank SY-102 samples were performed as directed in Comparability Grab Sampling and Analysis Plan for Fiscal Year 2000 (Sasaki 1999). No notification limits were exceeded. Preliminary data on samples 2SY-99-5, -6, and -7 were reported in ''Format II Report on Tank 241-SY-102 Waste Compatibility Grab Samples Taken in January 2000'' (Lockrem 2000). The data presented here represent the final results

  7. Active vibration control testing of the SPICES program: final demonstration article

    Science.gov (United States)

    Dunne, James P.; Jacobs, Jack H.

    1996-05-01

    The Synthesis and Processing of Intelligent Cost Effective Structures (SPICES) Program is a partnership program sponsored by the Advanced Research Projects Agency. The mission of the program is to develop cost effective material processing and synthesis technologies to enable new products employing active vibration suppression and control devices to be brought to market. The two year program came to fruition in 1995 through the fabrication of the final smart components and testing of an active plate combined with two trapezoidal rails, forming an active mount. Testing of the SPICES combined active mount took place at McDonnell Douglas facilities in St. Louis, MO, in October-December 1995. Approximately 15 dB reduction in overall response of a motor mounted on the active structure was achieved. Further details and results of the SPICES combined active mount demonstration testing are outlined. Results of numerous damping and control strategies that were developed and employed in the testing are presented, as well as aspects of the design and fabrication of the SPICES active mount components.

  8. Final Test Report: Hexavalent Chrome Free Coatings for Electronics Electromagnetic Interference (EMI) Shielding Effectiveness (SE)

    Science.gov (United States)

    Kessel, Kurt R.

    2016-01-01

    The test results for Salt Spray Resistance, Static Heat and Humidity and Marine Environment can be found in Sections 3.1.3.3, 3.1.4.3 and 3.1.5.3 respectively. In summary, both the Metalast TCP and SurTec 650 Type 2 conversion coatings perform very similar to the incumbent Type 1 conversion coating against both 6061 and 5052 aluminum under all three test conditions. Significant prior work was performed to select the aluminum and conversion coating included within this test cycle; Reference - NASA GSDO Program Hexavalent Chrome Alternatives Final Pretreatments Test Report Task Order: NNH12AA45D September 01, 2013. As illustrated in the data, the 6061 aluminum panels SLIGHTLY out-performed the 5052 aluminum panels. Individual shielding effectiveness graphs for each panel are included within Appendix C and D. One other notable effect found during review of the data is that the Test Panels exposed to B117 Salt Fog reduced in shielding effectiveness significantly more than the Marine Environment Test Panels. The shielding effectiveness of the Marine Test Panels was approximately 20dB higher than the Test Panels that underwent B117 Salt Fog Exposure. The intent of this evaluation was not to maximize shielding effectiveness values. The same Parker Chomerics Cho-Seal 6503 gasket material was used for all panels with aluminum and conversion coating variants. A typical EMI gasket design for corrosive environments would be done quite differently. The intent was to execute a test that would provide the best possible evaluation of different aluminum materials and conversion coatings in corrosive environments. The test program achieved this intent. The fact that the two aluminums and two Type II conversion coatings performed similar to the incumbent Type 1 conversion coating is a positive outcome. It was desired to have an outcome that further differentiation the performance of two aluminum types and two conversion coating types but this could not be extracted by the test

  9. Preliminary irradiation test results from the Yankee Atomic Electric Company reactor vessel test irradiation program

    International Nuclear Information System (INIS)

    Biemiller, E.C.; Fyfitch, Stephen; Campbell, C.A.

    1994-01-01

    The Yankee Atomic Electric Company test irradiation program was implemented to characterize the irradiation response of representative Yankee Rowe reactor vessel beltline plate materials and to remove uncertainties in the analysis of existing irradiation data on the Yankee Rowe reactor vessel steel. Plate materials each containing 0.24 w/o copper, but different nickel contents at 0.63 w/o and 0.19 w/o, were heat treated to simulate the Yankee vessel heat treatment (austenitized at 982 o C (1800 o F)) and to simulate Regulatory Guide 1.99 database materials (austenitized at 871 o C (1600 o F)). These heat treatments produced different microstructures so the effect of microstructure on irradiation damage sensitivity could be tested. Because the nickel content of the test plates varied and the copper level was constant, the effect of nickel on irradiation embrittlement was also tested. Correlation monitor material, HSST-02, was included in the program to benchmark the Ford Nuclear Reactor (University of Michigan Test Reactor) which had never been used before for this type of irradiation program. Materials taken from plate surface locations (versus 1/4 T) were included to test whether or not the improved toughness properties of the plate surface layer, resulting from the rapid quench, are maintained after irradiation. If the improved properties are maintained, pressurized thermal shock calculations could utilize this margin. Finally, for one experiment, irradiations were conducted at two irradiation temperatures (260 o C and 288 o C) to determine the effect of irradiation temperature on embrittlement. (Author)

  10. Assessment of the quality of test results from selected civil engineering material testing laboratories in Tanzania

    CSIR Research Space (South Africa)

    Mbawala, SJ

    2017-12-01

    Full Text Available Civil and geotechnical engineering material testing laboratories are expected to produce accurate and reliable test results. However, the ability of laboratories to produce accurate and reliable test results depends on many factors, among others...

  11. 78 FR 29702 - Ball Bearings and Parts Thereof From Germany: Final Results of Antidumping Duty Administrative...

    Science.gov (United States)

    2013-05-21

    ...On February 11, 2013, the Department of Commerce (the Department) published the preliminary results and partial rescission of its administrative review of the antidumping duty order on ball bearings and parts thereof from Germany. The period of review (POR) is May 1, 2011, through September 14, 2011.\\1\\ We received no comments from interested parties. Accordingly, for the final results we continue to find that subject merchandise has not been sold at less than normal value. ---------------------------------------------------------------------------

  12. Melter operation results in chemical test at Rokkasho Reprocessing Plant

    International Nuclear Information System (INIS)

    Kanehira, Norio; Yoshioka, Masahiro; Muramoto, Hitoshi; Oba, Takaaki; Takahashi, Yuji

    2005-01-01

    Chemical Test of the glass melter system of the Vitrification Facility at Rokkasho Reprocessing Plant (RRP) was performed. In this test, basic performance of heating-up of the melter, melting glass, pouring glass was confirmed using simulated materials. Through these tests and operation of all modes, good results were gained, and training of operators was completed. (author)

  13. Final results of the PIDIE intercomparison exercise for the plutonium isotopic determination by gamma-ray spectrometry

    International Nuclear Information System (INIS)

    Morel, J.; Chauvenet, B.; Etcheverry, M.

    1991-01-01

    Final results from the PIDIE intercomparison exercise organised by the ESARDA Working Group on techniques and standards for non-destructive analysis are presented. The aim of this exercise carried out in 1988 was to test the gamma-ray spectroscopy methods used to determine the plutonium isotopic ratios in a large range of isotopic composition, in order to analyse the parameters and the error sources influencing the results. Sets of seven sealed samples of different plutonium isotopic composition were sent to nine participating laboratories. The final results with uncertainty indicators are reported; they are compared with complementary mass-spectrometry determinations. No important bias has been observed from this exercise. Significant improvements in plutonium isotopic determination by gamma-ray spectrometry come from both more elaborate spectrum analysis methods and better equipment

  14. Tests of the Standard Model with Multi boson final states at the ATLAS Detector

    CERN Document Server

    Gonella, Giulia; The ATLAS collaboration

    2018-01-01

    Measurements of the cross sections of the production of pairs of electroweak gauge bosons at the LHC constitute stringent tests of the electroweak sector of the Standard Model and provide a model- independent means to search for new physics at the TeV scale. The ATLAS collaboration has performed detailed measurements of integrated and differential cross sections of the production of heavy di-boson pairs in fully-leptonic and semi-leptonic final states at centre-of-mass energies of 13 TeV. The results are compared to predictions and provide constraints on new physics, by setting limits on anomalous triple gauge couplings. Some analyses in this area will be reviewed and their main results summarised.

  15. The Dornier 328 Acoustic Test Cell (ATC) for interior noise tests and selected test results

    Science.gov (United States)

    Hackstein, H. Josef; Borchers, Ingo U.; Renger, Klaus; Vogt, Konrad

    1992-01-01

    To perform acoustic studies for achieving low noise levels for the Dornier 328, an acoustic test cell (ATC) of the Dornier 328 has been built. The ATC consists of a fuselage section, a realistic fuselage suspension system, and three exterior noise simulation rings. A complex digital 60 channel computer/amplifier noise generation system as well as multichannel digital data acquisition and evaluation system have been used. The noise control tests started with vibration measurements for supporting acoustic data interpretation. In addition, experiments have been carried out on dynamic vibration absorbers, the most important passive noise reduction measure for low frequency propeller noise. The design and arrangement of the current ATC are presented. Furthermore, exterior noise simulation as well as data acquisition are explained. The most promising results show noise reduction due to synchrophasing and dynamic vibration absorbers.

  16. MASTICATION, PHONETICS AND ESTHETICS AS A FINAL RESULT OF PARTIAL OR COMPLETE DENTURE TREATMENT.

    Directory of Open Access Journals (Sweden)

    Kalina Georgieva

    2015-08-01

    Full Text Available Three target groups- dentists/ dental students, dental technicians and patients were asked to fill in an anonymous questionnaire about their satisfaction of the final results after prosthetic treatment with removable dentures using a scale from 1 to 5 (1- completely dissatisfied, 2-dissatisfied, 3-indifferent, 4-satisfied, 5-completely satisfied. The mean results (including colour, shape and size of artificial teeth, arrangement of front teeth, colour of artificial gums, phonetics, mastication, natural smile, enough space for tongue for all three groups of respondents were compared. Dental technicians (4,34 are more satisfied than dentists/dental students (3,62 and patients (3,53. A successful outcome of prosthetic treatment depends on one hand on the professional approach of the dental team and on the other hand on the patient’s motivation and cooperation. The predictive final results and realistic expectations lead to satisfaction of all participants in the treatment process.

  17. Production Facility Prototype Blower 1000 Hour Test Results II

    Energy Technology Data Exchange (ETDEWEB)

    Wass, Alexander Joseph [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Woloshun, Keith Albert [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Dale, Gregory E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Dalmas, Dale Allen [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Romero, Frank Patrick [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2018-01-08

    Long duration tests of the Aerzen GM 12.4 roots style blower in a closed loop configuration provides valuable data and lessons learned for long-term operation at the Mo-99 production facility. The blower was operated in a closed loop configuration with the flow conditions anticipated in plant operation with a Mo-100 target inline. The additional thermal energy generated from beam heating of the Mo-100 disks were not included in these tests. Five 1000 hour tests have been completed since the first test was performed in January of 2016. All five 1000 hour tests have proven successful in exposing preventable issues related to oil and helium leaks. All blower tests to this date have resulted in stable blower performance and consistency. A summary of the results for each test, including a review of the first and second tests, are included in this report.

  18. Results and Analysis from Space Suit Joint Torque Testing

    Science.gov (United States)

    Matty, Jennifer

    2010-01-01

    This joint mobility KC lecture included information from two papers, "A Method for and Issues Associated with the Determination of Space Suit Joint Requirements" and "Results and Analysis from Space Suit Joint Torque Testing," as presented for the International Conference on Environmental Systems in 2009 and 2010, respectively. The first paper discusses historical joint torque testing methodologies and approaches that were tested in 2008 and 2009. The second paper discusses the testing that was completed in 2009 and 2010.

  19. Hawaiian Electric Advanced Inverter Test Plan - Result Summary

    Energy Technology Data Exchange (ETDEWEB)

    Hoke, Anderson; Nelson, Austin; Prabakar, Kumaraguru; Nagarajan, Adarsh

    2016-10-14

    This presentation is intended to share the results of lab testing of five PV inverters with the Hawaiian Electric Companies and other stakeholders and interested parties. The tests included baseline testing of advanced inverter grid support functions, as well as distribution circuit-level tests to examine the impact of the PV inverters on simulated distribution feeders using power hardware-in-the-loop (PHIL) techniques. hardware-in-the-loop (PHIL) techniques.

  20. Evaluation of LLTR series II test A-7 results

    International Nuclear Information System (INIS)

    Knittle, D.E.; Amos, J.C.; Yang, T.M.

    1981-09-01

    This report evaluates the test A-7 data and assesses the capability of the analytical methodology (as a result of Series I program) to predict the thermal/hydraulic phenomena associated with a large SWR event occurring after the sodium system pressure has increased to near the rupture disc burst pressure due to a smaller size leak event. Evaluation of intertest examination data to determine the extent of test article damage resulting from test A-7 is also included

  1. Test beam results from the D0 end electromagnetic calorimeter

    International Nuclear Information System (INIS)

    Roe, N.A.

    1991-11-01

    Test beam results are presented for the DO end electromagnetic calorimeter. Data were taken with electrons and pions ranging in energy from 5 GeV to 150 GeV. Results from the analysis of the test beam data are presented on energy resolution and linearity, stability and uniformity of response, position resolution and electron-pion separation

  2. 40 CFR 85.1509 - Final admission of modification and test vehicles.

    Science.gov (United States)

    2010-07-01

    ... test vehicles. 85.1509 Section 85.1509 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) CONTROL OF AIR POLLUTION FROM MOBILE SOURCES Importation of Motor Vehicles and Motor Vehicle Engines § 85.1509 Final admission of modification and test vehicles. (a) Except...

  3. Final summary report of fuel-dynamics tests H2 and E4

    International Nuclear Information System (INIS)

    Doerner, R.C.; Rothman, A.B.; De Volpi, A.; Dickerman, C.E.; Deitrich, L.W; Stahl, D.; Murphy, W.F.

    1976-02-01

    Results of two failure experiments using LMFBR-type fuel during simulated unprotected transient overpower accidents are reported and analyzed. In both experiments, a single fresh fuel pin in a Mark-IIA loop was subjected to a temperature-limited, step-reactivity irradiation in the TREAT reactor. Total energy was 490 MJ in Test H2 and 690 MJ in Test E4. Except for their timing, the sequence of events in the failure scenario was the same for both tests. Local coolant boiling began 25-50 msec before failure. Significant upward fuel flow in the center of the pin started as early as 100 msec before cladding failure. Cladding failure was due to melting after contact with molten fuel and occurred at the top of the fuel column. Formation of an outlet flow-channel blockage began about 10 msec after failure and was complete by 50 msec. Inlet blockage began later and was less extensive. No significant amount of fuel sweepout was observed. Fuel remains separated into a small group of 50-1000-μm fragments and a macroscopic group of chunks and clinkers. The final distribution of fuel remains may have resulted from a delayed fuel/steel interaction in the inlet region

  4. Tank 241-T-204, core 188 analytical results for the final report

    Energy Technology Data Exchange (ETDEWEB)

    Nuzum, J.L.

    1997-07-24

    TANK 241-T-204, CORE 188, ANALYTICAL RESULTS FOR THE FINAL REPORT. This document is the final laboratory report for Tank 241 -T-204. Push mode core segments were removed from Riser 3 between March 27, 1997, and April 11, 1997. Segments were received and extruded at 222-8 Laboratory. Analyses were performed in accordance with Tank 241-T-204 Push Mode Core Sampling and analysis Plan (TRAP) (Winkleman, 1997), Letter of instruction for Core Sample Analysis of Tanks 241-T-201, 241- T-202, 241-T-203, and 241-T-204 (LAY) (Bell, 1997), and Safety Screening Data Qual@ Objective (DO) ODukelow, et al., 1995). None of the subsamples submitted for total alpha activity (AT) or differential scanning calorimetry (DC) analyses exceeded the notification limits stated in DO. The statistical results of the 95% confidence interval on the mean calculations are provided by the Tank Waste Remediation Systems Technical Basis Group and are not considered in this report.

  5. Results of Detailed Hydrologic Characterization Tests - Fiscal Year 2000

    International Nuclear Information System (INIS)

    Spane, Frank A; Thorne, Paul D; Newcomer, Darrell R

    2001-01-01

    This report provides the results of detailed hydrologic characterization tests conducted within eleven Hanford Site wells during fiscal year 2000. Detailed characterization tests performed included groundwater-flow characterization; barometric response evaluation; slug tests; single-well tracer tests; constant-rate pumping tests; and in-well, vertical flow tests. Hydraulic property estimates obtained from the detailed hydrologic tests include transmissivity; hydraulic conductivity; specific yield; effective porosity; in-well, lateral flow velocity; aquifer-flow velocity; vertical distribution of hydraulic conductivity (within the well-screen section); and in-well, vertical flow velocity. In addition, local groundwater-flow characteristics (i.e., hydraulic gradient and flow direction) were determined for four sites where detailed well testing was performed

  6. Early results of gate valve flow interruption blowdown tests

    International Nuclear Information System (INIS)

    DeWall, K.G.

    1988-01-01

    The preliminary results of the USNRC/INEL high-energy BWR line break flow interruption testing are presented. Two representative nuclear valve assemblies were cycled under design basis Reactor Water Cleanup pipe break conditions to provide input for the technical basis for resolving the Nuclear Regulatory Commission's Generic Issue 87. The effects of the blowdown hydraulic loadings on valve operability, especially valve closure stem forces, were studied. The blowdown tests showed that, given enough thrust, typical gate valves will close against the high flow resulting from a line break. The tests also showed that proper operator sizing depends on the correct identification of values for the sizing equation. Evidence exists that values used in the past may not be conservative for all valve applications. The tests showed that improper operator lock ring installation following test or maintenance can invalidate in-situ test results and prevent the valve from performing its design function. 2 refs., 12 figs., 2 tabs

  7. Vehicle infrastructure integration proof of concept : results and findings summary-vehicle : final report

    Science.gov (United States)

    2009-05-18

    This document describes the objectives and the approach to the testing of the VII Proof of Concept system. A summary of the test results and findings for both the major system functions and the applications designed for the system, are presented alon...

  8. Preliminary design for hot dirty-gas control-valve test facility. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    This report presents the results of a preliminary design and cost estimating effort for a facility for the testing of control valves in Hot Dirty Gas (HDGCV) service. This design was performed by Mittelhauser Corporation for the United States Department of Energy's Morgantown Energy Technology Center (METC). The objective of this effort was to provide METC with a feasible preliminary design for a test facility which could be used to evaluate valve designs under simulated service conditions and provide a technology data base for DOE and industry. In addition to the actual preliminary design of the test facility, final design/construction/operating schedules and a facility cost estimate were prepared to provide METC sufficient information with which to evaluate this design. The bases, assumptions, and limitations of this study effort are given. The tasks carried out were as follows: METC Facility Review, Environmental Control Study, Gas Generation Study, Metallurgy Review, Safety Review, Facility Process Design, Facility Conceptual Layout, Instrumentation Design, Cost Estimates, and Schedules. The report provides information regarding the methods of approach used in the various tasks involved in the completion of this study. Section 5.0 of this report presents the results of the study effort. The results obtained from the above-defined tasks are described briefly. The turnkey cost of the test facility is estimated to be $9,774,700 in fourth quarter 1979 dollars, and the annual operating cost is estimated to be $960,000 plus utilities costs which are not included because unit costs per utility were not available from METC.

  9. Final safety and hazards analysis for the Battelle LOCA simulation tests in the NRU reactor

    International Nuclear Information System (INIS)

    Axford, D.J.; Martin, I.C.; McAuley, S.J.

    1981-04-01

    This is the final safety and hazards report for the proposed Battelle LOCA simulation tests in NRU. A brief description of equipment test design and operating procedure precedes a safety analysis and hazards review of the project. The hazards review addresses potential equipment failures as well as potential for a metal/water reaction and evaluates the consequences. The operation of the tests as proposed does not present an unacceptable risk to the NRU Reactor, CRNL personnel or members of the public. (author)

  10. Relationship between substances in seminal plasma and Acrobeads Test results.

    Science.gov (United States)

    Komori, Kazuhiko; Tsujimura, Akira; Okamoto, Yoshio; Matsuoka, Yasuhiro; Takao, Tetsuya; Miyagawa, Yasushi; Takada, Shingo; Nonomura, Norio; Okuyama, Akihiko

    2009-01-01

    To asses the effects of seminal plasma on sperm function. Retrospective case-control study. University hospital. One hundred fourteen infertile men. Acrobeads Test scores (0-4) and measurement of interleukin (IL)-6, soluble IL-6 receptor, epidermal growth factor, insulin-like growth factor-I (IGF-I), transforming growth factor-beta I, superoxide dismutase, calcitonin, and macrophage migration inhibitory factor (MIF) levels in seminal plasma. Kruskal-Wallis test to compare the concentrations of substances as a nonparametric test for differences among Acrobeads Test scores and a multivariable logistic regression model to find independent risk factors associated with abnormal Acrobeads Test results. The Acrobeads Test score was 0 for 7 samples, 1 for 20 samples, 2 for 18 samples, 3 for 28 samples, and 4 for 41 samples. Age, abstinence period, and semen parameters, except for sperm motility and percentage of sperm with abnormal morphology, had no effect on the Acrobeads Test results. Concentrations of IGF-I and MIF were significantly higher in patients with abnormal Acrobeads Test results. Multivariate analysis indicated that MIF and IGF-I were significantly associated with abnormal Acrobeads Test results (scores 0 to 1). Although further studies are needed, IGF-I and MIF in seminal plasma may have negative effects on sperm function.

  11. Results of recent KROTOS FCI tests. Alumina vs. corium melts

    Energy Technology Data Exchange (ETDEWEB)

    Huhtiniemi, I.; Magallon, D.; Hohmann, H. [Commission of the European Communities, Ispra (Italy). Joint Research Center

    1998-01-01

    Recent results from KROTOS fuel-coolant interaction experiments are discussed. Five tests with alumina were performed under highly subcooled conditions, all of these tests resulted in spontaneous steam explosions. Additionally, four tests were performed at low subcooling to confirm, on one hand, the suppression of spontaneous steam explosions under such conditions and, on the other hand, that such a system is still triggerable using an external initiator. The other test parameters in these alumina tests included the melt superheat and the initial pressure. All the tests in the investigated superheat range (150 K - 750 K) produced a steam explosion and no evidence of the explosion suppression by the elevated initial pressure (in the limited range of 0.1 - 0.375 MPa) was observed in the alumina tests. The corium test series include a test with 3 kg of melt under both subcooled and near saturated conditions at ambient pressure. Two additional tests were performed with subcooled water; one test was performed at an elevated pressure of 0.2 MPa with 2.4 kg of melt and another test with 5.1 kg of melt at ambient pressure. None of these tests with corium produced a propagating energetic steam explosion. However, propagating low energy (about twice the energy of the trigger pulse) events were observed. All corium tests produced significantly higher water level swells during the mixing phase than the corresponding alumina tests. Present experimental evidence suggests that the water depletion in the mixing zone suppresses energetic steam explosions with corium melts at ambient pressure and in the present pour geometry. Processes that could produce such a difference in void generation are discussed. (author)

  12. Spent fuel sabotage test program, characterization of aerosol dispersal : interim final report.

    Energy Technology Data Exchange (ETDEWEB)

    Gregson, Michael Warren; Brockmann, John E.; Loiseau, Olivier (Institut de Radioprotection et de Surete Nucleaire, France); Klennert, Lindsay A.; Nolte, Oliver (Fraunhofer Institut fur Toxikologie und Experimentelle Medizin, Germany); Molecke, Martin Alan; Autrusson, Bruno A. (Institut de Radioprotection et de Surete Nucleaire, France); Koch, Wolfgang (Fraunhofer Institut fur Toxikologie und Experimentelle Medizin, Germany); Pretzsch, Gunter Guido (Gesellschaft fur Anlagen- und Reaktorsicherheit, Germany); Brucher, Wenzel (Gesellschaft fur Anlagen- und Reaktorsicherheit, Germany); Steyskal, Michele D.

    2008-03-01

    This multinational, multi-phase spent fuel sabotage test program is quantifying the aerosol particles produced when the products of a high energy density device (HEDD) interact with and explosively particulate test rodlets that contain pellets of either surrogate materials or actual spent fuel. This program provides source-term data that are relevant to plausible sabotage scenarios in relation to spent fuel transport and storage casks and associated risk assessments. We present details and significant results obtained from this program from 2001 through 2007. Measured aerosol results include: respirable fractions produced; amounts, nuclide content, and produced particle size distributions and morphology; measurements of volatile fission product species enhanced sorption--enrichment factors onto respirable particles; and, status on determination of the spent fuel ratio, SFR, needed for scaling studies. Emphasis is provided on recent Phase 3 tests using depleted uranium oxide pellets plus non-radioactive fission product dopants in surrogate spent fuel test rodlets, plus the latest surrogate cerium oxide results and aerosol laboratory supporting calibration work. The DUO{sub 2}, CeO{sub 2}, plus fission product dopant aerosol particle results are compared with available historical data. We also provide a status review on continuing preparations for the final Phase 4 in this program, tests using individual short rodlets containing actual spent fuel from U.S. PWR reactors, with both high- and lower-burnup fuel. The source-term data, aerosol results, and program design have been tailored to support and guide follow-on computer modeling of aerosol dispersal hazards and radiological consequence assessments. This spent fuel sabotage, aerosol test program was performed primarily at Sandia National Laboratories, with support provided by both the U.S. Department of Energy and the Nuclear Regulatory Commission. This program has significant input from, and is cooperatively

  13. Physical and chemical test results of electrostatic safe flooring materials

    Science.gov (United States)

    Gompf, R. H.

    1988-01-01

    This test program was initiated because a need existed at the Kennedy Space Center (KSC) to have this information readily available to the engineer who must make the choice of which electrostatic safe floor to use in a specific application. The information, however, should be of value throughout both the government and private industry in the selection of a floor covering material. Included are the test results of 18 floor covering materials which by test evaluation at KSC are considered electrostatically safe. Tests were done and/or the data compiled in the following areas: electrostatics, flammability, hypergolic compatibility, outgassing, floor type, material thickness, and available colors. Each section contains the test method used to gather the data and the test results.

  14. Thermal results of the Japanese LCT coil's domestic test

    International Nuclear Information System (INIS)

    Tada, Eisuke; Hiyama, Tadao; Kato, Takashi; Takahashi, Osamu; Shimamoto, Susumu

    1984-01-01

    This paper describes thermal results obtained in the domestic test of the Japanese LCT coil which was constructed at the Japan Atomic Energy Research Institute (JAERI) in order to develop large superconducting coils for fusion in international collaboration proposed by the IEA. The domestic test was carried out from May 13 to June 17 in 1982 by using the test facility named as SETF (Superconducting Engineering Test Facility) which was composed of a 350-l/h helium cryogenic system, a vacuum system, a 30 KA-DC power supply and protection system, and a PDP-11/70 computer system. The cool-down characteristics, heat load, fast discharge characteristics, stability, and warm-up characteristics of the LCT coil were successfully measured in the test. The details of thermal test results acquired in the cool-down, heat load measurement, fast discharge, and warm-up, and the comparison between measurements and calculations are described in this paper. (author)

  15. Commissioning and First Results from the Fermilab Cryomodule Test Stand

    Energy Technology Data Exchange (ETDEWEB)

    Harms, Elvin; et al.

    2017-05-01

    A new test stand dedicated to SRF cryomodule testing, CMTS1, has been commissioned and is now in operation at Fermilab. The first device to be cooled down and powered in this facility is the prototype 1.3 GHz cryomodule assembled at Fermilab for LCLS-II. We describe the demonstrated capabilities of CMTS1, report on steps taken during commissioning, provide an overview of first test results, and survey future plans.

  16. Sims Prototype System 2 test results: Engineering analysis

    Science.gov (United States)

    1978-01-01

    The testing, problems encountered, and the results and conclusions obtained from tests performed on the IBM Prototype System, 2, solar hot water system, at the Marshall Space Flight Center Solar Test Facility was described. System 2 is a liquid, non draining solar energy system for supplying domestic hot water to single residences. The system consists of collectors, storage tank, heat exchanger, pumps and associated plumbing and controls.

  17. Barometric pressure transient testing applications at the Nevada Test Site: formation permeability analysis. Final report

    International Nuclear Information System (INIS)

    Hanson, J.M.

    1984-12-01

    The report evaluates previous investigations of the gas permeability of the rock surrounding emplacement holes at the Nevada Test Site. The discussion sets the framework from which the present uncertainty in gas permeability can be overcome. The usefulness of the barometric pressure testing method has been established. Flow models were used to evaluate barometric pressure transients taken at NTS holes U2fe, U19ac and U20ai. 31 refs., 103 figs., 18 tabs

  18. RTG performance on Galileo and Ulysses and Cassini test results

    International Nuclear Information System (INIS)

    Kelly, C. Edward; Klee, Paul M.

    1997-01-01

    Power output from telemetry for the two Galileo RTGs are shown from the 1989 launch to the recent Jupiter encounter. Comparisons of predicted, measured and required performance are shown. Similar comparisons are made for the RTG on the Ulysses spacecraft which completed its planned mission in 1995. Also presented are test results from small scale thermoelectric modules and full scale converters performed for the Cassini program. The Cassini mission to Saturn is scheduled for an October 1997 launch. Small scale module test results on thermoelectric couples from the qualification and flight production runs are shown. These tests have exceeded 19,000 hours are continuing to provide increased confidence in the predicted long term performance of the Cassini RTGs. Test results are presented for full scale units both ETGs (E-6, E-7) and RTGs (F-2, F-5) along with mission power predictions. F-5, fueled in 1985, served as a spare for the Galileo and Ulysses missions and plays the same role in the Cassini program. It has successfully completed all acceptance testing. The ten years storage between thermal vacuum tests is the longest ever experienced by an RTG. The data from this test are unique in providing the effects of long term low temperature storage on power output. All ETG and RTG test results to date indicate that the power requirements of the Cassini spacecraft will be met. BOM and EOM power margins of at least five percent are predicted

  19. RTG performance on Galileo and Ulysses and Cassini test results

    International Nuclear Information System (INIS)

    Kelly, C.E.; Klee, P.M.

    1997-01-01

    Power output from telemetry for the two Galileo RTGs are shown from the 1989 launch to the recent Jupiter encounter. Comparisons of predicted, measured and required performance are shown. Similar comparisons are made for the RTG on the Ulysses spacecraft which completed its planned mission in 1995. Also presented are test results from small scale thermoelectric modules and full scale converters performed for the Cassini program. The Cassini mission to Saturn is scheduled for an October 1997 launch. Small scale module test results on thermoelectric couples from the qualification and flight production runs are shown. These tests have exceeded 19,000 hours are continuing to provide increased confidence in the predicted long term performance of the Cassini RTGs. Test results are presented for full scale units both ETGs (E-6, E-7) and RTGs (F-2, F-5) along with mission power predictions. F-5, fueled in 1985, served as a spare for the Galileo and Ulysses missions and plays the same role in the Cassini program. It has successfully completed all acceptance testing. The ten years storage between thermal vacuum tests is the longest ever experienced by an RTG. The data from this test are unique in providing the effects of long term low temperature storage on power output. All ETG and RTG test results to date indicate that the power requirements of the Cassini spacecraft will be met. BOM and EOM power margins of at least five percent are predicted. copyright 1997 American Institute of Physics

  20. Results of EMC market surveillance tests for UPS systems

    Energy Technology Data Exchange (ETDEWEB)

    Rajamaeki, J. [Safety Technology Authority, Helsinki (Finland)

    1997-12-31

    This paper reports the first wide electromagnetic compatibility (EMC) market surveillance project in Finland in which the uninterruptible power systems (UPS) on the Finnish market are monitored. Altogether 11 UPS units are EMC tested and the results of these tests are described in this paper. The effect of basic characters of UPS on the level of electromagnetic interference are analysed. (orig.) 3 refs.

  1. 7 CFR 91.24 - Reports of test results.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 3 2010-01-01 2010-01-01 false Reports of test results. 91.24 Section 91.24 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Standards, Inspections, Marketing Practices), DEPARTMENT OF AGRICULTURE (CONTINUED) COMMODITY LABORATORY TESTING PROGRAMS...

  2. Development of new testing methods for the numerical load analysis for the drop test of steel sheet containers for the final repository Konrad

    International Nuclear Information System (INIS)

    Protz, C.; Voelzke, H.; Zencker, U.; Hagenow, P.; Gruenewald, H.

    2011-01-01

    The qualification of steel sheet containers as intermediate-level waste container for the final repository is performed by the BAM (Bundeasmt fuer Materialpruefung) according to the BfS (Bundesamt fuer Strahlenschutz) requirements. The testing requirements include the stacking pressure tests, lifting tests, drop tests thermal tests (fire resistance) and tightness tests. Besides the verification using model or prototype tests and transferability considerations numerical safety analyses may be performed alternatively. The authors describe the internal BAM research project ConDrop aimed to develop extended testing methods for the drop test of steel sheet containers for the final repository Konrad using numerical load analyses. A finite element model was developed using The FE software LS-PrePost 3.0 and ANSYS 12.0 and the software FE-Code LS-DYNA for the simulation of the drop test (5 m height). The results were verified by experimental data from instrumented drop tests. The container preserves its integrity after the drop test, plastic deformation occurred at the bottom plate, the side walls, the cask cover and the lateral uprights.

  3. Drug and alcohol testing results 2009 annual report

    Science.gov (United States)

    2013-11-01

    This is the 15th annual report of the results of the Federal Transit Administrations (FTA) Drug and Alcohol Testing Program. This report summarizes the reporting requirements for calendar year 2009, the requirements of the overall drug and alcohol...

  4. Drug and alcohol testing results 2007 annual report

    Science.gov (United States)

    2009-05-01

    This is the 13th annual report of the results of the Federal Transit Administrations (FTA) Drug and Alcohol Testing Program. This report summarizes the reporting requirements for calendar year 2007, the requirements of the overall drug and alcohol...

  5. Drug and Alcohol Testing Results 2008 Annual Report

    Science.gov (United States)

    2010-09-01

    This is the 14th annual report of the results of the Federal Transit Administration's (FTA) Drug and Alcohol Testing : Program. This report summarizes the reporting requirements for calendar year 2008, the requirements of the overall : drug and alcoh...

  6. Drug and alcohol testing results 2006 annual report.

    Science.gov (United States)

    2008-08-01

    This is the 12th annual report of the results of the Federal Transit Administration's (FTA) Drug and Alcohol Testing Program. This report summarizes the reporting requirements for calendar year 2006, the requirements of the overall drug and alcohol t...

  7. Results from tests of the Delphi TPC prototype

    International Nuclear Information System (INIS)

    Vilanova, D.

    1985-01-01

    Results from beam tests of a half-scale sector of the Delphi TPC are presented. The spatial resolution is slightly higher than predicted by Monte Carlo simulations, corresponding to an average value of about 300 μm. (orig.)

  8. Test emission of uranium hexafluoride in atmosphere. Results interpretation

    International Nuclear Information System (INIS)

    Crabol, B.; Deville-Cavelin, G.

    1989-01-01

    To permit the modelization of gaseous uranium hexafluoride behaviour in atmosphere, a validation test has been executed the 10 April 1987. The experimental conditions, the main results and a comparison with a diffusion model are given in this report [fr

  9. PULSE COMBUSTOR DESIGN QUALIFICATION TEST AND CLEAN COAL FEEDSTOCK TEST - VOLUME I AND VOLUME II; FINAL

    International Nuclear Information System (INIS)

    Unknown

    2002-01-01

    For this Cooperative Agreement, the pulse heater module is the technology envelope for an indirectly heated steam reformer. The field of use of the steam reformer pursuant to this Cooperative Agreement with DOE is for the processing of sub-bituminous coals and lignite. The main focus is the mild gasification of such coals for the generation of both fuel gas and char-for the steel industry is the main focus. An alternate market application for the substitution of metallurgical coke is also presented. This project was devoted to qualification of a 253-tube pulse heater module. This module was designed, fabricated, installed, instrumented and tested in a fluidized bed test facility. Several test campaigns were conducted. This larger heater is a 3.5 times scale-up of the previous pulse heaters that had 72 tubes each. The smaller heater has been part of previous pilot field testing of the steam reformer at New Bern, North Carolina. The project also included collection and reduction of mild gasification process data from operation of the process development unit (PDU). The operation of the PDU was aimed at conditions required to produce char (and gas) for the Northshore Steel Operations. Northshore Steel supplied the coal for the process unit tests

  10. Interim results from UO2 fuel oxidation tests in air

    International Nuclear Information System (INIS)

    Campbell, T.K.; Gilbert, E.R.; Thornhill, C.K.; White, G.D.; Piepel, G.F.; Griffin, C.W.j.

    1987-08-01

    An experimental program is being conducted at Pacific Northwest Laboratory (PNL) to extend the characterization of spent fuel oxidation in air. To characterize oxidation behavior of irradiated UO 2 , fuel oxidation tests were performed on declad light-water reactor spent fuel and nonirradited UO 2 pellets in the temperature range of 135 to 250 0 C. These tests were designed to determine the important independent variables that might affect spent fuel oxidation behavior. The data from this program, when combined with the test results from other programs, will be used to develop recommended spent fuel dry-storage temperature limits in air. This report describes interim test results. The initial PNL investigations of nonirradiated and spent fuels identified the important testing variables as temperature, fuel burnup, radiolysis of the air, fuel microstructure, and moisture in the air. Based on these initial results, a more extensive statistically designed test matrix was developed to study the effects of temperature, burnup, and moisture on the oxidation behavior of spent fuel. Oxidation tests were initiated using both boiling-water reactor and pressurized-water reactor fuels from several different reactors with burnups from 8 to 34 GWd/MTU. A 10 5 R/h gamma field was applied to the test ovens to simulate dry storage cask conditions. Nonirradiated fuel was included as a control. This report describes experimental results from the initial tests on both the spent and nonirradiated fuels and results to date on the tests in a 10 5 R/h gamma field. 33 refs., 51 figs., 6 tabs

  11. Testing of components on the shaking table facilities of AEP and contribution to full scale dynamic testing of Kozloduy NPP. Final report

    International Nuclear Information System (INIS)

    Ambriashvili, Y.

    1996-01-01

    This final report summarizes the results of components testing on the shaking table facilities of 'Atomenergoproject' which are considered as a contribution to the full scale dynamic testing of the Kozloduy nuclear power plant Units 5 and 6. It was designed on 1.0 g according to the calculations that were based on accelerograms which included artificial and already known recordings of real earthquakes. Maximum acceleration of the designed spectrum and new spectrum which are recommended are now within the range of frequencies 2.5-20 Hz. Active reactor and the primary loop are seismic stable as well as the tested equipment tested by 'Atomenergoproject'

  12. NNWSI Phase II materials interaction test procedure and preliminary results

    International Nuclear Information System (INIS)

    Bates, J.K.; Gerding, T.J.

    1985-01-01

    The Nevada Nuclear Waste Storage Investigations (NNWSI) project is investigating the volcanic tuff beds of Yucca Mountain, Nevada, as a potential location for a high-level radioactive waste repository. This report describes a test method (Phase II) that has been developed to measure the release of radionuclides from the waste package under simulated repository conditions, and provides information on materials interactions that may occur in the repository. The results of 13 weeks of testing using the method are presented, and an analog test is described that investigates the relationship between the test method and expected repository conditions. 9 references, 10 figures, 11 tables

  13. Recent test results on the ATLAS SCT detector

    International Nuclear Information System (INIS)

    Pernegger, H.

    2003-01-01

    The ATLAS Semiconductor Tracker (SCT) will be a central part of the tracking system of the ATLAS experiment. The SCT, which is currently under construction, will consist of four concentric barrels of silicon detectors as well as two silicon endcap detectors formed by nine disks each. After an overview of the SCT and the detector module layout, the paper will summarize recent test results obtained from silicon detector modules, which have been extensively tested before starting their large series production. The tests presented here cover electrical performance of individual modules, their performance after irradiation, as well as system tests in a multi-module setup

  14. Preliminary results of steel containment vessel model test

    International Nuclear Information System (INIS)

    Matsumoto, T.; Komine, K.; Arai, S.

    1997-01-01

    A high pressure test of a mixed-scaled model (1:10 in geometry and 1:4 in shell thickness) of a steel containment vessel (SCV), representing an improved boiling water reactor (BWR) Mark II containment, was conducted on December 11-12, 1996 at Sandia National Laboratories. This paper describes the preliminary results of the high pressure test. In addition, the preliminary post-test measurement data and the preliminary comparison of test data with pretest analysis predictions are also presented

  15. Test results on reuse of reclaimed shower water - A summary

    Science.gov (United States)

    Verostko, Charles E.; Garcia, Rafael; Sauer, Richard; Reysa, Richard P.; Linton, Arthur T.

    1989-01-01

    Results are presented from tests to evaluate a microgravity whole body shower and waste water recovery system design for possible use on the Space Station. Several water recovery methods were tested, including phase change distillation, a thermoelectric hollow fiber membrane evaporation subsystem, and a reverse osmosis dynamic membrane system. Consideration is given to the test hardware, the types of soaps evaluated, the human response to showering with reclaimed water, chemical treatment for microbial control, the procedures for providing hygienic water, and the quality of water produced by the systems. All three of the waste water recovery systems tested successfully produced reclaimed water for reuse.

  16. Mitigation of social and environmental impacts resulting from final closure of uranium mines

    International Nuclear Information System (INIS)

    Cipriani, Moacir

    2002-11-01

    This thesis focus on the impact of uranium mines in Brazil. It is recent, in the order of the Brazilian mining, the concern with the impact of mining activities. The Federal Constitution of 1988 compels the miner to rehabilitate the degraded environment, in accordance with the technical solution demanded by the competent public agency, which makes use of a system of environmental norms conditioning the mining activity. However, the concern with the closure of mines is in an early stage, for whose achievement the public power still lacks of norms and regulations. The closure of the first uranium mining in Brazil assumes special meaning, because the possible environmental problems related to uranium mines are considered to be serious and the uranium industry is state owned. This thesis is divided in two sections. The first one describes the state of the art of the uranium industry and the rules and management practices regarding the final closure of uranium mining in Brazil and countries like Australia, Canada, USA and France, that have been selected on the basis of the following criteria: production, exportation, control of reserves and final consumption of uranium. In the second part, a case study of Pocos de Caldas mine is presented, with description of historical production, plant waste and the chemical treatment of the ore. This part also presents the research carried out since the beginning of the operations aiming to remedial actions, including the dismantling of surface structures, tailings reclamation, and ground-water restoration, following CNEN (Brazilian Nuclear Energy Commission) rules, as well as a survey of local press coverage of the impact of the industry. A final recommendation is made regarding a management model and strategies to mitigate social and environmental impacts resulting from final closure of the CIPC. (author)

  17. HIPPARCOS satellite: Aeritalia involvement and system test activities and results

    Science.gov (United States)

    Strim, B.; Cugno, W.; Morsillo, G.

    In 1989 the European Space Agency is scheduled to launch HIPPARCOS on a 2.5-year mission that will revolutionize the state of astronomy. This is the first satellite to be dedicated to astrometry, a branch of astronomy that deals with the position of celestial objects and their motion in space. With an accuracy impossible to achieve from Earth, HIPPARCOS will make position, trigonometric parallax and proper motion measurements of some 100.000 pre-selected stars. The data will be used to calculate each star's distance and motion, providing astronomers with an unprecedented map of the heavens. In the end, the HIPPARCOS mission is expected to reveal surprisingly new insight into theories of stellar evolution, as well as into the nature of our galaxy and the universe. The program has been awarded to the MESH industrial consortium for definition, development and production. The French firm MATRA (prime contractor) and the AERITALIA SPACE SYSTEMS GROUP (major co-contractor) share program responsibility. AERITALIA is in charge of the spacecraft or "service module". This is the structural platform for the telescope payload and provides all subsystem services including thermal control, data handling, telecommunications, electrical power distribution, power generation, attitude and orbit control, and apogee kick motor. AERITALIA is responsible for the procurement of all spacecraft subsystems for which it directs the activities of a multinational team of subcontractors. In addition, it is in charge of the satellite's final assembly, integration and testing, as well as for the procurement of all ground support equipment for satellite testing. HIPPARCOS stands for HIgh Precision PARallax COllecting Satellite. Its name is also intended to honor the Greek astronomer Hipparchus (190-120 BC) who compiled the first star catalog and who first used trigonometric parallax to calculate the distance to the moon. (Parallax is the apparent shift in a celestial body's position in the sky

  18. Brine migration test for Asse Mine, Federal Republic of Germany: final test plan

    International Nuclear Information System (INIS)

    1983-07-01

    The United States and the Federal Republic of Germany (FRG) will conduct a brine migration test in the Asse Salt Mine in the FRG as part of the US/FRG Cooperative Radioactive Waste Management Agreement. Two sets of two tests each will be conducted to study both liquid inclusion migration and vapor migration in the two salt types chosen for the experiments: (1) pure salt, for its characteristics similar to the salt that might occur in potential US repositories, and (2) transitional salt, for its similarity to the salt that might occur in potential repositories in Germany

  19. Final Report Feasibility Study for the California Wave Energy Test Center (CalWavesm)

    Energy Technology Data Exchange (ETDEWEB)

    Blakeslee, Samuel Norman [California Polytechnic State Univ. (CalPoly), San Luis Obispo, CA (United States). Inst. for Advanced Technology and Public Policy; Toman, William I. [Protean Wave Energy Ltd., Los Osos, CA (United States); Williams, Richard B. [Leidos Maritime Solutions, Reston, VA (United States); Davy, Douglas M. [CH2M, Sacramento, CA (United States); West, Anna [Kearns and West, Inc., San Francisco, CA (United States); Connet, Randy M. [Omega Power Engineers, LLC, Anaheim, CA (United States); Thompson, Janet [Kearns and West, Inc., San Francisco, CA (United States); Dolan, Dale [California Polytechnic State Univ. (CalPoly), San Luis Obispo, CA (United States); Baltimore, Craig [California Polytechnic State Univ. (CalPoly), San Luis Obispo, CA (United States); Jacobson, Paul [Electric Power Research Inst. (EPRI), Knoxville, TN (United States); Hagerman, George [Virginia Polytechnic Inst. and State Univ. (Virginia Tech), Blacksburg, VA (United States); Potter, Chris [California Natural Resources Agency, Sacramento, CA (United States); Dooher, Brendan [Pacific Gas and Electric Company, San Francisco, CA (United States); Wendt, Dean [California Polytechnic State Univ. (CalPoly), San Luis Obispo, CA (United States); Sheppard, Colin [Humboldt State Univ., Arcata, CA (United States); Harris, Andrew [Humboldt State Univ., Arcata, CA (United States); Lawson, W. Graham [Power Delivery Consultants, Inc., Albany, NY (United States)

    2017-07-31

    The California Wave Energy Test Center (CalWave) Feasibility Study project was funded over multiple phases by the Department of Energy to perform an interdisciplinary feasibility assessment to analyze the engineering, permitting, and stakeholder requirements to establish an open water, fully energetic, grid connected, wave energy test center off the coast of California for the purposes of advancing U.S. wave energy research, development, and testing capabilities. Work under this grant included wave energy resource characterization, grid impact and interconnection requirements, port infrastructure and maritime industry capability/suitability to accommodate the industry at research, demonstration and commercial scale, and macro and micro siting considerations. CalWave Phase I performed a macro-siting and down-selection process focusing on two potential test sites in California: Humboldt Bay and Vandenberg Air Force Base. This work resulted in the Vandenberg Air Force Base site being chosen as the most favorable site based on a peer reviewed criteria matrix. CalWave Phase II focused on four siting location alternatives along the Vandenberg Air Force Base coastline and culminated with a final siting down-selection. Key outcomes from this work include completion of preliminary engineering and systems integration work, a robust turnkey cost estimate, shoreside and subsea hazards assessment, storm wave analysis, lessons learned reports from several maritime disciplines, test center benchmarking as compared to existing international test sites, analysis of existing applicable environmental literature, the completion of a preliminary regulatory, permitting and licensing roadmap, robust interaction and engagement with state and federal regulatory agency personnel and local stakeholders, and the population of a Draft Federal Energy Regulatory Commission (FERC) Preliminary Application Document (PAD). Analysis of existing offshore oil and gas infrastructure was also performed

  20. Influence of diet on the results of laboratory tests

    Directory of Open Access Journals (Sweden)

    Kinga Lis

    2013-12-01

    Full Text Available Blood and urine laboratory tests are necessary to diagnose the state of the patient. These tests are also helpful in the assessment of diet and nutritional status of the organism. It is recommended that both blood and urine for laboratory tests be collected in the morning, from fasting patients after an overnight rest. These conditions are defined as the standard conditions for collection of material for laboratory testing. Before testing, patients should follow their natural diet and avoid physical exertion, night work, long-distance travel, as well as consumption of alcohol and drugs. They should also reduce the consumption of synthetic vitamins and herbal remedies and other dietary supplements. Medications should be limited to those that are absolutely necessary. All of these factors can affect the results of laboratory tests.

  1. Results of tests with open fuel in KNK II

    International Nuclear Information System (INIS)

    Schmitz, G.

    1987-03-01

    For the operation of Liquid Metal Cooled Fast Breeder Reactors with cladding failures the consequences of increased contamination by fission products and fuel and the possibility of failure propagation to adjacent fuel pins due to fuel swelling have to be envisaged. To clarify some of these problems a KNK II test program involving open fuel was defined with the first experiments of this program being performed between October 1981 and May 1984. After the description of the test equipment and of the test program, the results will be presented on delayed neutron measurements, fission gas measurements and post irradiation examinations. The report will conclude with a discussion of the results [de

  2. Final Report - Assessment of Testing Options for the NTR at the INL

    Energy Technology Data Exchange (ETDEWEB)

    Howe, Steven D; McLing, Travis L; McCurry, Michael; Plummer, Mitchell A

    2013-02-01

    non-nuclear , sub-scale test using gas injection to validate the computational models; 4) Produce a preliminary cost estimate to build a nuclear furnace equivalent facility to test NTR fuel on a green field location on the INL site. The results show that the INL geology is substantially better suited to the SAFE testing method than the NTS site. The existence of impermeable interbeds just above the sub-surface aquifer ensure that no material from the test, radioactive or not, can enter the water table. Similar beds located just below the surface will prevent any gaseous products from reaching the surface for dispersion. The extremely high permeability of the strata between the interbeds allows rapid dispersion of the rocket exhaust. In addition, the high permeability suggests that a lower back-pressure may develop in the hole against the rocket thrust, which increases safety of operations. Finally, the cost of performing a sub-scale, non-nuclear verification experiment was determined to be $3M. The third method was assessed through discussions with INL staff resident at the site. In essence, any new Category I facility on any DOE site will cost in excess of $250M. Based on the results of this study, a cost estimate for testing a nuclear rocket at the INL site appears to be warranted. Given the fact that a new nuclear fuel may be possible that does not release any fission products, the SAFE testing option appears to be the most affordable.

  3. Mathematic model of regional economy development by the final result of labor resources

    Science.gov (United States)

    Zaitseva, Irina; Malafeev, Oleg; Strekopytov, Sergei; Bondarenko, Galina; Lovyannikov, Denis

    2018-04-01

    This article presents the mathematic model of regional economy development based on the result of labor resources. The solution of a region development-planning problem is considered for the period of long-lasting planning taking into account the beginning and the end of the planned period. The challenge is to find the distribution of investments in the main and additional branches of the regional economy, which will provide simultaneous transaction of all major sectors of the regional economy from the given condition to the predetermined final state.

  4. Search for right-handed currents in muon decay: final results

    International Nuclear Information System (INIS)

    Strovink, M.

    1986-01-01

    Final results from the Berkeley-Northwestern-TRIUMF muon decay experiment are summarized. If right-handed neutrinos are less massive than ∼ 6 MeV, the mass of a possible right-handed W 2 must exceed 514 GeV (with no mixing of left- and right-handed gauge bosons), or 432 GeV (with any mixing). Stringent limits are also set on left-right mixing, on non-V,A components of charged weak interactions, and on the energy scales for lepton compositeness and family symmetry breaking. 10 refs.; 5 figs

  5. Tank 241-U-106, cores 147 and 148, analytical results for the final report

    Energy Technology Data Exchange (ETDEWEB)

    Steen, F.H.

    1996-09-27

    This document is the final report deliverable for tank 241-U-106 push mode core segments collected between May 8, 1996 and May 10, 1996 and received by the 222-S Laboratory between May 14, 1996 and May 16, 1996. The segments were subsampled and analyzed in accordance with the Tank 241-U-106 Push Mode Core Sampling and analysis Plan (TSAP), the Historical Model Evaluation Data Requirements (Historical DQO), Data Quality Objective to Support Resolution of the Organic Complexant Safety Issue (Organic DQO) and the Safety Screening Data Quality Objective (DQO). The analytical results are included in Table 1.

  6. Tank 214-AW-105, grab samples, analytical results for the final report

    International Nuclear Information System (INIS)

    Esch, R.A.

    1997-01-01

    This document is the final report for tank 241-AW-105 grab samples. Twenty grabs samples were collected from risers 10A and 15A on August 20 and 21, 1996, of which eight were designated for the K Basin sludge compatibility and mixing studies. This document presents the analytical results for the remaining twelve samples. Analyses were performed in accordance with the Compatibility Grab Sampling and Analysis Plan (TSAP) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DO). The results for the previous sampling of this tank were reported in WHC-SD-WM-DP-149, Rev. 0, 60-Day Waste Compatibility Safety Issue and Final Results for Tank 241-A W-105, Grab Samples 5A W-95-1, 5A W-95-2 and 5A W-95-3. Three supernate samples exceeded the TOC notification limit (30,000 microg C/g dry weight). Appropriate notifications were made. No immediate notifications were required for any other analyte. The TSAP requested analyses for polychlorinated biphenyls (PCB) for all liquids and centrifuged solid subsamples. The PCB analysis of the liquid samples has been delayed and will be presented in a revision to this document

  7. A Fuzzy Logic Based Method for Analysing Test Results

    Directory of Open Access Journals (Sweden)

    Le Xuan Vinh

    2017-11-01

    Full Text Available Network operators must perform many tasks to ensure smooth operation of the network, such as planning, monitoring, etc. Among those tasks, regular testing of network performance, network errors and troubleshooting is very important. Meaningful test results will allow the operators to evaluate network performanceof any shortcomings and to better plan for network upgrade. Due to the diverse and mainly unquantifiable nature of network testing results, there is a needs to develop a method for systematically and rigorously analysing these results. In this paper, we present STAM (System Test-result Analysis Method which employs a bottom-up hierarchical processing approach using Fuzzy logic. STAM is capable of combining all test results into a quantitative description of the network performance in terms of network stability, the significance of various network erros, performance of each function blocks within the network. The validity of this method has been successfully demonstrated in assisting the testing of a VoIP system at the Research Instiute of Post and Telecoms in Vietnam. The paper is organized as follows. The first section gives an overview of fuzzy logic theory the concepts of which will be used in the development of STAM. The next section describes STAM. The last section, demonstrating STAM’s capability, presents a success story in which STAM is successfully applied.

  8. Full-Length High-Temperature Severe Fuel Damage Test No. 5: Final safety analysis

    International Nuclear Information System (INIS)

    Lanning, D.D.; Lombardo, N.J.; Panisko, F.E.

    1993-09-01

    This report presents the final safety analysis for the preparation, conduct, and post-test discharge operation for the Full-Length High Temperature Experiment-5 (FLHT-5) to be conducted in the L-24 position of the National Research Universal (NRU) Reactor at Chalk River Nuclear Laboratories (CRNL), Ontario, Canada. The test is sponsored by an international group organized by the US Nuclear Regulatory Commission. The test is designed and conducted by staff from Pacific Northwest Laboratory with CRNL staff support. The test will study the consequences of loss-of-coolant and the progression of severe fuel damage

  9. Uprated OMS Engine Status-Sea Level Testing Results

    Science.gov (United States)

    Bertolino, J. D.; Boyd, W. C.

    1990-01-01

    The current Space Shuttle Orbital Maneuvering Engine (OME) is pressure fed, utilizing storable propellants. Performance uprating of this engine, through the use of a gas generator driven turbopump to increase operating pressure, is being pursued by the NASA Johnson Space Center (JSC). Component level design, fabrication, and test activities for this engine system have been on-going since 1984. More recently, a complete engine designated the Integrated Component Test Bed (ICTB), was tested at sea level conditions by Aerojet. A description of the test hardware and results of the sea level test program are presented. These results, which include the test condition operating envelope and projected performance at altitude conditions, confirm the capability of the selected Uprated OME (UOME) configuration to meet or exceed performance and operational requirements. Engine flexibility, demonstrated through testing at two different operational mixture ratios, along with a summary of projected Space Shuttle performance enhancements using the UOME, are discussed. Planned future activities, including ICTB tests at simulated altitude conditions, and recommendations for further engine development, are also discussed.

  10. Cement/bentonite interaction. Results from 16 month laboratory tests

    Energy Technology Data Exchange (ETDEWEB)

    Karnland, O. [Clay Technology AB, Lund (Sweden)

    1997-12-01

    The work concerns possible bentonite clay mineral alteration in constructions with bentonite in close contact with cement, and the effect of such changes on bentonite buffer properties. The investigation comprises a 16 months laboratory test series with hydrothermal cell tests, percolation tests and diffusion tests. MX-80 Wyoming bentonite was used in all tests. Two types of artificial cement pore water solutions were used in the percolation and diffusion tests. The swelling pressure and the hydraulic conductivity were measured continuously in the percolation tests. After termination, the clay was analyzed with respect to changes in element distribution, mineralogy and shear strength. The water solutions were analyzed with respect to pH, cations and major anions. The results concerning chemical and mineralogical changes are in summary: Ion exchange in the montmorillonite until equilibrium with cement pore-water ions was reached; Increase in cation exchange capacity; Dissolution of original cristobalite; Increase in quartz content; Minor increase in illite content; Minor formation of chlorite; Formation of CSH(I); Wash away of CSH-gel into surrounding water. A large decrease in swelling pressure and a moderate increase in hydraulic conductivity were recorded in the samples percolated by SULFACEM pore-water solution. The mineralogical alterations only concerned a minor part of the total bentonite mass and the changes in physical properties were therefore most likely due to the replacement of the original charge balancing cation by cement pore-water cations. Comparisons between the current test result and results from 4 month tests indicate that the rates of illite and chlorite formation were reduced during the tests. The presence of zeolites in the clay could not be ensured. However, the discovery of CSH material is important since CSH is expected to precede the formation of zeolites 5 refs, 48 figs, 11 tabs

  11. ExEP yield modeling tool and validation test results

    Science.gov (United States)

    Morgan, Rhonda; Turmon, Michael; Delacroix, Christian; Savransky, Dmitry; Garrett, Daniel; Lowrance, Patrick; Liu, Xiang Cate; Nunez, Paul

    2017-09-01

    EXOSIMS is an open-source simulation tool for parametric modeling of the detection yield and characterization of exoplanets. EXOSIMS has been adopted by the Exoplanet Exploration Programs Standards Definition and Evaluation Team (ExSDET) as a common mechanism for comparison of exoplanet mission concept studies. To ensure trustworthiness of the tool, we developed a validation test plan that leverages the Python-language unit-test framework, utilizes integration tests for selected module interactions, and performs end-to-end crossvalidation with other yield tools. This paper presents the test methods and results, with the physics-based tests such as photometry and integration time calculation treated in detail and the functional tests treated summarily. The test case utilized a 4m unobscured telescope with an idealized coronagraph and an exoplanet population from the IPAC radial velocity (RV) exoplanet catalog. The known RV planets were set at quadrature to allow deterministic validation of the calculation of physical parameters, such as working angle, photon counts and integration time. The observing keepout region was tested by generating plots and movies of the targets and the keepout zone over a year. Although the keepout integration test required the interpretation of a user, the test revealed problems in the L2 halo orbit and the parameterization of keepout applied to some solar system bodies, which the development team was able to address. The validation testing of EXOSIMS was performed iteratively with the developers of EXOSIMS and resulted in a more robust, stable, and trustworthy tool that the exoplanet community can use to simulate exoplanet direct-detection missions from probe class, to WFIRST, up to large mission concepts such as HabEx and LUVOIR.

  12. BWR Full Integral Simulation Test (FIST) Phase II test results and TRAC-BWR model qualification

    International Nuclear Information System (INIS)

    Sutherland, W.A.; Alamgir, M.; Findlay, J.A.; Hwang, W.S.

    1985-10-01

    Eight matrix tests were conducted in the FIST Phase I. These tests investigated the large break, small break and steamline break LOCA's, as well as natural circulation and power transients. There are nine tests in Phase II of the FIST program. They include the following LOCA tests: BWR/6 LPCI line break, BWR/6 intermediate size recirculation break, and a BWR/4 large break. Steady state natural circulation tests with feedwater makeup performed at high and low pressure, and at high pressure with HPCS makeup, are included. Simulation of a transient without rod insertion, and with controlled depressurization, was performed. Also included is a simulation of the Peach Bottom turbine trip test. The final two tests simulated a failure to maintain water level during a postulated accident. A FIST program objective is to assess the TRAC code by comparisons with test data. Two post-test predictions made with TRACB04 are compared with Phase II test data in this report. These are for the BWR/6 LPCI line break LOCA, and the Peach Bottom turbine trip test simulation

  13. Results from Testing of Two Rotary Percussive Drilling Systems

    Science.gov (United States)

    Kriechbaum, Kristopher; Brown, Kyle; Cady, Ian; von der Heydt, Max; Klein, Kerry; Kulczycki, Eric; Okon, Avi

    2010-01-01

    The developmental test program for the MSL (Mars Science Laboratory) rotary percussive drill examined the e ect of various drill input parameters on the drill pene- tration rate. Some of the input parameters tested were drill angle with respect to gravity and percussive impact energy. The suite of rocks tested ranged from a high strength basalt to soft Kaolinite clay. We developed a hole start routine to reduce high sideloads from bit walk. The ongoing development test program for the IMSAH (Integrated Mars Sample Acquisition and Handling) rotary percussive corer uses many of the same rocks as the MSL suite. An additional performance parameter is core integrity. The MSL development test drill and the IMSAH test drill use similar hardware to provide rotation and percussion. However, the MSL test drill uses external stabilizers, while the IMSAH test drill does not have external stabilization. In addition the IMSAH drill is a core drill, while the MSL drill uses a solid powdering bit. Results from the testing of these two related drilling systems is examined.

  14. Measurement of ability emotional intelligence: results for two new tests.

    Science.gov (United States)

    Austin, Elizabeth J

    2010-08-01

    Emotional intelligence (EI) has attracted considerable interest amongst both individual differences researchers and those in other areas of psychology who are interested in how EI relates to criteria such as well-being and career success. Both trait (self-report) and ability EI measures have been developed; the focus of this paper is on ability EI. The associations of two new ability EI tests with psychometric intelligence, emotion perception, and the Mayer-Salovey-Caruso EI test (MSCEIT) were examined. The new EI tests were the Situational Test of Emotion Management (STEM) and the Situational Test of Emotional Understanding (STEU). Only the STEU and the MSCEIT Understanding Emotions branch were significantly correlated with psychometric intelligence, suggesting that only understanding emotions can be regarded as a candidate new intelligence component. These understanding emotions tests were also positively correlated with emotion perception tests, and STEM and STEU scores were positively correlated with MSCEIT total score and most branch scores. Neither the STEM nor the STEU were significantly correlated with trait EI tests, confirming the distinctness of trait and ability EI. Taking the present results as a starting-point, approaches to the development of new ability EI tests and models of EI are suggested.

  15. 76 FR 56158 - Certain Frozen Warmwater Shrimp From the Socialist Republic of Vietnam: Final Results and Final...

    Science.gov (United States)

    2011-09-12

    ... F. Purchased Ice G. Water H. Containerization I. Labor J. Financial Ratios Comment 3: Zeroing... parties an opportunity to comment on the Preliminary Results and, based upon our analysis of the comments... to comment on the Preliminary Results. Between April 4, 2011, and April 25, 2011, the Department...

  16. Towards the final MRPC design. Performance test with heavy ion beam

    Energy Technology Data Exchange (ETDEWEB)

    Deppner, Ingo; Herrmann, Norbert [Physikalisches Institut Uni. Heidelberg, Heidelberg (Germany)

    2015-07-01

    The Compressed Baryonic Matter spectrometer (CBM) is a future heavy ion experiment located at the Facility for Anti-proton and Ion Research (FAIR) in Darmstadt, Germany. The key element in CBM providing hadron identification at incident energies between 2 and 35 AGeV will be a 120 m{sup 2} large Time-of-Flight (ToF) wall composed of Multi-gap Resistive Plate Chambers (MRPC) with a system time resolution better than 80 ps. Aiming for an interaction rate of 10 MHz for Au+Au collisions the MRPCs have to cope with an incident particle flux between 0.1 kHz/cm{sup 2} and 25 kHz/cm{sup 2} depending on their location. Characterized by granularity and rate capability the actual conceptual design of the ToF-wall foresees 4 different counter types called MRPC1 - MRPC4. In order to elaborate the final MRPC design of these counters a heavy ion test beam time was performed at GSI. In this contribution we present performance test results of 2 different MRPC3 full size prototypes developed at Heidelberg University and Tsinghua University, Beijing.

  17. Testing two novel stump-lifting heads in a final felling Norway spruce stand

    Energy Technology Data Exchange (ETDEWEB)

    Kaerhae, K. (Metsaeteho Oy, Helsinki (Finland)), Email: kalle.karha@metsateho.fi; Mutikainen, A. (TTS Research, Rajamaeki (Finland)), Email: arto.mutikainen@tts.fi

    2009-07-01

    The use of stump and root wood chips has increased very rapidly in the 21st century in Finland: in the year 2000, the total consumption of stump wood chips for energy generation was 10 GWh, while in 2008 it was around 1.2 TWh. Metsaeteho Oy and TTS Research tested two new stump-lifting devices for lifting stumps in a final felling Norway spruce (picea abies) stand. In the time study with the Vaekevae Stump Processor lifting head, the productivity of stump lifting was 7,5 m3 / E{sub 0}-hour when lifting spruce stumps with a diameter of 30 cm from clayey soil, and 8.3 m3 /E{sub 0}-hour when lifting spruce stumps from sandy soil. When lifting stumps with a diameter of 40 cm, the stump-lifting productivity was 9.0 m3 /E{sub 0}-h (clay) and 10,5 m3 / E{sub 0}-h (sand). The results of this relatively restricted test indicated that the Vaekevae Stump Processor is s reliable and effective stump-lifting head that enables the harvesting of high-quality stump raw material for energy generation. The stump lifting productivity of the other lifting head (Jaervinen) was lower than that of the Vaekevae Strump Processor. Some development suggestions for the Jaervinen lifting head were presented and discussed. (orig.)

  18. Proposed Interventions to Decrease the Frequency of Missed Test Results

    Science.gov (United States)

    Wahls, Terry L.; Cram, Peter

    2009-01-01

    Numerous studies have identified that delays in diagnosis related to the mishandling of abnormal test results are an import contributor to diagnostic errors. Factors contributing to missed results included organizational factors, provider factors and patient-related factors. At the diagnosis error conference continuing medical education conference…

  19. EOL3 M0 X-ray Tomography Test Results

    CERN Document Server

    Avramidou, R; Bozhko, N; Borisov, A; Goriatchev, V; Goriatchev, S; Gushin, V; Fakhroutdinov, R; Kojine, A; Kononov, A; Larionov, A; Salomatin, Yu I; Schuh, S; Sedykh, Yu; Tchougouev, A

    2001-01-01

    Results of X-ray tomography test of EOL3 module 0 chamber is presented in the note. Peculiarities of the X-ray tomography of the chamber are discussed. Comparison of the tomography results with predictions of the production site measurements is made.

  20. Electromagnetic results of the Japanese LCT coil's domestic test

    International Nuclear Information System (INIS)

    Nishi, Masataka; Okuno, Kiyoshi; Takahashi, Yoshikazu; Tsuji, Hiroshi; Ando, Toshinari; Shimamoto, Susumu

    1984-01-01

    The domestic test of the Japanese LCT coil was carried out in 1982. During this test, the coil was charged up to the single coil's 100% state (10.22kA, 6.4T, 106MJ) four times and experienced no quenche. at the 100% charging state, coil stability was tested by using heaters installed in the conductor. A half turn length normal zone (about 5 m) generated by heaters was spontenously disappeared in 2 second. This normalized zone included the highest magnetic field position. The transport current which gives the stable limit is extraporated to be about 12.5kA at 8T by this test result. The dump test was carried out also from the 100% charging state. At that time, about 90% of the coil's stored energy was extracted by the dump resistor and the coil was not damaged. (author)

  1. Test results and operational characteristics of prototype SSCL half cell

    International Nuclear Information System (INIS)

    McInturff, A.D.; Burgett, W.; Carter, H.

    1994-01-01

    The SSCL Accelerator System's String Test (ASST) has had several cool down, subsequent operational test series, and warm up cycles. The first cycle of these was rather limited in scope as mandated by Congress. The subsequent tests have been performed to obtain more complete information about parameters of, or operating experience with, the ensemble of magnets and spools when operating serially as in accelerator operations. The tests and procedures performed to date have emphasized cryogenic, mechanical, and electrical operations. These have included running, as well as upset conditions, i.e., superconducting to normal transition of the string (quench). This paper represents a summary of the operational test results and characteristics seen to date. A limited discussion will be included as to their implications with respect to a successful accelerator operation

  2. Depressurisation studies. Phase 2: results of Tests 127 and 128

    International Nuclear Information System (INIS)

    Edwards, A.R.; Borgartz, B.O.; Goodman, R.M.E.; O'Brien, T.P.; Rawlingson, M.

    1978-06-01

    A basic experimental programme involving the sudden depressurisation of a simple pipe system containing water at 3.45 to 17.24MPa pressure and temperature in the range of 200 to 250 0 C has been concluded. Measurements were made of the transient density, pressure, and temperature variations in a two phase fluid in the system during discharge. Phase 1 tests investigated blowdown from straight pipes 4m long with constant internal diameters of 73 and 32 mm. Phase 2 tests incorporated a reservoir added to the 32mm pipe. In this, the second of three reports on Phase 2 tests, the test assembly, instrumentation and experimental procedure are briefly described. The conditions and results are reported for two of the tests in which the liquid in the long discharge pipe was initially subcooled by 10 0 C and 15 0 C while the reservoir was at saturation conditions with a steam dome present. (UK)

  3. ATLAS RPC commissioning status and cosmic ray test results

    CERN Document Server

    Bianco, Michele

    2009-01-01

    The muon trigger system of the ATLAS experiment consists of several sub-systems and each of them need to be tested and certified before LHC operation. In the barrel region Resistive Plate Chambers are employed. RPC detector and its level-1 trigger electronics are designed to detect and select high momentum muons with high time resolution and good tracking capability for a total surface of about 4000 m2. The commissioning phase provided an unique opportunity to demonstrate, before LHC start-up, the functionality of the muon trigger components such as detector chambers, level-1 trigger electronics, detector slow control system, data acquisition chain, software and computing. We present the status of ATLAS RPC detector, the problems met during the commissioning and the solutions found and, finally, its performances as obtained by acquiring cosmic rays.

  4. Test results, Industrial Solar Technology parabolic trough solar collector

    Energy Technology Data Exchange (ETDEWEB)

    Dudley, V.E. [EG and G MSI, Albuquerque, NM (United States); Evans, L.R.; Matthews, C.W. [Sandia National Labs., Albuquerque, NM (United States)

    1995-11-01

    Sandia National Laboratories and Industrial Solar Technology are cost-sharing development of advanced parabolic trough technology. As part of this effort, several configurations of an IST solar collector were tested to determine the collector efficiency and thermal losses with black chrome and black nickel receiver selective coatings, combined with aluminized film and silver film reflectors, using standard Pyrex{reg_sign} and anti-reflective coated Pyrex{reg_sign} glass receiver envelopes. The development effort has been successful, producing an advanced collector with 77% optical efficiency, using silver-film reflectors, a black nickel receiver coating, and a solgel anti-reflective glass receiver envelope. For each receiver configuration, performance equations were empirically derived relating collector efficiency and thermal losses to the operating temperature. Finally, equations were derived showing collector performance as a function of input insolation value, incident angle, and operating temperature.

  5. Tensile and fracture toughness test results of neutron irradiated beryllium

    Energy Technology Data Exchange (ETDEWEB)

    Chaouadi, R.; Moons, F.; Puzzolante, J.L. [Centre d`Etude de l`Energie Nucleaire, Mol (Belgium)

    1998-01-01

    Tensile and fracture toughness test results of four Beryllium grades are reported here. The flow and fracture properties are investigated by using small size tensile and round compact tension specimens. Irradiation was performed at the BR2 material testing reactor which allows various temperature and irradiation conditions. The fast neutron fluence (>1 MeV) ranges between 0.65 and 2.45 10{sup 21} n/cm{sup 2}. In the meantime, un-irradiated specimens were aged at the irradiation temperatures to separate if any the effect of temperature from irradiation damage. Test results are analyzed and discussed, in particular in terms of the effects of material grade, test temperature, thermal ageing and neutron irradiation. (author)

  6. COMPARISON OF RESULTS OF THERMAL TESTS OF BALCONY DOORS

    Directory of Open Access Journals (Sweden)

    Golubev Stanislav Sergeevich

    2012-10-01

    Full Text Available Results of thermal tests of balcony doors are presented in the article. In the course of the research project, two types of doors were tested. The first type represents a PVC frame door (width 82 mm; it has a triple glazing (4K-16Ar-4-16Ar-K4; its blank part represents a polystyrene sandwich panel (width 40 mm. The second type represents a PVC frame door (width 82 mm, that has a triple glazing (4K-16Ar-4-16Ar-K4 and composite PVC panels. The testing procedure and processing results are described in the article. The test has demonstrated that the thermal resistance value of the balcony door of the first type exceeds the thermal resistance value of the balcony door of the second type.

  7. Analysis of SCTF/CCTF counterpart test results

    International Nuclear Information System (INIS)

    Okubo, Tsutomu; Sobajima, Makoto; Iwamura, Takamichi; Ohnuki, Akira; Abe, Yutaka; Adachi, Hiromichi; Murao, Yoshio

    1990-06-01

    Slab Core Test Facility (SCTF) and Cylindrical Core Test Facility (CCTF) are large scale experimental facilities of Japan Atomic Energy Research Institute (JAERI) for the investigation of reflooding behavior during a postulated loss-of-coolant accident (LOCA) in PWRs. Although the flow area scaling ratios of both facilities to a 1,000 MWe class PWR are the same and 1/21.4, the SCTF has the same core width as the radius of the reference PWR while the CCTF has a 1/4.5 times shorter core radius. Therefore, a few SCTF/CCTF counterpart tests were conducted in order to investigate the difference in core reflooding behavior between in the SCTF and CCTF tests as well as the effect of core radial length on core two-dimensional thermo-hydrodynamic behavior. This report present the test results and an analysis on them. Major results obtained are: (1) Taking account of the differences in test conditions and facility design, core reflooding behavior is considered to be similar between the SCTF and the CCTF test. Main difference of the facility design is in the effective core flow area and this is considered to result in the difference in core water accumulation behavior. (2) The effect of core radial length on core two-dimensional thermo-hydrodynamic behavior has been observed to be significant and heat transfer enhancement or degradation in radial direction is more significant for the longer radius core. (3) In addition, where the core power varies significantly in the radial direction, significant heat transfer enhancement has been observed in the higher power bundle during the LPCI period. Also, in the peripheral region, heat transfer degradation has been observed more significantly in the outer bundle even they have the same bundle power. (4) Magnitude of these heat transfer enhancement or degradation was larger at the higher elevation than the midplane level in the SCTF test, whereas smaller in the CCTF test. (author)

  8. Results of SC proton cavity tests (B = 1 and B = 0.65)

    CERN Document Server

    Peauger, F et al

    2013-01-01

    The two superconducting cavities were carefully designed for challenging performance. They were fabricated in industry with intermediate tests and specialized processing in CEA and CNRS. The results are promising, except for a degradation of the field flatness of the low velocity cavity, after electron-beam welding. This might reduce the accelerating gradient. Due to delays in manufacturing, the final performance tests will be carried out in the coming months.

  9. Improved PFB operations - 400-hour turbine test results

    Science.gov (United States)

    Rollbuhler, R. J.; Benford, S. M.; Zellars, G. R.

    1980-04-01

    The paper deals with a 400-hr small turbine test in the effluent of a pressurized fluidized bed (PFB) at an average temperature of 770 C, an average relative gas velocity of 300 m/sec, and average solid loadings of 200 ppm. Consideration is given to combustion parameters and operating procedure as well as to the turbine system and turbine test operating procedures. Emphasis is placed on erosion/corrosion results.

  10. Test Beam Results of a 3D Diamond Detector

    CERN Document Server

    Dunser, Marc

    2015-01-01

    3D pixel technology has been used successfully in the past with silicon detectors for tracking applications. Recently, a first prototype of the same 3D technology has been produced on a chemical vapour deposited single-crystal diamond sensor. This device has been subsequently tested in a beam test at CERN’s SPS accelerator in a beam of 120 GeV protons. Details on the production and results of testbeam data are presented.

  11. Creep in rock salt with temperature. Testing methods and results

    International Nuclear Information System (INIS)

    Charpentier, J.P.; Berest, P.

    1985-01-01

    The growing interest shown in the delayed behaviour of rocks at elevated temperature has led the Solid Mechanics Laboratory to develop specific equipment designed for creep tests. The design and dimensioning of these units offer the possibility of investigating a wide range of materials. The article describes the test facilities used (uni-axial and tri-axial creep units) and presents the experimental results obtained on samples of Bresse salt [fr

  12. Acoustic results of the Boeing model 360 whirl tower test

    Science.gov (United States)

    Watts, Michael E.; Jordan, David

    1990-09-01

    An evaluation is presented for whirl tower test results of the Model 360 helicopter's advanced, high-performance four-bladed composite rotor system intended to facilitate over-200-knot flight. During these performance measurements, acoustic data were acquired by seven microphones. A comparison of whirl-tower tests with theory indicate that theoretical prediction accuracies vary with both microphone position and the inclusion of ground reflection. Prediction errors varied from 0 to 40 percent of the measured signal-to-peak amplitude.

  13. Results of initial nuclear tests on LWBR (LWBR Development Program)

    International Nuclear Information System (INIS)

    Sarber, W.K.

    1979-06-01

    This report presents and discusses the results of physics tests performed at beginning of life on the Light Water Breeder Reactor (LWBR). These tests have confirmed that movable seed assembly critical positions and reactivity worths, temperature coefficients, xenon transient characteristics, core symmetry, and core shutdown are within the range of values used in the design of the LWBR and its reactor protection analysis. Measured core physics parameters were found to be in good agreement with the calculated values

  14. Wellbore inertial navigation system (WINS) software development and test results

    Energy Technology Data Exchange (ETDEWEB)

    Wardlaw, R. Jr.

    1982-09-01

    The structure and operation of the real-time software developed for the Wellbore Inertial Navigation System (WINS) application are described. The procedure and results of a field test held in a 7000-ft well in the Nevada Test Site are discussed. Calibration and instrumentation error compensation are outlined, as are design improvement areas requiring further test and development. Notes on Kalman filtering and complete program listings of the real-time software are included in the Appendices. Reference is made to a companion document which describes the downhole instrumentation package.

  15. Final report of the Buffer Mass Test - Volume I: Scope, preparative field work and test arrangement

    International Nuclear Information System (INIS)

    Pusch, R.; Nilsson, J.; Ramqvist, G.

    1985-07-01

    The Buffer Mass Test was conducted in a 30 m long drift at 340 m depth in the Stripa mine, The main objective being to check the predicted functions of certain bentonite-based buffer materials in rock environment. These materials were blocks of highly compacted sodium bentonite placed in large boreholes simulating deposition holes for canisters, and on-site compacted sand/bentonite mixtures used as tunnel backfill. The blocks of bentonite embedded electrical heaters which served to produce heat so as to create conditions similar to those in a repository. The temperature in the initially non-saturated buffer materials was expected to be a function of the water uptake from the rock, which was also assumed to lead to rather high swelling pressures. The recording of these processes and of the moistening of the buffer materials , as well as of the associated build-up of piezometric heads at rock/buffer interfaces, was the major item of the field test. For this purpose the buffer materials and the rock were equipped with a large number of thermal elements, pressure and piezometric cells as well as moisture sensors. The choise of positions and properties of these gauges, which were connected to an effective data acquisition system, was based on predictions that required a careful site documentation with respect to the fracture characteristics and hydrological properties of the surrounding rock. (author)

  16. Advanced Stirling Convertor Durability Testing: Plans and Interim Results

    Science.gov (United States)

    Meer, David W.; Oriti, Salvatore M.

    2012-01-01

    The U.S. Department of Energy (DOE), Lockheed Martin Corporation (LM), and NASA Glenn Research Center (GRC) have been developing the Advanced Stirling Radioisotope Generator (ASRG) for use as a power system for space science missions. In support of this program, GRC has been involved in testing Stirling convertors, including the Advanced Stirling Convertor (ASC), for use in the ASRG. This testing includes electromagnetic interference/compatibility (EMI/EMC), structural dynamics, advanced materials, organics, and unattended extended operation. The purpose of the durability tests is to experimentally demonstrate the margins in the ASC design. Due to the high value of the hardware, previous ASC tests focused on establishing baseline performance of the convertors within the nominal operating conditions. The durability tests present the first planned extension of the operating conditions into regions beyond those intended to meet the product spec, where the possibility exists of lateral contact, overstroke, or over-temperature events. These tests are not intended to cause damage that would shorten the life of the convertors, so they can transition into extended operation at the conclusion of the tests. This paper describes the four tests included in the durability test sequence: 1) start/stop cycling, 2) exposure to constant acceleration in the lateral and axial directions, 3) random vibration at increased piston amplitude to induce contact events, and 4) overstroke testing to simulate potential failures during processing or during the mission life where contact events could occur. The paper also summarizes the analysis and simulation used to predict the results of each of these tests.

  17. Results of patch testing in 10 patients with peristomal dermatitis.

    Science.gov (United States)

    Landis, Megan N; Keeling, James H; Yiannias, James A; Richardson, Donna M; Nordberg Linehan, Diane L; Davis, Mark D P

    2012-09-01

    Peristomal dermatitis is a common problem in patients with ostomies that is a source of considerable morbidity. Irritant contact dermatitis is most common, but allergic contact dermatitis can also occur. Because of the lack of published reports on patch testing for this indication, we undertook a retrospective study of patch testing results in patients with suspected peristomal allergic contact dermatitis. We sought to describe our patch testing experience with patients referred with peristomal dermatitis. This was a retrospective review of medical records of patients with ostomies and peristomal dermatitis who underwent patch testing in the Mayo Clinic Departments of Dermatology in Jacksonville, FL; Rochester, MN; and Scottsdale, AZ, during a 10-year period (2000-2010). Ten patients with peristomal dermatitis were referred for patch testing (6 in Minnesota, 2 in Florida, and 2 in Arizona). Patients were patch tested to the materials used in their stoma devices, to the standard series, and in some cases to supplemental series. All 10 had at least one allergic patch test reaction, most commonly to stoma paste (3 of 10 patients). Retrospective nature of study via chart review is a limitation. Patch testing is a useful tool for identification of allergens in patients with peristomal dermatitis. Copyright © 2011 American Academy of Dermatology, Inc. Published by Mosby, Inc. All rights reserved.

  18. Physical separations soil washing system cold test results

    Energy Technology Data Exchange (ETDEWEB)

    McGuire, J.P.

    1993-07-28

    This test summary describes the objectives, methodology, and results of a physical separations soil-washing system setup and shakedown test using uncontaminated soil. The test is being conducted in preparation for a treatability test to be conducted in the North Pond of the 300-FF-1 Operable Unit. It will be used to assess the feasibility of using a physical separations process to reduce the volume of contaminated soils in the 300-FF-1 Operable Unit. The test is described in DOE-RL (1993). The setup test was conducted at an uncontrolled area located approximately 3.2 km northwest of the 300-FF-1 Operable Unit. The material processed was free of contamination. The physical separation equipment to be used in the test was transferred to the US Department of Energy (DOE) by the US Environmental Protection Agency (EPA) Risk Reduction Engineering Laboratory. On May 13, 1993, soil-washing equipment was moved to the cold test location. Design assistance and recommendation for operation was provided by the EPA.

  19. LWR surveillance dosimetry improvement program: PSF metallurgical blind test results

    International Nuclear Information System (INIS)

    Kam, F.B.K.; Stallmann, F.W.; Guthrie, G.; McElroy, W.N.

    1985-01-01

    The ORR-PSF benchmark experiment was designed to simulate the surveillance capsule-pressure vessel configuration in power reactors and to test the validity of procedures which determine the radiation damage in the vessel from test results in the surveillance capsule. The PSF metallurgical blind test was initiated to give participants an opportunity to test their current embrittlement prediction methodologies. Experimental results were withheld from the participants except for the type of information which is normally contained in surveillance reports. Preliminary analysis of the PSF metallurgical blind test results shows that: (1) current prediction methodologies, as used by the PSF Blind Test participants, are adequate, falling within +- 20 0 C of the measured values for Δ NDT. None of the different methods is clearly superior; (2) the proposed revision of Reg. Guide 1.99 (Rev. 2) gives a better representation of the fluence and chemistry dependency of Δ NDT than the current version (Rev. 1); and (3) fluence rate effects can be seen but not quantified. Fluence spectral effects are too small to be detectable in this experiment. (orig.)

  20. Thermal Analysis of Low Layer Density Multilayer Insulation Test Results

    Science.gov (United States)

    Johnson, Wesley L.

    2011-01-01

    Investigation of the thermal performance of low layer density multilayer insulations is important for designing long-duration space exploration missions involving the storage of cryogenic propellants. Theoretical calculations show an analytical optimal layer density, as widely reported in the literature. However, the appropriate test data by which to evaluate these calculations have been only recently obtained. As part of a recent research project, NASA procured several multilayer insulation test coupons for calorimeter testing. These coupons were configured to allow for the layer density to be varied from 0.5 to 2.6 layer/mm. The coupon testing was completed using the cylindrical Cryostat-l00 apparatus by the Cryogenics Test Laboratory at Kennedy Space Center. The results show the properties of the insulation as a function of layer density for multiple points. Overlaying these new results with data from the literature reveals a minimum layer density; however, the value is higher than predicted. Additionally, the data show that the transition region between high vacuum and no vacuum is dependent on the spacing of the reflective layers. Historically this spacing has not been taken into account as thermal performance was calculated as a function of pressure and temperature only; however the recent testing shows that the data is dependent on the Knudsen number which takes into account pressure, temperature, and layer spacing. These results aid in the understanding of the performance parameters of MLI and help to complete the body of literature on the topic.

  1. Tank 241-T-105, cores 205 and 207 analytical results for the final report

    International Nuclear Information System (INIS)

    Esch, R.A.

    1997-01-01

    This document is the final laboratory report for tank 241-T-105 push mode core segments collected between June 24, 1997 and June 30, 1997. The segments were subsampled and analyzed in accordance with the Tank Push Mode Core Sampling and Analysis Plan (TSAP) (Field,1997), the Tank Safety Screening Data Quality Objective (Safety DQO) (Dukelow, et al., 1995) and Tank 241-T-105 Sample Analysis (memo) (Field, 1997a). The analytical results are included in Table 1. None of the subsamples submitted for the differential scanning calorimetry (DSC) analysis or total alpha activity (AT) exceeded the notification limits as stated in the TSAP (Field, 1997). The statistical results of the 95% confidence interval on the mean calculations are provided by the Tank Waste Remediation Systems (TWRS) Technical Basis Group in accordance with the Memorandum of Understanding (Schreiber, 1997) and not considered in this report

  2. Factors Affecting Result in Chinese Proficiency Test (HSK Level 6: Reading Section and Preparation Strategies

    Directory of Open Access Journals (Sweden)

    Sri Haryanti

    2013-11-01

    Full Text Available Chinese Proficiency Test (HSK is an internationally standardized exam which tests and rates Chinese language proficiency. The highest level in this test is level 6. The writing part of the test consists of 3 (three parts, namely, (1 listening, (2 reading, (3 writing. Furthermore, the reading part is made of 4 components. Level 6 of this test implies a high degree of difficulty. This paper specifically looked on how to prepare effectively for participants to be able to work on the reading part in order to achieve best result. This article used the methods of literature review and observational study as well as field research and would also incorporate the author’s personal experience in taking the test into recommending strategies for doing the reading part in a level 6 HSK test. Finally, research suggested several techniques and tips that might assist participants in achieving maximum scores in handling the reading part of level 6 HSK test.

  3. 77 FR 67332 - Certain Steel Threaded Rod From the People's Republic of China: Final Results and Final Partial...

    Science.gov (United States)

    2012-11-09

    ... Value for Hydrochloric Acid (3) Surrogate Financial Ratios Comment 2. Correcting the Harmonized Tariff...'') April 1, 2010, through March 31, 2011.\\1\\ Based upon our analysis of the comments and information... parties were further provided an opportunity to comment on the Preliminary Results. Between July 17 and...

  4. Spent fuel drying system test results (first dry-run)

    International Nuclear Information System (INIS)

    Klinger, G.S.; Oliver, B.M.; Abrefah, J.; Marschman, S.C.; MacFarlan, P.J.; Ritter, G.A.

    1998-07-01

    The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks in the basin have been detected and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuel elements in an interim storage facility on the Hanford Site. Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 7.0) have been conducted by Pacific Northwest National Laboratory (PNNL) on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of the first dry-run test, which was conducted without a fuel element. The empty test apparatus was subjected to a combination of low- and high-temperature vacuum drying treatments that were intended to mimic, wherever possible, the fuel treatment strategies of the IPS. The data from this dry-run test can serve as a baseline for the first two fuel element tests, 1990 (Run 1) and 3128W (Run 2). The purpose of this dry-run was to establish the background levels of hydrogen in the system, and the hydrogen generation and release characteristics attributable to the test system without a fuel element present. This test also serves to establish the background levels of water in the system and the water release characteristics. The system used for the drying test series was the Whole Element Furnace Testing System, described in Section 2.0, which is located in the Postirradiation Testing Laboratory (PTL, 327 Building). The test conditions and methodology are given in section 3.0, and the experimental

  5. Small-Scale Spray Releases: Initial Aerosol Test Results

    Energy Technology Data Exchange (ETDEWEB)

    Mahoney, Lenna A.; Gauglitz, Phillip A.; Kimura, Marcia L.; Brown, Garrett N.; Kurath, Dean E.; Buchmiller, William C.; Smith, Dennese M.; Blanchard, Jeremy; Song, Chen; Daniel, Richard C.; Wells, Beric E.; Tran, Diana N.; Burns, Carolyn A.

    2013-05-29

    One of the events postulated in the hazard analysis at the Waste Treatment and Immobilization Plant (WTP) and other U.S. Department of Energy (DOE) nuclear facilities is a breach in process piping that produces aerosols with droplet sizes in the respirable range. The current approach for predicting the size and concentration of aerosols produced in a spray leak involves extrapolating from correlations reported in the literature. These correlations are based on results obtained from small engineered spray nozzles using pure liquids with Newtonian fluid behavior. The narrow ranges of physical properties on which the correlations are based do not cover the wide range of slurries and viscous materials that will be processed in the WTP and across processing facilities in the DOE complex. Two key technical areas were identified where testing results were needed to improve the technical basis by reducing the uncertainty due to extrapolating existing literature results. The first technical need was to quantify the role of slurry particles in small breaches where the slurry particles may plug and result in substantially reduced, or even negligible, respirable fraction formed by high-pressure sprays. The second technical need was to determine the aerosol droplet size distribution and volume from prototypic breaches and fluids, specifically including sprays from larger breaches with slurries where data from the literature are scarce. To address these technical areas, small- and large-scale test stands were constructed and operated with simulants to determine aerosol release fractions and net generation rates from a range of breach sizes and geometries. The properties of the simulants represented the range of properties expected in the WTP process streams and included water, sodium salt solutions, slurries containing boehmite or gibbsite, and a hazardous chemical simulant. The effect of antifoam agents was assessed with most of the simulants. Orifices included round holes and

  6. The CANopen Controller IP Core: Implementation, Synthesis and Test Results

    Science.gov (United States)

    Caramia, Maurizio; Bolognino, Luca; Montagna, Mario; Tosi, Pietro; Errico, Walter; Bigongiari, Franco; Furano, Gianluca

    2011-08-01

    This paper will describe the implementation and test results of the CANopen Controller IP Core (CCIPC) implemented by Thales Alenia Space and SITAEL Aerospace with the support of ESA in the frame of the EXOMARS Project. The CCIPC is a configurable VHDL implementation of the CANOPEN protocol [1]; it is foreseen to be used as CAN bus slave controller within the EXOMARS Entry Descending and Landing Demonstrato Module (EDM) and Rover Module. The CCIPC features, configuration capability, synthesis and test results will be described and the evidence of the state of maturity of this innovative IP core will be demonstrated.

  7. Buckling Test Results from the 8-Foot-Diameter Orthogrid-Stiffened Cylinder Test Article TA01. [Test Dates: 19-21 November 2008

    Science.gov (United States)

    Hilburger, Mark W.; Waters, W. Allen, Jr.; Haynie, Waddy T.

    2015-01-01

    Results from the testing of cylinder test article SBKF-P2-CYLTA01 (referred to herein as TA01) are presented. The testing was conducted at the Marshall Space Flight Center (MSFC), November 19?21, 2008, in support of the Shell Buckling Knockdown Factor (SBKF) Project.i The test was used to verify the performance of a newly constructed buckling test facility at MSFC and to verify the test article design and analysis approach used by the SBKF project researchers. TA01 is an 8-foot-diameter (96-inches), 78.0-inch long, aluminum-lithium (Al-Li), orthogrid-stiffened cylindrical shell similar to those used in current state-of-the-art launch vehicle structures and was designed to exhibit global buckling when subjected to compression loads. Five different load sequences were applied to TA01 during testing and included four sub-critical load sequences, i.e., loading conditions that did not cause buckling or material failure, and one final load sequence to buckling and collapse. The sub-critical load sequences consisted of either uniform axial compression loading or combined axial compression and bending and the final load sequence subjected TA01 to uniform axial compression. Traditional displacement transducers and strain gages were used to monitor the test article response at nearly 300 locations and an advanced digital image correlation system was used to obtain low-speed and high-speed full-field displacement measurements of the outer surface of the test article. Overall, the test facility and test article performed as designed. In particular, the test facility successfully applied all desired load combinations to the test article and was able to test safely into the postbuckling range of loading, and the test article failed by global buckling. In addition, the test results correlated well with initial pretest predictions.

  8. Large coil task and results of testing US coils

    International Nuclear Information System (INIS)

    Haubenreich, P.N.

    1986-01-01

    The United States, EURATOM, Japan, and Switzerland have collaborated since 1978 in development of superconducting toroidal field coils for fusion reactor applications. The United States provided a test facility nd three coils; the other participants, one coil each. All coils have the same interface dimensions and performance requirements (stable at 8 T), but internal design was decided by each team. Two US coil teams chose bath-cooled NbTi, 10-kA conductors. One developed a Nb 3 Sn conductor, cooled by internal flow, rated at 18 kA. All US coils have diagnostic instrumentation and imbedded heaters that enable stability tests and simulated nuclear heating experiments. In single-coil tests, each coil operated at full current in self-field (6.4 T). In six-coil tests that began in July 1986, one US coil and the Japanese coil hve been successfully operated at full current at 8 T. The other coils have operated as background coils while awaiting their turn as test coil. Coil tests have been informative and results gratifying. The facility has capably supported coil testing and its operation has provided information that will be useful in designing future fusion systems. Coil capabilities beyond nominal design points will be determined

  9. Healthy Efficient New Gas Homes (HENGH) Pilot Test Results

    Energy Technology Data Exchange (ETDEWEB)

    Chan, Wanyu R. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Maddalena, Randy L [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Stratton, Chris [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Hotchi, Toshifumi [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Singer, Brett C. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Walker, Iain S. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Sherman, Max H. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2016-05-01

    The Healthy Efficient New Gas Homes (HENGH) is a field study that will collect data on ventilation systems and indoor air quality (IAQ) in new California homes that were built to 2008 Title 24 standards. A pilot test was performed to help inform the most time and cost effective approaches to measuring IAQ in the 100 test homes that will be recruited for this study. Two occupied, single-family detached homes built to 2008 Title 24 participated in the pilot test. One of the test homes uses exhaust-only ventilation provided by a continuous exhaust fan in the laundry room. The other home uses supply air for ventilation. Measurements of IAQ were collected for two weeks. Time-resolved concentrations of particulate matter (PM), nitrogen dioxide (NO2), carbon dioxide (CO2), carbon monoxide (CO), and formaldehyde were measured. Measurements of IAQ also included time-integrated concentrations of volatile organic compounds (VOCs), volatile aldehydes, and NO2. Three perfluorocarbon tracers (PFTs) were used to estimate the dilution rate of an indoor emitted air contaminant in the two pilot test homes. Diagnostic tests were performed to measure envelope air leakage, duct leakage, and airflow of range hood, exhaust fans, and clothes dryer vent when accessible. Occupant activities, such as cooking, use of range hood and exhaust fans, were monitored using various data loggers. This document describes results of the pilot test.

  10. Test results of the SMES model coil. Pulse performance

    International Nuclear Information System (INIS)

    Hamajima, Takataro; Shimada, Mamoru; Ono, Michitaka

    1998-01-01

    A model coil for superconducting magnetic energy storage (SMES model coil) has been developed to establish the component technologies needed for a small-scale 100 kWh SMES device. The SMES model coil was fabricated, and then performance tests were carried out in 1996. The coil was successfully charged up to around 30 kA and down to zero at the same ramp rate of magnetic field experienced in a 100 kWh SMES device. AC loss in the coil was measured by an enthalpy method as parameters of ramp rate and flat top current. The results were evaluated by an analysis and compared with short-sample test results. The measured hysteresis loss is in good agreement with that estimated from the short-sample results. It was found that the coupling loss of the coil consists of two major coupling time constants. One is a short time constant of about 200 ms, which is in agreement with the test results of a short real conductor. The other is a long time constant of about 30 s, which could not be expected from the short sample test results. (author)

  11. LWR aerosol containment experiments (LACE) program and initial test results

    International Nuclear Information System (INIS)

    Muhlestein, L.D.; Hilliard, R.K.; Bloom, G.R.; McCormack, J.D.; Rahn, F.J.

    1985-01-01

    The LWR aerosol containment experiments (LACE) program is described. The LACE program is being performed at the Hanford Engineer Development Laboratory (operated by Westinghouse Hanford Company) and the initial tests are sponsored by EPRI. The objectives of the LACE program are: to demonstrate, at large-scale, inherent radioactive aerosol retention behavior for postulated high consequence LWR accident situations; and to provide a data base to be used for aerosol behavior . Test results from the first phase of the LACE program are presented and discussed. Three large-scale scoping tests, simulating a containment bypass accident sequence, demonstrated the extent of agglomeration and deposition of aerosols occurring in the pipe pathway and vented auxiliary building under realistic accident conditions. Parameters varied during the scoping tests were aerosol type and steam condensation

  12. Selected Test Results from the Encell Technology Nickel Iron Battery

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, Summer Kamal Rhodes [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Advanced Power Sources R& D; Baca, Wes Edmund [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Advanced Power Sources R& D; Avedikian, Kristan [Encell Technology, Alachua, FL (United States)

    2014-09-01

    The performance of the Encell Nickel Iron (NiFe) battery was measured. Tests included capacity, capacity as a function of rate, capacity as a function of temperature, charge retention (28-day), efficiency, accelerated life projection, and water refill evaluation. The goal of this work was to evaluate the general performance of the Encell NiFe battery technology for stationary applications and demonstrate the chemistry's capabilities in extreme conditions. Test results have indicated that the Encell NiFe battery technology can provide power levels up to the 6C discharge rate, ampere-hour efficiency above 70%. In summary, the Encell batteries have met performance metrics established by the manufacturer. Long-term cycle tests are not included in this report. A cycle test at elevated temperature was run, funded by the manufacturer, which Encell uses to predict long-term cycling performance, and which passed their prescribed metrics.

  13. Results of assembly test of HTTR reactor internals

    International Nuclear Information System (INIS)

    Maruyama, S.; Saikusa, A.; Shiozawa, S.; Tsuji, N.; Miki, T.

    1996-01-01

    The assembly test of the HTTR actual reactor internals had been carried out at the works, prior to their installation in the actual reactor pressure vessel(RPV) at the construction site. The assembly test consists of several items such as examining fabricating precision of each component and alignment of piled-up structures, measuring circumferential coolant velocity profile in the passage between the simulated RPV and the reactor internals as well as under the support plates, measuring by-pass flow rate through gaps between the reactor internals, and measuring the binding force of the core restraint mechanism. Results of the test showed good performance of the HTTR reactor internals. Installation of the reactor internals in the actual RPV was started at the construction site of HTTR in April, 1995. In the installation process, main items of the assembly test at the works were repeated to investigate the reproducibility of installation. (author). 5 refs, 11 figs

  14. Small-Scale Spray Releases: Initial Aerosol Test Results

    Energy Technology Data Exchange (ETDEWEB)

    Mahoney, Lenna A.; Gauglitz, Phillip A.; Kimura, Marcia L.; Brown, Garrett N.; Kurath, Dean E.; Buchmiller, William C.; Smith, Dennese M.; Blanchard, Jeremy; Song, Chen; Daniel, Richard C.; Wells, Beric E.; Tran, Diana N.; Burns, Carolyn A.

    2012-11-01

    One of the events postulated in the hazard analysis at the Waste Treatment and Immobilization Plant (WTP) and other U.S. Department of Energy (DOE) nuclear facilities is a breach in process piping that produces aerosols with droplet sizes in the respirable range. The current approach for predicting the size and concentration of aerosols produced in a spray leak involves extrapolating from correlations reported in the literature. These correlations are based on results obtained from small engineered spray nozzles using pure liquids with Newtonian fluid behavior. The narrow ranges of physical properties on which the correlations are based do not cover the wide range of slurries and viscous materials that will be processed in the WTP and across processing facilities in the DOE complex. Two key technical areas were identified where testing results were needed to improve the technical basis by reducing the uncertainty due to extrapolating existing literature results. The first technical need was to quantify the role of slurry particles in small breaches where the slurry particles may plug and result in substantially reduced, or even negligible, respirable fraction formed by high-pressure sprays. The second technical need was to determine the aerosol droplet size distribution and volume from prototypic breaches and fluids, specifically including sprays from larger breaches with slurries where data from the literature are scarce. To address these technical areas, small- and large-scale test stands were constructed and operated with simulants to determine aerosol release fractions and generation rates from a range of breach sizes and geometries. The properties of the simulants represented the range of properties expected in the WTP process streams and included water, sodium salt solutions, slurries containing boehmite or gibbsite, and a hazardous chemical simulant. The effect of anti-foam agents was assessed with most of the simulants. Orifices included round holes and

  15. Wind tunnel test IA300 analysis and results, volume 1

    Science.gov (United States)

    Kelley, P. B.; Beaufait, W. B.; Kitchens, L. L.; Pace, J. P.

    1987-01-01

    The analysis and interpretation of wind tunnel pressure data from the Space Shuttle wind tunnel test IA300 are presented. The primary objective of the test was to determine the effects of the Space Shuttle Main Engine (SSME) and the Solid Rocket Booster (SRB) plumes on the integrated vehicle forebody pressure distributions, the elevon hinge moments, and wing loads. The results of this test will be combined with flight test results to form a new data base to be employed in the IVBC-3 airloads analysis. A secondary objective was to obtain solid plume data for correlation with the results of gaseous plume tests. Data from the power level portion was used in conjunction with flight base pressures to evaluate nominal power levels to be used during the investigation of changes in model attitude, eleveon deflection, and nozzle gimbal angle. The plume induced aerodynamic loads were developed for the Space Shuttle bases and forebody areas. A computer code was developed to integrate the pressure data. Using simplified geometrical models of the Space Shuttle elements and components, the pressure data were integrated to develop plume induced force and moments coefficients that can be combined with a power-off data base to develop a power-on data base.

  16. Potential for false positive HIV test results with the serial rapid HIV testing algorithm

    Directory of Open Access Journals (Sweden)

    Baveewo Steven

    2012-03-01

    Full Text Available Abstract Background Rapid HIV tests provide same-day results and are widely used in HIV testing programs in areas with limited personnel and laboratory infrastructure. The Uganda Ministry of Health currently recommends the serial rapid testing algorithm with Determine, STAT-PAK, and Uni-Gold for diagnosis of HIV infection. Using this algorithm, individuals who test positive on Determine, negative to STAT-PAK and positive to Uni-Gold are reported as HIV positive. We conducted further testing on this subgroup of samples using qualitative DNA PCR to assess the potential for false positive tests in this situation. Results Of the 3388 individuals who were tested, 984 were HIV positive on two consecutive tests, and 29 were considered positive by a tiebreaker (positive on Determine, negative on STAT-PAK, and positive on Uni-Gold. However, when the 29 samples were further tested using qualitative DNA PCR, 14 (48.2% were HIV negative. Conclusion Although this study was not primarily designed to assess the validity of rapid HIV tests and thus only a subset of the samples were retested, the findings show a potential for false positive HIV results in the subset of individuals who test positive when a tiebreaker test is used in serial testing. These findings highlight a need for confirmatory testing for this category of individuals.

  17. Test-beam results of a SOI pixel detector prototype

    CERN Document Server

    Bugiel, Roma; Dannheim, Dominik; Fiergolski, Adrian; Hynds, Daniel; Idzik, Marek; Kapusta, P; Kucewicz, Wojciech; Munker, Ruth Magdalena; Nurnberg, Andreas Matthias

    2018-01-01

    This paper presents the test-beam results of a monolithic pixel-detector prototype fabricated in 200 nm Silicon-On-Insulator (SOI) CMOS technology. The SOI detector was tested at the CERN SPS H6 beam line. The detector is fabricated on a 500 μm thick high-resistivity float- zone n-type (FZ-n) wafer. The pixel size is 30 μm × 30 μm and its readout uses a source- follower configuration. The test-beam data are analysed in order to compute the spatial resolution and detector efficiency. The analysis chain includes pedestal and noise calculation, cluster reconstruction, as well as alignment and η-correction for non-linear charge sharing. The results show a spatial resolution of about 4.3 μm.

  18. Results for the Brine Evaporation Bag (BEB) Brine Processing Test

    Science.gov (United States)

    Delzeit, Lance; Flynn, Michael; Fisher, John; Shaw, Hali; Kawashima, Brian; Beeler, David; Howard, Kevin

    2015-01-01

    The recent Brine Processing Test compared the NASA Forward Osmosis Brine Dewatering (FOBD), Paragon Ionomer Water Processor (IWP), UMPQUA Ultrasonic Brine Dewatering System (UBDS), and the NASA Brine Evaporation Bag (BEB). This paper reports the results of the BEB. The BEB was operated at 70 deg C and a base pressure of 12 torr. The BEB was operated in a batch mode, and processed 0.4L of brine per batch. Two different brine feeds were tested, a chromic acid-urine brine and a chromic acid-urine-hygiene mix brine. The chromic acid-urine brine, known as the ISS Alternate Pretreatment Brine, had an average processing rate of 95 mL/hr with a specific power of 5kWhr/L. The complete results of these tests will be reported within this paper.

  19. Rise-to-power test in High Temperature Engineering Test Reactor. Test progress and summary of test results up to 30 MW of reactor thermal power

    International Nuclear Information System (INIS)

    Nakagawa, Shigeaki; Fujimoto, Nozomu; Shimakawa, Satoshi

    2002-08-01

    The High Temperature Engineering Test Reactor (HTTR) is a graphite moderated and gas cooled reactor with the thermal power of 30 MW and the reactor outlet coolant temperature of 850degC/950degC. Rise-to-power test in the HTTR was performed from April 23rd to June 6th in 2000 as phase 1 test up to 10 MW in the rated operation mode, from January 29th to March 1st in 2001 as phase 2 test up to 20 MW in the rated operation mode and from April 14th to June 8th in 2001 as phase 3 test up to 20 MW in the high temperature test the mechanism of the reactor outlet coolant temperature becomes 850degC at 30 MW in the rated operation mode and 950degC in the high temperature test operation mode. Phase 4 rise-to-power test to achieve the thermal reactor power of 30 MW started on October 23rd in 2001. On December 7th in 2001 it was confirmed that the thermal reactor power and the reactor outlet coolant temperature reached to 30 MW and 850degC respectively in the single loaded operation mode in which only the primary pressurized water cooler is operating. Phase 4 test was performed until March 6th in 2002. JAERI (Japan Atomic Energy Research Institute) obtained the certificate of the pre-operation test from MEXT (Ministry of Education Culture Sports Science and Technology) after all the pre-operation tests by MEXT were passed successfully with the reactor transient test at an abnormal event as a final pre-operation test. From the test results of the rise-up-power test up to 30 MW in the rated operation mode, performance of the reactor and cooling system were confirmed, and it was also confirmed that an operation of reactor facility can be performed safely. Some problems to be solved were found through the tests. By solving them, the reactor operation with the reactor outlet coolant temperature of 950degC will be achievable. (author)

  20. 75 FR 64254 - Certain Hot-Rolled Flat-Rolled Carbon Quality Steel Products From Brazil; Final Results of...

    Science.gov (United States)

    2010-10-19

    ...-Rolled Carbon Quality Steel Products From Brazil; Final Results of Antidumping Duty Administrative Review... for the Final Results, 75 FR 19369 (April 14, 2010) (Preliminary Results). This review covers sales of... Products from Brazil,'' dated June 22, 2010 (USIMINAS Sales Verification Report). Following the release of...

  1. 75 FR 70212 - Chlorinated Isocyanurates From the People's Republic of China: Final Results of 2008-2009...

    Science.gov (United States)

    2010-11-17

    ...; see also Final Surrogate Value Memo. We revised the surrogate financial ratio calculations by making... comment on our preliminary results. Based on our analysis of the comments received, we have made changes to our margin calculations. Therefore, the final results differ from the preliminary results. The...

  2. Preliminary results of testing bioassay analytical performance standards

    International Nuclear Information System (INIS)

    Fisher, D.R.; Robinson, A.V.; Hadley, R.T.

    1983-08-01

    The analytical performance of both in vivo and in vitro bioassay laboratories is being studied to determine the capability of these laboratories to meet the minimum criteria for accuracy and precision specified in the draft ANSI Standard N13.30, Performance Criteria for Radiobioassay. This paper presents preliminary results of the first round of testing

  3. Pattern Of Skin Prick Allergy Test Results In Enugu | Mgbor ...

    African Journals Online (AJOL)

    In this study we report on pattern of allergy prick skin test results found among atopic patients attending the department of otorhinolargngology of the University of Nigeria Teaching Hospital Enugu and Hansa Clinics, Enugu and propose ways of minimizing the exposure of the population to allergens. Material and method

  4. Recent results on the RIA test in IGR reactor

    International Nuclear Information System (INIS)

    Asmolov, V.; Yegorova, L.

    1997-01-01

    At the 23d WRSM meeting the data base characterizing results of VVER high burnup fuel rods tests under reactivity-initiated accident (RIA) conditions was presented. Comparison of PWR and VVER failure thresholds was given also. Additional analysis of the obtained results was being carried out during 1996. The results of analysis show that the two different failure mechanisms were observed for PWR and VVER fuel rods. Some factors which can be as the possible reasons of these differences are presented. First of them is the state of preirradiated cladding. Published test data for PWR high burnup fuel rods demonstrated that the PWR high burnup fuel rods failed at the RIA test are characterized by very high level of oxidation and hydriding for the claddings. Corresponding researches were performed at Institute of Atomic Reactors (RLAR, Dimitrovgrad, Russia) for large set of VVER high burnup fuel rods. Results of these investigations show that preirradiated commercial Zr-1%Nb claddings practically keep their initial levels of oxidation and H 2 concentration. Consequently the VVER preirradiated cladding must keep the high level of mechanical properties. The second reason leading to differences between failure mechanisms for two types of high burnup fuel rods can be the test conditions. Now such kind of analysis have been performed by two methods

  5. Interpretation of Chemical Pathology Test Results in Paediatrics ...

    African Journals Online (AJOL)

    At any time we interprete paediatric chemical pathology test results we must take into consideration a number of factors, which are related with and restricted to paediatric patients. Such factors include the paediatric patient's age that may change from prematurity to above 18 years, and the paediatric patient's body weight ...

  6. VEGETABLE OILS AS SUBSTITUTION FOR DIESEL OIL Test results ...

    African Journals Online (AJOL)

    Test results obtained on a Diesel Engine with direct injection. W. Scheer, Professor ... High kinematic viscosities, high flash points and high ... nozzle and in the combustion chamber. This is ... speed, fuel consumption and exhaust tempera· tures. ... it enters the fuel system of the engine. An one ..... Internal publi- cation of ...

  7. SIMS prototype System 3 test results: engineering analysis

    Energy Technology Data Exchange (ETDEWEB)

    1978-08-01

    The results obtained during testing of a closed hydronic drain down solar system designed for space and hot water heating are presented. Data analysis is included which documents the system performance and verifies the suitability of SIMS Prototype System 3 for field installation.

  8. Multi-bundle shashlik calorimeter prototypes beam-test results

    International Nuclear Information System (INIS)

    Badier, J.; Bloch, P.; Bityukov, S.; Bordalo, P.; Busson, P.; Charlot, C.; Dobrzynski, L.; Golutvin, I.; Guschin, E.; Issakov, V.; Ivanchenko, I.; Klimenko, V.; Marin, V.; Moissenz, P.; Obraztsov, V.; Ostankov, A.; Popov, V.; Puljak, I.; Ramos, S.; Seez, C.; Sergueev, S.; Soushkov, V.; Tanaka, R.; Varela, J.; Virdee, T.S.; Zaitchenko, A.; Zamiatin, N.

    1995-01-01

    The first beam-test results for two- and three-bundle shashlik tower prototypes are described. We found that the spatial resolution, the uniformity of energy response, the calorimeter reliability and hermeticity and also two showers separation are improved in multi-bundle design approach. ((orig.))

  9. SIMS prototype system 3 test results: Engineering analysis

    Science.gov (United States)

    1978-01-01

    The results obtained during testing of a closed hydronic drain down solar system designed for space and hot water heating is presented. Data analysis is included which documents the system performance and verifies the suitability of SIMS Prototype System 3 for field installation.

  10. Results of the Intelligence Test for Visually Impaired Children (ITVIC).

    Science.gov (United States)

    Dekker, R.; And Others

    1991-01-01

    Statistical analyses of scores on subtests of the Intelligence Test for Visually Impaired Children were done for two groups of children, either with or without usable vision. Results suggest that the battery has differential factorial and predictive validity. (Author/DB)

  11. DEWATERING TREATMENT SCALE-UP TESTING RESULTS OF HANFORD TANK WASTES

    International Nuclear Information System (INIS)

    TEDESCHI AR

    2008-01-01

    This report documents CH2M HILL Hanford Group Inc. (CH2M HILL) 2007 dryer testing results in Richland, WA at the AMEC Nuclear Ltd., GeoMelt Division (AMEC) Horn Rapids Test Site. It provides a discussion of scope and results to qualify the dryer system as a viable unit-operation in the continuing evaluation of the bulk vitrification process. A 10,000 liter (L) dryer/mixer was tested for supplemental treatment of Hanford tank low-activity wastes, drying and mixing a simulated non-radioactive salt solution with glass forming minerals. Testing validated the full scale equipment for producing dried product similar to smaller scale tests, and qualified the dryer system for a subsequent integrated dryer/vitrification test using the same simulant and glass formers. The dryer system is planned for installation at the Hanford tank farms to dry/mix radioactive waste for final treatment evaluation of the supplemental bulk vitrification process

  12. Large-Scale Spray Releases: Initial Aerosol Test Results

    Energy Technology Data Exchange (ETDEWEB)

    Schonewill, Philip P.; Gauglitz, Phillip A.; Bontha, Jagannadha R.; Daniel, Richard C.; Kurath, Dean E.; Adkins, Harold E.; Billing, Justin M.; Burns, Carolyn A.; Davis, James M.; Enderlin, Carl W.; Fischer, Christopher M.; Jenks, Jeromy WJ; Lukins, Craig D.; MacFarlan, Paul J.; Shutthanandan, Janani I.; Smith, Dennese M.

    2012-12-01

    One of the events postulated in the hazard analysis at the Waste Treatment and Immobilization Plant (WTP) and other U.S. Department of Energy (DOE) nuclear facilities is a breach in process piping that produces aerosols with droplet sizes in the respirable range. The current approach for predicting the size and concentration of aerosols produced in a spray leak involves extrapolating from correlations reported in the literature. These correlations are based on results obtained from small engineered spray nozzles using pure liquids with Newtonian fluid behavior. The narrow ranges of physical properties on which the correlations are based do not cover the wide range of slurries and viscous materials that will be processed in the WTP and across processing facilities in the DOE complex. Two key technical areas were identified where testing results were needed to improve the technical basis by reducing the uncertainty due to extrapolating existing literature results. The first technical need was to quantify the role of slurry particles in small breaches where the slurry particles may plug and result in substantially reduced, or even negligible, respirable fraction formed by high-pressure sprays. The second technical need was to determine the aerosol droplet size distribution and volume from prototypic breaches and fluids, specifically including sprays from larger breaches with slurries where data from the literature are scarce. To address these technical areas, small- and large-scale test stands were constructed and operated with simulants to determine aerosol release fractions and generation rates from a range of breach sizes and geometries. The properties of the simulants represented the range of properties expected in the WTP process streams and included water, sodium salt solutions, slurries containing boehmite or gibbsite, and a hazardous chemical simulant. The effect of anti-foam agents was assessed with most of the simulants. Orifices included round holes and

  13. Space Launch System Base Heating Test: Experimental Operations & Results

    Science.gov (United States)

    Dufrene, Aaron; Mehta, Manish; MacLean, Matthew; Seaford, Mark; Holden, Michael

    2016-01-01

    NASA's Space Launch System (SLS) uses four clustered liquid rocket engines along with two solid rocket boosters. The interaction between all six rocket exhaust plumes will produce a complex and severe thermal environment in the base of the vehicle. This work focuses on a recent 2% scale, hot-fire SLS base heating test. These base heating tests are short-duration tests executed with chamber pressures near the full-scale values with gaseous hydrogen/oxygen engines and RSRMV analogous solid propellant motors. The LENS II shock tunnel/Ludwieg tube tunnel was used at or near flight duplicated conditions up to Mach 5. Model development was based on the Space Shuttle base heating tests with several improvements including doubling of the maximum chamber pressures and duplication of freestream conditions. Test methodology and conditions are presented, and base heating results from 76 runs are reported in non-dimensional form. Regions of high heating are identified and comparisons of various configuration and conditions are highlighted. Base pressure and radiometer results are also reported.

  14. Graphite electrode arc melter demonstration Phase 2 test results

    International Nuclear Information System (INIS)

    Soelberg, N.R.; Chambers, A.G.; Anderson, G.L.; O'Connor, W.K.; Oden, L.L.; Turner, P.C.

    1996-06-01

    Several U.S. Department of Energy organizations and the U.S. Bureau of Mines have been collaboratively conducting mixed waste treatment process demonstration testing on the near full-scale graphite electrode submerged arc melter system at the Bureau's Albany (Oregon) Research Center. An initial test series successfully demonstrated arc melter capability for treating surrogate incinerator ash of buried mixed wastes with soil. The conceptual treatment process for that test series assumed that buried waste would be retrieved and incinerated, and that the incinerator ash would be vitrified in an arc melter. This report presents results from a recently completed second series of tests, undertaken to determine the ability of the arc melter system to stably process a wide range of open-quotes as-receivedclose quotes heterogeneous solid mixed wastes containing high levels of organics, representative of the wastes buried and stored at the Idaho National Engineering Laboratory (INEL). The Phase 2 demonstration test results indicate that an arc melter system is capable of directly processing these wastes and could enable elimination of an up-front incineration step in the conceptual treatment process

  15. Graphite electrode arc melter demonstration Phase 2 test results

    Energy Technology Data Exchange (ETDEWEB)

    Soelberg, N.R.; Chambers, A.G.; Anderson, G.L.; O`Connor, W.K.; Oden, L.L.; Turner, P.C.

    1996-06-01

    Several U.S. Department of Energy organizations and the U.S. Bureau of Mines have been collaboratively conducting mixed waste treatment process demonstration testing on the near full-scale graphite electrode submerged arc melter system at the Bureau`s Albany (Oregon) Research Center. An initial test series successfully demonstrated arc melter capability for treating surrogate incinerator ash of buried mixed wastes with soil. The conceptual treatment process for that test series assumed that buried waste would be retrieved and incinerated, and that the incinerator ash would be vitrified in an arc melter. This report presents results from a recently completed second series of tests, undertaken to determine the ability of the arc melter system to stably process a wide range of {open_quotes}as-received{close_quotes} heterogeneous solid mixed wastes containing high levels of organics, representative of the wastes buried and stored at the Idaho National Engineering Laboratory (INEL). The Phase 2 demonstration test results indicate that an arc melter system is capable of directly processing these wastes and could enable elimination of an up-front incineration step in the conceptual treatment process.

  16. Comparison of transient PCRV model test results with analysis

    International Nuclear Information System (INIS)

    Marchertas, A.H.; Belytschko, T.B.

    1979-01-01

    Comparisons are made of transient data derived from simple models of a reactor containment vessel with analytical solutions. This effort is a part of the ongoing process of development and testing of the DYNAPCON computer code. The test results used in these comparisons were obtained from scaled models of the British sodium cooled fast breeder program. The test structure is a scaled model of a cylindrically shaped reactor containment vessel made of concrete. This concrete vessel is prestressed axially by holddown bolts spanning the top and bottom slabs along the cylindrical walls, and is also prestressed circumferentially by a number of cables wrapped around the vessel. For test purposes this containment vessel is partially filled with water, which comes in direct contact with the vessel walls. The explosive charge is immersed in the pool of water and is centrally suspended from the top of the vessel. The tests are very similar to the series of tests made for the COVA experimental program, but the vessel here is the prestressed concrete container. (orig.)

  17. 688,112 statistical results: Content mining psychology articles for statistical test results

    OpenAIRE

    Hartgerink, C.H.J.

    2016-01-01

    In this data deposit, I describe a dataset that is the result of content mining 167,318 published articles for statistical test results reported according to the standards prescribed by the American Psychological Association (APA). Articles published by the APA, Springer, Sage, and Taylor & Francis were included (mining from Wiley and Elsevier was actively blocked). As a result of this content mining, 688,112 results from 50,845 articles were extracted. In order to provide a comprehensive set...

  18. Results of MACE tests M0 and M1

    International Nuclear Information System (INIS)

    Spencer, B.W.; Farmer, M.T.; Armstrong, D.R.; Kilsdonk, D.J.; Aeschlimann, R.W.; Fischer, M.

    1992-01-01

    This document discusses the Melt Attack and Coolability Experiment (MACE) Program underway at Argonne National Laboratory under ACE/EPRI sponsorship. The program addresses the efficacy of water to terminate an accident situation if melt progression were to result in a molten core/concrete interaction (MCCI) in the reactor containment. Large-scale experiments are being conducted in parallel with related modeling efforts, involving the addition of water to an MCI already underway. The experiments utilize UO 2 /ZrO 2 /Zr corium mixtures, direct electrical heating for simulation of decay heating, and various types of concrete basemats. Currently the tests involve 430 kg corium mass, 25 cm depth, in a 50 cm square test section. Test MO was a successful scoping test, but the first full size test, Ml, failed to achieve melt-water contact owing to existence of a preexisting bridge crust of corium charge. A heat flux of 3.5 MW/m 2 was measured in MO which removed energy from the corium pool equivalent to its entire heat of solidification prior to abatement by formation of an interfacial crust. The crust subsequently limited heat extraction to 600 kW/m 2 and less. Both tests MO and Ml revealed physical evidence of large pool swelling events which resulted in extrusion (and ejection) of melt into water above the crust, significantly increasing the overall quench and reducing the remaining melt in contact with the concrete. Furthermore, test Ml provided evidence of occasional ''burst mode'' ablation events and one additional important benefit of overlying water -- aerosol capture

  19. GTS Duratek, phase I Hanford low-level waste melter tests: Final report

    International Nuclear Information System (INIS)

    Eaton, W.C.

    1995-01-01

    A multiphase program was initiated in 1994 to test commercially available melter technologies for the vitrification of the low-level waste (LLW) stream from defense waste stored in underground tanks at the Hanford Site in southeastern Washington State. Phase 1 of the melter demonstration tests using simulated LLW was completed during fiscal year 1995. This document is the final report on testing performed by GTS Duratek Inc. in Columbia, Maryland. GTS Duratek (one of the seven vendors selected) was chosen to demonstrate Joule heated melter technology under WHC subcontract number MMI-SVV-384215. The report contains description of the tests, observations, test data and some analysis of the data as it pertains to application of this technology for LLW vitrification. The document also contains summaries of the melter offgas reports issued as separate documents for the 100 kg melter (WHC-SD-WM-VI-028) and for the 1000 kg melter (WHC-SD-WM-VI-029)

  20. Paternity tests in Mexico: Results obtained in 3005 cases.

    Science.gov (United States)

    García-Aceves, M E; Romero Rentería, O; Díaz-Navarro, X X; Rangel-Villalobos, H

    2018-04-01

    National and international reports regarding the paternity testing activity scarcely include information from Mexico and other Latin American countries. Therefore, we report different results from the analysis of 3005 paternity cases analyzed during a period of five years in a Mexican paternity testing laboratory. Motherless tests were the most frequent (77.27%), followed by trio cases (20.70%); the remaining 2.04% included different cases of kinship reconstruction. The paternity exclusion rate was 29.58%, higher but into the range reported by the American Association of Blood Banks (average 24.12%). We detected 65 mutations, most of them involving one-step (93.8% and the remaining were two-step mutations (6.2%) thus, we were able to estimate the paternal mutation rate for 17 different STR loci: 0.0018 (95% CI 0.0005-0.0047). Five triallelic patterns and 12 suspected null alleles were detected during this period; however, re-amplification of these samples with a different Human Identification (HID) kit confirmed the homozygous genotypes, which suggests that most of these exclusions actually are one-step mutations. HID kits with ≥20 STRs detected more exclusions, diminishing the rate of inconclusive results with isolated exclusions (Powerplex 21 kit (20 STRs) and Powerplex Fusion kit (22 STRs) offered similar PI (p = 0.379) and average number of exclusions (PE) (p = 0.339) when a daughter was involved in motherless tests. In brief, besides to report forensic parameters from paternity tests in Mexico, results describe improvements to solve motherless paternity tests using HID kits with ≥20 STRs instead of one including 15 STRs. Copyright © 2018 Elsevier Ltd and Faculty of Forensic and Legal Medicine. All rights reserved.

  1. Potential for false positive HIV test results with the serial rapid HIV testing algorithm.

    Science.gov (United States)

    Baveewo, Steven; Kamya, Moses R; Mayanja-Kizza, Harriet; Fatch, Robin; Bangsberg, David R; Coates, Thomas; Hahn, Judith A; Wanyenze, Rhoda K

    2012-03-19

    Rapid HIV tests provide same-day results and are widely used in HIV testing programs in areas with limited personnel and laboratory infrastructure. The Uganda Ministry of Health currently recommends the serial rapid testing algorithm with Determine, STAT-PAK, and Uni-Gold for diagnosis of HIV infection. Using this algorithm, individuals who test positive on Determine, negative to STAT-PAK and positive to Uni-Gold are reported as HIV positive. We conducted further testing on this subgroup of samples using qualitative DNA PCR to assess the potential for false positive tests in this situation. Of the 3388 individuals who were tested, 984 were HIV positive on two consecutive tests, and 29 were considered positive by a tiebreaker (positive on Determine, negative on STAT-PAK, and positive on Uni-Gold). However, when the 29 samples were further tested using qualitative DNA PCR, 14 (48.2%) were HIV negative. Although this study was not primarily designed to assess the validity of rapid HIV tests and thus only a subset of the samples were retested, the findings show a potential for false positive HIV results in the subset of individuals who test positive when a tiebreaker test is used in serial testing. These findings highlight a need for confirmatory testing for this category of individuals.

  2. Long Term Corrosion/Degradation Test Six Year Results

    Energy Technology Data Exchange (ETDEWEB)

    M. K. Adler Flitton; C. W. Bishop; M. E. Delwiche; T. S. Yoder

    2004-09-01

    The Subsurface Disposal Area (SDA) of the Radioactive Waste Management Complex (RWMC) located at the Idaho National Engineering and Environmental Laboratory (INEEL) contains neutron-activated metals from non-fuel, nuclear reactor core components. The Long-Term Corrosion/Degradation (LTCD) Test is designed to obtain site-specific corrosion rates to support efforts to more accurately estimate the transfer of activated elements to the environment. The test is using two proven, industry-standard methods—direct corrosion testing using metal coupons, and monitored corrosion testing using electrical/resistance probes—to determine corrosion rates for various metal alloys generally representing the metals of interest buried at the SDA, including Type 304L stainless steel, Type 316L stainless steel, Inconel 718, Beryllium S200F, Aluminum 6061, Zircaloy-4, low-carbon steel, and Ferralium 255. In the direct testing, metal coupons are retrieved for corrosion evaluation after having been buried in SDA backfill soil and exposed to natural SDA environmental conditions for times ranging from one year to as many as 32 years, depending on research needs and funding availability. In the monitored testing, electrical/resistance probes buried in SDA backfill soil will provide corrosion data for the duration of the test or until the probes fail. This report provides an update describing the current status of the test and documents results to date. Data from the one-year and three-year results are also included, for comparison and evaluation of trends. In the six-year results, most metals being tested showed extremely low measurable rates of general corrosion. For Type 304L stainless steel, Type 316L stainless steel, Inconel 718, and Ferralium 255, corrosion rates fell in the range of “no reportable” to 0.0002 mils per year (MPY). Corrosion rates for Zircaloy-4 ranged from no measurable corrosion to 0.0001 MPY. These rates are two orders of magnitude lower than those specified in

  3. The TRANSRAPID propulsion system - development and test results

    Energy Technology Data Exchange (ETDEWEB)

    Henning, U [Siemens AG, Erlangen (Germany); Kamp, P G [Siemens AG, Erlangen (Germany); Hochleitner, J [Siemens AG, Erlangen (Germany)

    1996-12-31

    The structure of the propulsion system for the Transrapid comprises a number of components which are located along the guideway. These drive components are temporarily switched together to form the drive control zones necessary to permit maglev operation over the guideway. The paper describes the development of the stationary propulsion converter with GTO thyristors. The drive components are tested under realistic operating conditions. The test results confirm the performance capability as well as verify the suitability of the concept for use in revenue service. (HW)

  4. Thermosyphon Flooding in Reduced Gravity Environments Test Results

    Science.gov (United States)

    Gibson, Marc A.; Jaworske, Donald A.; Sanzi, Jim; Ljubanovic, Damir

    2013-01-01

    The condenser flooding phenomenon associated with gravity aided two-phase thermosyphons was studied using parabolic flights to obtain the desired reduced gravity environment (RGE). The experiment was designed and built to test a total of twelve titanium water thermosyphons in multiple gravity environments with the goal of developing a model that would accurately explain the correlation between gravitational forces and the maximum axial heat transfer limit associated with condenser flooding. Results from laboratory testing and parabolic flights are included in this report as part I of a two part series. The data analysis and correlations are included in a follow on paper.

  5. PISA TESTS IN LATIN AMERICA: RESULTS IN CONTEXT

    Directory of Open Access Journals (Sweden)

    Guillermina Tiramonti

    2014-05-01

    Full Text Available The educational reforms implemented in Latin America in the ‘90s introduced changes in the modes of regulation of educational systems based on the adoption of mechanisms for assessing student achievement. Since 2000, eight Latin-American countries (Argentina, Chile, Uruguay, Colombia, Brazil, Costa Rica, Mexico and Peru are involved in the PISA tests. The article presents a brief review of the social and educational situation of the Region, relevant for the interpretation and comparative analysis of the results of these tests that is presented below.

  6. Test Results of the ALICE-HMPID Detector Commissioning

    CERN Document Server

    Volpe, G

    2008-01-01

    The ALICE High Momentum Particle Identification Detector (HMPID) consists of seven identical proximity focusing RICH counters. It covers in total 11 m2, exploiting large area CsI photocathodes for Cherenkov light imaging. The detector is installed in the ALICE solenoid, ready for the data acquisition. By means of the Detector Control System, the Front-end (FEE) and the Readout (R/O) electronics, the MWPC high voltages, the cooling and the gas system have been tested. The HMPID module gas pressure, temperature, current and voltage trends have been monitored and archived in the ORACLE database. In this paper a comprehensive review on the test results is presented.

  7. Patch Test Results of 775 Patients with Allergic Contact Dermatitis

    Directory of Open Access Journals (Sweden)

    Simin Ada

    2010-12-01

    Full Text Available Background and Design: The allergens responsible for allergic contact dermatitis vary among countries and even between different geographical regions within the same country over time. It is of great importance to perform the patch test at certain intervals, to evaluate the results in different centers and to compare them afterwards. Our aim was to evaluate the patch test results in our patients with allergic contact dermatitis.Material and Method: The records of the patients with allergic contact dermatitis, who had been patch tested between May 1997 and March 2009, were analyzed retrospectively. The demographic features such as age and sex, localization of the contact dermatitis, and the patch test results were recorded. Results: Of the 775 patients, 581 (75.2% were females and 194 (25% males. Of all patients, 735 were patch tested with the European Standard Series, 318 - with both the European Standard Series and cosmetic series, and 40-with cosmetic series alone. Of the patients tested with the European Standard Series, 255 (34.7% had at least one positive reaction. The most frequent allergen in the European Standard Series was nickel sulfate (17.3%, followed by cobalt chloride (7.2%, potassium dichromate (3%, fragrance mix (2.9%, and p-phenylenediamine base (2.6%. Of the 358 patients tested with cosmetic series, 82 (22.9% had at least one positive reaction. The 5 most frequently observed cosmetic series allergens were octyl gallate (3.9%, thimerosal (2.2%, sorbitan sesquioleate (2%, Euxyl K 400 (2% and methyldibromo glutaronitrile (1.4%. Conclusion: Our study shows the contact allergen profile of our center over 12 years. The most common allergens and their frequency differ between centers in various cities in Turkey. Those geographical differences should be re-evaluated by further studies performed in the certain time period. The high frequency of reactions to octyl gallate is an important finding in patients suspected of cosmetic allergy

  8. Frequency of chest pain in primary care, diagnostic tests performed and final diagnoses.

    Science.gov (United States)

    Hoorweg, Beatrijs Bn; Willemsen, Robert Ta; Cleef, Lotte E; Boogaerts, Tom; Buntinx, Frank; Glatz, Jan Fc; Dinant, Geert Jan

    2017-11-01

    Observational study of patients with chest pain in primary care: determination of incidence, referral rate, diagnostic tests and (agreement between) working and final diagnoses. 118 general practitioners (GPs) in the Netherlands and Belgium recorded all patient contacts during  2weeks. Furthermore, patients presenting with chest pain were registered extensively. A follow-up form was filled in after 30 days. 22 294 patient contacts were registered. In 281 (1.26%), chest pain was a reason for consulting the GP (mean age for men 54.4/women 53 years). In this cohort of 281 patients, in 38.1% of patients, acute coronary syndrome (ACS) was suspected at least temporarily during consultation, 40.2% of patients were referred to secondary care and 512 diagnostic tests were performed by GPs and consulted specialists. Musculoskeletal pain was the most frequent working (26.1%) and final diagnoses (33.1%). Potentially life-threatening diseases as final diagnosis (such as myocardial infarction) accounted for 8.4% of all chest pain cases. In 23.1% of cases, a major difference between working and final diagnoses was found, in 0.7% a severe disease was initially missed by the GP. Chest pain was present in 281 patients (1.26% of all consultations). Final diagnoses were mostly non-life-threatening. Nevertheless, in 8.4% of patients with chest pain, life-threatening underlying causes were identified. This seems reflected in the magnitude and wide variety of diagnostic tests performed in these patients by GPs and specialists, in the (safe) overestimation of life-threatening diseases by GPs at initial assessment and in the high referral rate we found. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2017. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

  9. Tank 241-S-106, cores 183, 184 and 187 analytical results for the final report

    International Nuclear Information System (INIS)

    Esch, R.A.

    1997-01-01

    This document is the final laboratory report for tank 241-S-106 push mode core segments collected between February 12, 1997 and March 21, 1997. The segments were subsampled and analyzed in accordance with the Tank Push Mode Core Sampling and Analysis Plan (TSAP), the Tank Safety Screening Data Quality Objective (Safety DQO), the Historical Model Evaluation Data Requirements (Historical DQO) and the Data Quality Objective to Support Resolution of the Organic Complexant Safety Issue (Organic DQO). The analytical results are included in Table 1. Six of the twenty-four subsamples submitted for the differential scanning calorimetry (DSC) analysis exceeded the notification limit of 480 Joules/g stated in the DQO. Appropriate notifications were made. Total Organic Carbon (TOC) analyses were performed on all samples that produced exotherms during the DSC analysis. All results were less than the notification limit of three weight percent TOC. No cyanide analysis was performed, per agreement with the Tank Safety Program. None of the samples submitted for Total Alpha Activity exceeded notification limits as stated in the TSAP. Statistical evaluation of results by calculating the 95% upper confidence limit is not performed by the 222-S Laboratory and is not considered in this report. No core composites were created because there was insufficient solid material from any of the three core sampling events to generate a composite that would be representative of the tank contents

  10. LAST MINUTE SOLUTIONS FOR IMPROVING ROMANIA’S FINAL RESULTS IN RELATION TO EUROPE 2020 STRATEGY

    Directory of Open Access Journals (Sweden)

    ANA MARIA TALMACIU (BANU

    2016-10-01

    Full Text Available The aim of this study is to upgrade the competitive position of Romania in relation to the Europe 2020 Strategy, and to offer some last-minute solutions to improve the final results. Romania's interim results revealed a very slow pace for meeting the national proposed targets. The context in which Romania joined this competitive program was not a favorable one, if we consider her state of new state in the EU and the economic crisis. In the first part of the study we analyze the main macroeconomic indicators for the period before adopting the Europe 2020 Strategy. We believe that this initial analysis is relevant to a better understanding of the initially context of the country, and for a better assessment of actual outcomes. The second part of the study updates interim results of proposed national targets in the Europe 2020 strategy. The personal contribution in this study consists in the comments on the analyzed indicators and in the proposed solutions for the next 3 years of implementation of the strategic program.

  11. Biological test methods for the ecotoxicological characterization of wastes. Final report; Biologische Testerverfahren zur oekotoxikologischen Charakterisierung von Abfaellen. Abschlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Becker, Roland [Bundesanstalt fuer Materialforschung, Berlin (Germany); Donnevert, Gerhild [Fachhochschule Giessen-Friedberg (Germany). FB MNI; Roembke, Joerg [ECT Oekotoxikologie GmbH, Floersheim am Main (Germany)

    2007-11-15

    battery the acceptance rate varied between 74.1% (Algae test) and 92.6% (Daphnia test). Methodologically, no problems occurred but further guidance on moisture determination in the terrestrial tests as well as details concerning reference testing and data evaluation for several tests are needed. Independently which test system is considered, SOI always caused the lowest effects and WOO was most toxic, while the EC50 values of INC show an intermediate toxicity. Among the aquatic tests, daphnids and one algal species were the most sensitive ones, while plants were always more sensitive than earthworms in the solid waste samples. Based on the test results from additional tests proposals for the modification of the existing basic test battery could be made. For example, the earthworm acute test could be replaced by another soil invertebrate test with higher sensitivity. Further work performed in parallel to the ring test improves waste testing considerably (e.g. the use of artificial soil as control substrate). A comparison of the ring test results with literature data published so far revealed a good agreement. The results of this ring test support confirm that a combination of a battery of biological tests and chemical residue analysis is needed for an ecotoxicological characterization of wastes. With small modifications proposed in this report the basic test battery is considered to be well suitable for the hazard and risk assessment of wastes. Further, probably multi-variate evaluation of the ring test results will improve the identification of those tests most qualified for the ecotoxicological characterization of wastes. Finally, the experiences made in the ring test support also the proposals made in CEN guideline 14735 (2005) concerning the performance of such tests. (orig.)

  12. 688,112 statistical results : Content mining psychology articles for statistical test results

    NARCIS (Netherlands)

    Hartgerink, C.H.J.

    2016-01-01

    In this data deposit, I describe a dataset that is the result of content mining 167,318 published articles for statistical test results reported according to the standards prescribed by the American Psychological Association (APA). Articles published by the APA, Springer, Sage, and Taylor & Francis

  13. Phase III Simplified Integrated Test (SIT) results - Space Station ECLSS testing

    Science.gov (United States)

    Roberts, Barry C.; Carrasquillo, Robyn L.; Dubiel, Melissa Y.; Ogle, Kathryn Y.; Perry, Jay L.; Whitley, Ken M.

    1990-01-01

    During 1989, phase III testing of Space Station Freedom Environmental Control and Life Support Systems (ECLSS) began at Marshall Space Flight Center (MSFC) with the Simplified Integrated Test. This test, conducted at the MSFC Core Module Integration Facility (CMIF), was the first time the four baseline air revitalization subsystems were integrated together. This paper details the results and lessons learned from the phase III SIT. Future plans for testing at the MSFC CMIF are also discussed.

  14. Demonstration, testing, & evaluation of in situ heating of soil. Draft final report, Volume I

    Energy Technology Data Exchange (ETDEWEB)

    Dev, H.; Enk, J.; Jones, D.; Saboto, W.

    1996-02-12

    This document is a draft final report (Volume 1) for US DOE contract entitled, {open_quotes}Demonstration Testing and Evaluation of In Situ Soil Heating,{close_quotes} Contract No. DE-AC05-93OR22160, IITRI Project No. C06787. This report is presented in two volumes. Volume I contains the technical report and Volume II contains appendices with background information and data. In this project approximately 300 cu. yd. of clayey soil containing a low concentration plume of volatile organic chemicals was heated in situ by the application of electrical energy. It was shown that as a result of heating the effective permeability of soil to air flow was increased such that in situ soil vapor extraction could be performed. The initial permeability of soil was so low that the soil gas flow rate was immeasurably small even at high vacuum levels. When scaled up, this process can be used for the environmental clean up and restoration of DOE sites contaminated with VOCs and other organic chemicals boiling up to 120{degrees} to 130{degrees}C in the vadose zone. Although it may applied to many types of soil formations, it is particularly attractive for low permeability clayey soil where conventional in situ venting techniques are limited by low air flow.

  15. Demonstration, testing, ampersand evaluation of in situ heating of soil. Draft final report, Volume I

    International Nuclear Information System (INIS)

    Dev, H.; Enk, J.; Jones, D.; Saboto, W.

    1996-01-01

    This document is a draft final report (Volume 1) for US DOE contract entitled, open-quotes Demonstration Testing and Evaluation of In Situ Soil Heating,close quotes Contract No. DE-AC05-93OR22160, IITRI Project No. C06787. This report is presented in two volumes. Volume I contains the technical report and Volume II contains appendices with background information and data. In this project approximately 300 cu. yd. of clayey soil containing a low concentration plume of volatile organic chemicals was heated in situ by the application of electrical energy. It was shown that as a result of heating the effective permeability of soil to air flow was increased such that in situ soil vapor extraction could be performed. The initial permeability of soil was so low that the soil gas flow rate was immeasurably small even at high vacuum levels. When scaled up, this process can be used for the environmental clean up and restoration of DOE sites contaminated with VOCs and other organic chemicals boiling up to 120 degrees to 130 degrees C in the vadose zone. Although it may applied to many types of soil formations, it is particularly attractive for low permeability clayey soil where conventional in situ venting techniques are limited by low air flow

  16. Results of the quality assurance testing program for radiopharmaceuticals 1995

    International Nuclear Information System (INIS)

    Baldas, J.; Binnyman, J.; Ivanov, Z.; Lauder, R.

    1996-07-01

    The results of the quality assurance testing conducted by the Australian Radiation Laboratory is summarised. Overall 111 batches of 27 different types of radiopharmaceuticals were tested on samples obtained through normal commercial channels. Failure to meet full specifications was observed in 10 of the 111 batches. All technetium-99m cold kits were reconstituted according to the directions in the package insert using sodium pertechnetate ( 99m Tc) injection. Radionuclidic purity has been determined at the calibration time, except for Thallous [ 201 Tl] Chloride injection where the highest impurity level up to product expiry is quoted. Non-compliance of the vial label was observed in one of the ten batches failing specification and was the sole cause of product failure for this batch. Vial label non-compliance consisted of, absence of volume in the vial. Six batches failed the biodistribution test but in no case did this involve failure of the distribution for the target organs. tabs

  17. Initial CGE Model Results Summary Exogenous and Endogenous Variables Tests

    Energy Technology Data Exchange (ETDEWEB)

    Edwards, Brian Keith [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Boero, Riccardo [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Rivera, Michael Kelly [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-08-07

    The following discussion presents initial results of tests of the most recent version of the National Infrastructure Simulation and Analysis Center Dynamic Computable General Equilibrium (CGE) model developed by Los Alamos National Laboratory (LANL). The intent of this is to test and assess the model’s behavioral properties. The test evaluated whether the predicted impacts are reasonable from a qualitative perspective. This issue is whether the predicted change, be it an increase or decrease in other model variables, is consistent with prior economic intuition and expectations about the predicted change. One of the purposes of this effort is to determine whether model changes are needed in order to improve its behavior qualitatively and quantitatively.

  18. Results of the quality assurance testing program for radiopharmaceuticals 1995

    Energy Technology Data Exchange (ETDEWEB)

    Baldas, J.; Binnyman, J.; Ivanov, Z.; Lauder, R.

    1996-07-01

    The results of the quality assurance testing conducted by the Australian Radiation Laboratory is summarised. Overall 111 batches of 27 different types of radiopharmaceuticals were tested on samples obtained through normal commercial channels. Failure to meet full specifications was observed in 10 of the 111 batches. All technetium-99m cold kits were reconstituted according to the directions in the package insert using sodium pertechnetate ( {sup 99m}Tc) injection. Radionuclidic purity has been determined at the calibration time, except for Thallous [{sup 201}Tl] Chloride injection where the highest impurity level up to product expiry is quoted. Non-compliance of the vial label was observed in one of the ten batches failing specification and was the sole cause of product failure for this batch. Vial label non-compliance consisted of, absence of volume in the vial. Six batches failed the biodistribution test but in no case did this involve failure of the distribution for the target organs. tabs.

  19. TEST RESULTS FOR LHC INSERTION REGION DEPOLE MAGNETS

    International Nuclear Information System (INIS)

    MURATORE, J.; JAIN, A.; ANERELLA, M.; COSSOLINO, J.

    2005-01-01

    The Superconducting Magnet Division at Brookhaven National Laboratory (BNL) has made 20 insertion region dipoles for the Large Hadron Collider (LHC) at CERN. These 9.45 m-long, 8 cm aperture magnets have the same coil design as the arc dipoles now operating in the Relativistic Heavy Ion Collider (RHIC) at BNL and are of single aperture, twin aperture, and double cold mass configurations. They are required to produce fields up to 4.14 T for operation at 7.56 TeV. Eighteen of these magnets have been tested at 4.5 K using either forced flow supercritical helium or liquid helium. The testing was especially important for the twin aperture models, whose construction was very different from the RHIC dipoles, except for the coil design. This paper reports on the results of these tests, including spontaneous quench performance, verification of quench protection heater operation, and magnetic field quality

  20. Using Large Scale Test Results for Pedagogical Purposes

    DEFF Research Database (Denmark)

    Dolin, Jens

    2012-01-01

    The use and influence of large scale tests (LST), both national and international, has increased dramatically within the last decade. This process has revealed a tension between the legitimate need for information about the performance of the educational system and teachers to inform policy......, and the teachers’ and students’ use of this information for pedagogical purposes in the classroom. We know well how the policy makers interpret and use the outcomes of such tests, but we know less about how teachers make use of LSTs to inform their pedagogical practice. An important question is whether...... there is a contradiction between the political system’s use of LST and teachers’ (possible) pedagogical use of LST. And if yes: What is a contradiction based on? This presentation will give some results from a systematic review on how tests have influenced the pedagogical practice. The research revealed many of the fatal...

  1. SP-100 Fuel Pin Performance: Results from Irradiation Testing

    Science.gov (United States)

    Makenas, Bruce J.; Paxton, Dean M.; Vaidyanathan, Swaminathan; Marietta, Martin; Hoth, Carl W.

    1994-07-01

    A total of 86 experimental fuel pins with various fuel, liner, and cladding candidate materials have been irradiated in the Experimental Breeder Reactor-II (EBR-II) and the Fast Flux Test Facility (FFTF) reactor as part of the SP-100 fuel pin irradiation testing program. Postirradiation examination results from these fuel pins are key in establishing performance correlations and demonstrating the lifetime and safety of the reactor fuel system. This paper provides a brief description of the in-reactor fuel pin tests and presents the most recent irradiation data on the performance of wrought rhenium (Re) liner material and high density UN fuel at goal burnup of 6 atom percent (at. %). It also provides an overview of the significant variety of other fuel/liner/cladding combinations which were irradiated as part of this program and which may be of interest to more advanced efforts.

  2. Tank 241-BY-112, cores 174 and 177 analytical results for the final report

    International Nuclear Information System (INIS)

    Nuzum, J.L.

    1997-01-01

    Results from bulk density tests ranged from 1.03 g/mL to 1.86 g/mL. The highest bulk density result of 1.86 g/mL was used to calculate the solid total alpha activity notification limit for this tank (33.1 uCi/g), Total Alpha (AT) Analysis. Attachment 2 contains the Data Verification and Deliverable (DVD) Summary Report for AT analyses. This report summarizes results from AT analyses and provides data qualifiers and total propagated uncertainty (TPU) values for results. The TPU values are based on the uncertainties inherent in each step of the analysis process. They may be used as an additional reference to determine reasonable RPD values which may be used to accept valid data that do not meet the TSAP acceptance criteria. A report guide is provided with the report to assist in understanding this summary report

  3. Final Technical Resource Confirmation Testing at the Raft River Geothermal Project, Cassia County, Idaho

    Energy Technology Data Exchange (ETDEWEB)

    Glaspey, Douglas J.

    2008-01-30

    Incorporates the results of flow tests for geothermal production and injection wells in the Raft River geothermal field in southern Idaho. Interference testing was also accomplished across the wellfield.

  4. Containment liner plate anchors and steel embedments test results

    International Nuclear Information System (INIS)

    Chang-Lo, P.L.; Johnson, T.E.; Pfeifer, B.W.

    1977-01-01

    This paper summarizes test data on shear load and deformation capabilities for liner plate line anchors and structural steel embedments in reinforced and prestressed concrete nuclear containments. Reinforced and prestressed nuclear containments designed and constructed in the United States are lined with a minimum of 0.64 cm steel plate. The liner plates are anchored by the use of either studs or structural members (line anchors) which usually run in the vertical direction. This paper will only address line anchors. Static load versus displacement test data is necessary to assure that the design is adequate for the maximum loads. The test program for the liner anchors had the following major objectives: determine load versus displacement data for a variety of anchors considering structural tees and small beams with different weld configurations, from the preceding tests, determine which anchors would lead to an economical and extremely safe design and test these anchors for cyclic loads resulting from thermal fluctuations. Various concrete embeds in the containment and other structures are subjected to loads such as pipe rupture which results in shear. Since many of the loads are transient by nature, it is necessary to know the load-displacement relationship so that the energy absorption can be determined. The test program for the embeds had the following objectives: determine load-displacement relationship for various size anchors from 6.5 cm 2 to 26 cm 2 with maximum capacities of approximately 650 kN; determine the effect of various anchor width-to-thickness ratios for the same shear area

  5. 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

  6. Ocean Thermal Energy Converstion (OTEC) test facilities study program. Final report. Volume II. Part B

    Energy Technology Data Exchange (ETDEWEB)

    None

    1977-01-17

    Results are presented of an 8-month study to develop alternative non-site-specific OTEC facilities/platform requirements for an integrated OTEC test program which may include land and floating test facilities. Volume II--Appendixes is bound in three parts (A, B, and C) which together comprise a compendium of the most significant detailed data developed during the study. Part B provides an annotated test list and describes component tests and system tests.

  7. AGR-2 Irradiation Test Final As-Run Report, Rev 2

    Energy Technology Data Exchange (ETDEWEB)

    Collin, Blaise P. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-08-01

    This document presents the as-run analysis of the AGR-2 irradiation experiment. AGR-2 is the second of the planned irradiations for the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. Funding for this program is provided by the U.S. Department of Energy as part of the Very High Temperature Reactor (VHTR) Technical Development Office (TDO) program. The objectives of the AGR-2 experiment are to: (a) Irradiate UCO (uranium oxycarbide) and UO2 (uranium dioxide) fuel produced in a large coater. Fuel attributes are based on results obtained from the AGR-1 test and other project activities. (b) Provide irradiated fuel samples for post-irradiation experiment (PIE) and safety testing. (c) Support the development of an understanding of the relationship between fuel fabrication processes, fuel product properties, and irradiation performance. The primary objective of the test was to irradiate both UCO and UO2 TRISO (tri-structural isotropic) fuel produced from prototypic scale equipment to obtain normal operation and accident condition fuel performance data. The UCO compacts were subjected to a range of burnups and temperatures typical of anticipated prismatic reactor service conditions in three capsules. The test train also includes compacts containing UO2 particles produced independently by the United States, South Africa, and France in three separate capsules. The range of burnups and temperatures in these capsules were typical of anticipated pebble bed reactor service conditions. The results discussed in this report pertain only to U.S. produced fuel. In order to achieve the test objectives, the AGR-2 experiment was irradiated in the B-12 position of the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) for a total irradiation duration of 559.2 effective full power days (EFPD). Irradiation began on June 22, 2010, and ended on October 16, 2013, spanning 12 ATR power cycles and approximately three and a

  8. AGR-2 irradiation test final as-run report, Rev. 1

    International Nuclear Information System (INIS)

    2014-01-01

    This document presents the as-run analysis of the AGR-2 irradiation experiment. AGR-2 is the second of the planned irradiations for the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. Funding for this program is provided by the U.S. Department of Energy as part of the Very High Temperature Reactor (VHTR) Technical Development Office (TDO) program. The objectives of the AGR-2 experiment are to: (a) Irradiate UCO (uranium oxycarbide) and UO 2 (uranium dioxide) fuel produced in a large coater. Fuel attributes are based on results obtained from the AGR-1 test and other project activities; (b) Provide irradiated fuel samples for post-irradiation experiment (PIE) and safety testing; and, (c) Support the development of an understanding of the relationship between fuel fabrication processes, fuel product properties, and irradiation performance. The primary objective of the test was to irradiate both UCO and UO 2 TRISO (tri-structural isotropic) fuel produced from prototypic scale equipment to obtain normal operation and accident condition fuel performance data. The UCO compacts were subjected to a range of burnups and temperatures typical of anticipated prismatic reactor service conditions in three capsules. The test train also includes compacts containing UO 2 particles produced independently by the United States, South Africa, and France in three separate capsules. The range of burnups and temperatures in these capsules were typical of anticipated pebble bed reactor service conditions. The results discussed in this report pertain only to U.S. produced fuel. In order to achieve the test objectives, the AGR-2 experiment was irradiated in the B-12 position of the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) for a total irradiation duration of 559.2 effective full power days (EFPD). Irradiation began on June 22, 2010, and ended on October 16, 2013, spanning 12 ATR power cycles and approximately three and a half calendar years. The

  9. Large-Scale Spray Releases: Additional Aerosol Test Results

    Energy Technology Data Exchange (ETDEWEB)

    Daniel, Richard C.; Gauglitz, Phillip A.; Burns, Carolyn A.; Fountain, Matthew S.; Shimskey, Rick W.; Billing, Justin M.; Bontha, Jagannadha R.; Kurath, Dean E.; Jenks, Jeromy WJ; MacFarlan, Paul J.; Mahoney, Lenna A.

    2013-08-01

    One of the events postulated in the hazard analysis for the Waste Treatment and Immobilization Plant (WTP) and other U.S. Department of Energy (DOE) nuclear facilities is a breach in process piping that produces aerosols with droplet sizes in the respirable range. The current approach for predicting the size and concentration of aerosols produced in a spray leak event involves extrapolating from correlations reported in the literature. These correlations are based on results obtained from small engineered spray nozzles using pure liquids that behave as a Newtonian fluid. The narrow ranges of physical properties on which the correlations are based do not cover the wide range of slurries and viscous materials that will be processed in the WTP and in processing facilities across the DOE complex. To expand the data set upon which the WTP accident and safety analyses were based, an aerosol spray leak testing program was conducted by Pacific Northwest National Laboratory (PNNL). PNNL’s test program addressed two key technical areas to improve the WTP methodology (Larson and Allen 2010). The first technical area was to quantify the role of slurry particles in small breaches where slurry particles may plug the hole and prevent high-pressure sprays. The results from an effort to address this first technical area can be found in Mahoney et al. (2012a). The second technical area was to determine aerosol droplet size distribution and total droplet volume from prototypic breaches and fluids, including sprays from larger breaches and sprays of slurries for which literature data are mostly absent. To address the second technical area, the testing program collected aerosol generation data at two scales, commonly referred to as small-scale and large-scale testing. The small-scale testing and resultant data are described in Mahoney et al. (2012b), and the large-scale testing and resultant data are presented in Schonewill et al. (2012). In tests at both scales, simulants were used

  10. Spent fuel drying system test results (second dry-run)

    International Nuclear Information System (INIS)

    Klinger, G.S.; Oliver, B.M.; Abrefah, J.; Marschman, S.C.; MacFarlan, P.J.; Ritter, G.A.

    1998-07-01

    The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks have been detected in the basins and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuel elements in an interim storage facility on the Hanford Site (WHC 1995). Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 7.0) have been conducted by Pacific Northwest National Laboratory (PNNL) on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of the second dry-run test, which was conducted without a fuel element. With the concurrence of project management, the test protocol for this run, and subsequent drying test runs, was modified. These modifications were made to allow for improved data correlation with drying procedures proposed under the IPS. Details of these modifications are discussed in Section 3.0

  11. Experimental Results of Integrated Refrigeration and Storage System Testing

    Science.gov (United States)

    Notardonato, W. U.; Johnson, W. L.; Jumper, K.

    2009-01-01

    Launch operations engineers at the Kennedy Space Center have identified an Integrated Refrigeration and Storage system as a promising technology to reduce launch costs and enable advanced cryogenic operations. This system uses a close cycle Brayton refrigerator to remove energy from the stored cryogenic propellant. This allows for the potential of a zero loss storage and transfer system, as well and control of the state of the propellant through densification or re-liquefaction. However, the behavior of the fluid in this type of system is different than typical cryogenic behavior, and there will be a learning curve associated with its use. A 400 liter research cryostat has been designed, fabricated and delivered to KSC to test the thermo fluid behavior of liquid oxygen as energy is removed from the cryogen by a simulated DC cycle cryocooler. Results of the initial testing phase focusing on heat exchanger characterization and zero loss storage operations using liquid oxygen are presented in this paper. Future plans for testing of oxygen densification tests and oxygen liquefaction tests will also be discussed. KEYWORDS: Liquid Oxygen, Refrigeration, Storage

  12. Results of patch testing with lavender oil in Japan.

    Science.gov (United States)

    Sugiura, M; Hayakawa, R; Kato, Y; Sugiura, K; Hashimoto, R

    2000-09-01

    We report the annual results of patch testing with lavender oil for a 9-year period from 1990 to 1998 in Japan. Using Finn Chambers and Scanpor tape, we performed 2-day closed patch testing with lavender oil 20% pet. on the upper back of each patient suspected of having cosmetic contact dermatitis. We compared the frequency of positive patch tests to lavender oil each year with those to other fragrances. We diagnosed contact allergy when patch test reactions were + or Japan, there has been a trend for aromatherapy using lavender oil. With this trend, placing dried lavender flowers in pillows, drawers, cabinets, or rooms has become a new fashion. We asked patients who showed a positive reaction to lavender oil about their use of dried lavender flowers. We confirmed the use of dried lavender flowers in 5 cases out of 11 positive cases in 1997 and 8 out of 15 positive cases in 1998. We concluded that the increase in patch test positivity rates to lavender oil in 1997 and 1998 was due to the above fashion, rather than due to fragrances in cosmetic products.

  13. Overview of results from 2D airfoil testing at Risoe

    Energy Technology Data Exchange (ETDEWEB)

    Fuglsang, P. [Risoe National Lab., Wind Energy and Atmospheric Physics Dept., Roskilde (Denmark)

    1997-12-31

    This paper gives an overview of the results from two dimensional airfoil testing at Risoe. A two dimensional testing method was recently developed where a test rig is inserted into an open jet flow in a wind tunnel of the close return loop type with an open test section. Pressure measurements provide the lift and drag forces. Both stationary flow and dynamic inflow from pitch motion are possible. The wind tunnel static pressure and total dynamic pressures were calibrated and wind tunnel boundary corrections were found. So far, the testing method was verified by comparison of NACA 63-215 airfoil measurements to numerical predictions and to measurements. Furthermore, the Risoe-1, FFA-W3-241, FFA-W3-301 and NACA 63-430 airfoils were measured. Different types of leading edge roughness and vortex generators were investigated. For all airfoils, good agreements with predictions were obtained on both pressure distribution and on lift coefficient. The drag coefficients were slightly higher than predicted. (eg) 10 refs.

  14. VLT deformable secondary mirror: integration and electromechanical tests results

    Science.gov (United States)

    Biasi, R.; Andrighettoni, M.; Angerer, G.; Mair, C.; Pescoller, D.; Lazzarini, P.; Anaclerio, E.; Mantegazza, M.; Gallieni, D.; Vernet, E.; Arsenault, R.; Madec, P.-Y.; Duhoux, P.; Riccardi, A.; Xompero, M.; Briguglio, R.; Manetti, M.; Morandini, M.

    2012-07-01

    The VLT Deformable secondary is planned to be installed on the VLT UT#4 as part of the telescope conversion into the Adaptive Optics test Facility (AOF). The adaptive unit is based on the well proven contactless, voice coil motor technology that has been already successfully implemented in the MMT, LBT and Magellan adaptive secondaries, and is considered a promising technical choice for the forthcoming ELT-generation adaptive correctors, like the E-ELT M4 and the GMT ASM. The VLT adaptive unit has been recently assembled after the completion of the manufacturing and modular test phases. In this paper, we present the most relevant aspects of the system integration and report the preliminary results of the electromechanical tests performed on the unit. This test campaign is a typical major step foreseen in all similar systems built so far: thanks to the metrology embedded in the system, that allows generating time-dependent stimuli and recording in real time the position of the controlled mirror on all actuators, typical dynamic response quality parameters like modal settling time, overshoot and following error can be acquired without employing optical measurements. In this way the system dynamic and some aspect of its thermal and long term stability can be fully characterized before starting the optical tests and calibrations.

  15. Results of the First Performance Tests of the CMS Electromagnetic Calorimeter

    CERN Document Server

    Adzic, Petar; Almeida, Carlos; Almeida, Nuno; Anagnostou, Georgios; Anfreville, Marc; Anicin, Ivan; Antunovic, Zeljko; Asimidis, Asimakis; Auffray, Etiennette; Baccaro, Stefania; Barney, David; Barone, Luciano; Barrillon, Pierre; Bartoloni, Alessandro; Beauceron, Stephanie; Beaudette, Florian; Bell, Ken W; Benetta, Robert; Bercher, Michel; Beteva, B; Beuselinck, Raymond; Bhardwa, A; Biino, Cristina; Bimbot, Stephane; Bloch, Philippe; Blyth, Simon; Bonesini, Maurizio; Bordalo, Paula; Bornheim, Adolf; Bourotte, Jean; Britton, David; Brown, Robert M; Brunelière, Renaud; Busson, Philippe; Camporesi, Tiziano; Cartiglia, Nicolo; Cavallari, Francesca; Chamont, David; Chang, Paoti; Chang, You-Hao; Charlot, Claude; Chen, E Augustine; Chipaux, Rémi; Cockerill, David J A; Collard, Caroline; Combaret, Christophe; Costantini, Silvia; Da Silva, J C; Dafinei, Ioan; Daskalakis, Georgios; Davatz, Giovanna; De Min, Alberto; Deiters, Konrad; Dejardin, Marc; Della Negra, Rodolphe; Depasse, Pierre; Descamp, J; Dewhirst, Guy; Dhawan, Satish; Diemoz, Marcella; Dissertori, Günther; Dittmar, Michael; Djambazov, Lubomir; Dobrzynski, Ludwik; Drndarevic, Snezana; Dupanloup, Michel; Dzelalija, Mile; Ehlers, Jan; El-Mamouni, H; Peisert, Anna; Evangelou, Ioannis; Fabbro, Bernard; Faure, Jean-Louis; Fay, Jean; Ferri, Federico; Flower, Paul S; Franzoni, Giovanni; Funk, Wolfgang; Gaillac, Anne-Marie; Gargiulo, Corrado; Gascon-Shotkin, S; Geerebaert, Yannick; Gentit, François-Xavier; Ghezzi, Alessio; Gilly, Jean; Giolo-Nicollerat, Anne-Sylvie; Givernaud, Alain; Gninenko, Sergei; Go, Apollo; Godinovic, Nikola; Golubev, Nikolai; Gómez-Reino, Robert; Govoni, Pietro; Grahl, James; Gras, Philippe; Greenhalgh, Justin; Guillaud, Jean-Paul; Haguenauer, Maurice; Hamel De Montechenault, G; Hansen, Magnus; Heath, Helen F; Hill, Jack; Hobson, Peter R; Holmes, Daniel; Holzner, André; Hou, George Wei-Shu; Ille, Bernard; Ingram, Quentin; Jain, Adarsh; Janot, Patrick; Jarry, Patrick; Karar, M A; Kataria, Sushil Kumar; Katchanov, V A; Kennedy, Bruce W; Kloukinas, Kostas; Koblitz, Birger; Kokkas, Panagiotis; Korjik, M; Krasnikov, Nikolai; Krpic, Dragomir; Kyriakis, Aristotelis; Lebeau, Michel; Lecomte, Pierre; Lecoq, Paul; Lemaire, Marie-Claude; Lethuillier, Morgan; Lin, Willis; Lintern, A L; Lister, Alison; Locci, Elizabeth; Lodge, Anthony B; Longo, Egidio; Loukas, Demetrios; Lustermann, Werner; Lynch, Clare; MacKay, Catherine Kirsty; Maletic, Dimitrije; Mandjavidze, Irakli; Manthos, Nikolaos; Markou, Athanasios; Mathez, Hervé; Matveev, Viktor; Maurelli, Georges; Menichetti, Ezio; Meridiani, Paolo; Milenovic, Predrag; Milleret, Gérard; Miné, Philippe; Montecchi, Marco; Mur, Michel; Musienko, Yuri; Nardulli, Alessandro; Nash, Jordan; Neal, Homer; Nédélec, Patrick; Negri, Pietro; Nessi-Tedaldi, Francesca; Newman, Harvey B; Nikitenko, Alexander; Obertino, Maria Margherita; Ofierzynski, Radoslaw Adrian; Organtini, Giovanni; Paganini, Pascal; Paganoni, Marco; Papadopoulos, Ioannis; Paramatti, Riccardo; Pastrone, Nadia; Pauss, Felicitas; Poilleux, Patrick; Puljak, Ivica; Pullia, Antonino; Puzovic, Jovan; Ragazzi, Stefano; Ramos, Sergio; Rander, John; Ravat, Olivier; Raymond, M; Razis, Panos A; Redaelli, Nicola; Regnault, Nicolas; Renker, Dieter; Reucroft, Steve; Reymond, Jean-Marc; Reynaud, Michel; Reynaud, Serge; Romanteau, Thierry; Rondeaux, Françoise; Rosowsky, André; Rovelli, Chiara; Rusack, Roger; Rusakov, Sergey V; Ryan, Matthew John; Rykaczewski, Hans; Sakhelashvili, Tariel; Salerno, Roberto; Santos, Marcelino; Schinzel, Dietrich; Seez, Christopher; Semeniouk, Igor; Sempere-Roldan, P; Sharif, Omar; Sharp, Peter; Shepherd-Themistocleous, Claire; Shevchenko, Sergey; Shivpuri, Ram Krishen; Sidiropoulos, Georgios; Sillou, Daniel; Singovsky, Alexander; Sirois, Yves; Sirunyan, Albert M; Smith, Brian; Smith, Vincent J; Sproston, Martin; Suter, Henry; Swain, John; Tabarelli de Fatis, Tommaso; Takahashi, Maiko; Tapper, Robert J; Tcheremoukhine, Alexandre; Teixeira, Isabel; Teixeira, Joao Paulo; Teller, Olivier; Triantis, Frixos A; Troshin, Sergey; Tyurin, Nikolay; Udriot, Stève; Ueno, Koji; Uzunian, Andrey; Van Vulpen, Ivo; Varela, Joao; Vaz-Cardoso, N; Verrecchia, Patrice; Vichoudis, Paschalis; Viertel, Gert; Virdee, Tejinder; Wang, Minzu; Williams, Jennifer C; Yaselli, Ignacio; Zamiatin, Nikolai; Zelepoukine, Serguei; Zeller, Michael E; Zhang, Lin; Zhu, Kejun; Zhu, Ren-Yuan

    2006-01-01

    Performance tests of some aspects of the CMS ECAL were carried out on modules of the "barrel" sub-system in 2002 and 2003. A brief test with high energy electron beams was made in late 2003 to validate prototypes of the new Very Front End electronics. The final versions of the monitoring and cooling systems, and of the high and low voltage regulation were used in these tests. The results are consistent with the performance targets including those for noise and overall energy resolution, required to fulfil the physics programme of CMS at the LHC.

  16. Test Results for the Automated Rendezvous and Capture System

    Science.gov (United States)

    Cruzen, Craig; Dabney, Richard; Lomas, James

    1999-01-01

    The Automated Rendezvous and Capture (AR&C) system was designed and tested at NASA's Marshall Space Flight Center (MSFC) to demonstrate technologies and mission strategies for automated rendezvous and docking of spacecraft in Earth orbit, The system incorporates some of the latest innovations in Global Positioning, System space navigation, laser sensor technologies and automated mission sequencing algorithms. The system's initial design and integration was completed in 1998 and has undergone testing at MSFC. This paper describes the major components of the AR&C system and presents results from the official system tests performed in MSFC's Flight Robotics Laboratory with digital simulations and hardware in the loop tests. The results show that the AR&C system can safely and reliably perform automated rendezvous and docking missions in the absence of system failures with 100 percent success. When system failures are included, the system uses its automated collision avoidance maneuver logic to recover in a safe manner. The primary objective of the AR&C project is to prove that by designing a safe and robust automated system, mission operations cost can be reduced by decreasing the personnel required for mission design, preflight planning and training required for crewed rendezvous and docking missions.

  17. Honeywell Cascade Distiller System Performance Testing Interim Results

    Science.gov (United States)

    Callahan, Michael R.; Sargusingh, Miriam

    2014-01-01

    The ability to recover and purify water through physiochemical processes is crucial for realizing long-term human space missions, including both planetary habitation and space travel. Because of their robust nature, distillation systems have been actively pursued as one of the technologies for water recovery. The Cascade Distillation System (CDS) is a vacuum rotary distillation system with potential for greater reliability and lower energy costs than existing distillation systems. The CDS was previously under development through Honeywell and NASA. In 2009, an assessment was performed to collect data to support down-selection and development of a primary distillation technology for application in a lunar outpost water recovery system. Based on the results of this testing, an expert panel concluded that the CDS showed adequate development maturity, TRL-4, together with the best product water quality and competitive weight and power estimates to warrant further development. The Advanced Exploration Systems (AES) Water Recovery Project (WRP) worked to address weaknesses identified by The Panel; namely bearing design and heat pump power efficiency. Testing at the NASA-JSC Advanced Exploration System Water Laboratory (AES Water Lab) using a prototype Cascade Distillation Subsystem (CDS) wastewater processor (Honeywell International, Torrance, Calif.) with test support equipment and control system developed by Johnson Space Center was performed to evaluate performance of the system with the upgrades. The CDS will also have been challenged with ISS analog waste streams and a subset of those being considered for Exploration architectures. This paper details interim results of the AES WRP CDS performance testing.

  18. Interpolation of final geometry and result fields in process parameter space

    NARCIS (Netherlands)

    Misiun, Grzegorz Stefan; Wang, Chao; Geijselaers, Hubertus J.M.; van den Boogaard, Antonius H.; Saanouni, K.

    2016-01-01

    Different routes to produce a product in a bulk forming process can be described by a limited set of process parameters. The parameters determine the final geometry as well as the distribution of state variables in the final shape. Ring rolling has been simulated using different parameter settings.

  19. Postirradiation examination results for the Irradiation Effects Scoping Test 2

    International Nuclear Information System (INIS)

    Mehner, A.S.

    1977-01-01

    The postirradiation examination results are reported for two rods from the second scoping test (IE-ST-2) of the Nuclear Regulatory Commission Irradiation Effects Program. The rods were irradiated in the in-pile test loop of the Power Burst Facility at the Idaho National Engineering Laboratory. Rod IE-005 was fabricated from fresh fuel and cladding previously irradiated in the Saxton Reactor. Rod IE-006, fabricated from fresh fuel and unirradiated cladding, was equipped with six developmental cladding surface thermocouples. The rods were preconditioned, power ramped, and then subjected to film boiling operation. The performance of the rods and the developmental thermocouples are evaluated from the post irradiation examination results. The effects of prior irradiation damage in cladding are discussed in relation to fuel rod behavior during a power ramp and subsequent film boiling operation

  20. Results of a first beam test of hadron blind trackers

    Energy Technology Data Exchange (ETDEWEB)

    Chen, M. (Laboratory for Nuclear Science, MIT, Cambridge, MA (United States)); Luckey, D. (Laboratory for Nuclear Science, MIT, Cambridge, MA (United States)); Smolin, M. (Laboratory for Nuclear Science, MIT, Cambridge, MA (United States)); Sumorok, K. (Laboratory for Nuclear Science, MIT, Cambridge, MA (United States)); Zhang, X. (Laboratory for Nuclear Science, MIT, Cambridge, MA (United States)); Bolozdynya, A. (ITEP, Moscow (Russian Federation)); Belogurov, S. (ITEP, Moscow (Russian Federation)); Churakov, D. (ITEP, Moscow (Russian Federation)); Koutchenkov, A. (ITEP, Moscow (Russian Federation)); Kovalenko, A. (ITEP, Moscow (Russian Federation)); Kuzichev, V. (ITEP, Moscow (Russian Federation)); Lebedenko, V. (ITEP, Moscow (Russian Federation)); Sheinkman, V. (ITEP, Moscow (Russian Federation)); Smirnov, G. (ITEP, Moscow (Russian Federation)); Safronov, G. (ITEP, Moscow (Russian Federation)); Vinogradov, V. (ITEP, Moscow (Russian Federation)); Giomataris, Y. (IPN,

    1994-07-15

    We describe the experimental results of a new type of electron tracker, called Hadron Blind Detector or HBD. An HBD prototype was tested with gas mixtures of CF[sub 4] with He or Ne and a parallel plate avalanche chamber having a CsI photocathode of eight pads. Beam tests confirm the large Cherenkov light bandwidth in the EUV region that can be obtained with such gas mixtures. It results in a large quality factor of about 500 cm[sup -1] which allows HBD operation with a much shorter radiator thickness than conventional Cherenkov counters. Full electron efficiency was obtained, while pions were rejected up to momenta of 9 GeV/c. HBD is unique in measuring electron trajectories near the vertex, vetoing Dalitz pairs, and providing trigger on electrons among heavy hadron background. We discuss the use of such detectors for lepton identification and detection in high energy physics experiments and especially in heavy ion colliders. ((orig.))

  1. Results of a first beam test of hadron blind trackers

    International Nuclear Information System (INIS)

    Chen, M.; Luckey, D.; Smolin, M.; Sumorok, K.; Zhang, X.; Bolozdynya, A.; Belogurov, S.; Churakov, D.; Koutchenkov, A.; Kovalenko, A.; Kuzichev, V.; Lebedenko, V.; Sheinkman, V.; Smirnov, G.; Safronov, G.; Vinogradov, V.; Giomataris, Y.; Joseph, C.; Werlen, M.; Charpak, G.; Blumenfeld, B.; Gougas, A.K.; Steele, D.; Akopyan, M.

    1994-01-01

    We describe the experimental results of a new type of electron tracker, called Hadron Blind Detector or HBD. An HBD prototype was tested with gas mixtures of CF 4 with He or Ne and a parallel plate avalanche chamber having a CsI photocathode of eight pads. Beam tests confirm the large Cherenkov light bandwidth in the EUV region that can be obtained with such gas mixtures. It results in a large quality factor of about 500 cm -1 which allows HBD operation with a much shorter radiator thickness than conventional Cherenkov counters. Full electron efficiency was obtained, while pions were rejected up to momenta of 9 GeV/c. HBD is unique in measuring electron trajectories near the vertex, vetoing Dalitz pairs, and providing trigger on electrons among heavy hadron background. We discuss the use of such detectors for lepton identification and detection in high energy physics experiments and especially in heavy ion colliders. ((orig.))

  2. Improved Limits On The Existence Of Dark Matter. The Final Results From The PICASSO Experiment

    Science.gov (United States)

    Kamaha, Alvine Christelle

    The final results of the PICASSO experiment, with 409 kg days of exposure collected from November 2012 to January 2014, have yielded new limits for Spin-Dependent and Spin-Independent Dark Matter interactions. The data collected and the various backgrounds were assiduously studied using Monte Carlo simulations and a new set of sophisticated analysis techniques including the wavelet analysis presented in this thesis. In general, a good suppression of most backgrounds was attained. The neutron background event rate was reduced to about a factor of 10 compared to the previous phase of the experiment. Electronic and acoustic noise events were thoroughly suppressed. A new class of "mystery events" were removed as well. All that remained was the irreducible alpha background. No signal consistent with a WIMP Dark Matter hypothesis was observed. Consequently, an exclusion curve was obtained with a minimum limit at 90% C.L. of sigmaSDchip = 0.0228 pb at a WIMP mass of 20 GeV/c2 in the Spin-Dependent sector. By combining results from 2012 and the current results, an improved constraint of sigmaSDchip (90% C.L.) = 0.0188 pb at 20 GeV/c2 was placed on the Dark Matter interaction with protons in the Fluorine nuclei used in the detectors. In addition, the new limits on WIMP-proton interactions in the Spin Independent sector exclude the DAMA/LIBRA results (at 90% C.L.) for low masses below 12 GeV/c2 and further constrain the published CRESST and CDMS Si discovery regions at low WIMP masses.

  3. Summary of Test Results for Daya Bay Rock Samples

    International Nuclear Information System (INIS)

    Onishi, Celia Tiemi; Dobson, Patrick; Nakagawa, Seiji

    2004-01-01

    A series of analytical tests was conducted on a suite of granitic rock samples from the Daya Bay region of southeast China. The objective of these analyses was to determine key rock properties that would affect the suitability of this location for the siting of a neutrino oscillation experiment. This report contains the results of chemical analyses, rock property measurements, and a calculation of the mean atomic weight

  4. Seismic II over I Drop Test Program results and interpretation

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, B.

    1993-03-01

    The consequences of non-seismically qualified (Category 2) objects falling and striking essential seismically qualified (Category 1) objects has always been a significant, yet analytically difficult problem, particularly in evaluating the potential damage to equipment that may result from earthquakes. Analytical solutions for impact problems are conservative and available for mostly simple configurations. In a nuclear facility, the {open_quotes}sources{close_quotes} and {open_quotes}targets{close_quotes} requiring evaluation are frequently irregular in shape and configuration, making calculations and computer modeling difficult. Few industry or regulatory rules are available on this topic even though it is a source of considerable construction upgrade costs. A drop test program was recently conducted to develop a more accurate understanding of the consequences of seismic interactions. The resulting data can be used as a means to improve the judgment of seismic qualification engineers performing interaction evaluations and to develop realistic design criteria for seismic interactions. Impact tests on various combinations of sources and targets commonly found in one Savannah River Site (SRS) nuclear facility were performed by dropping the sources from various heights onto the targets. This report summarizes results of the Drop Test Program. Force and acceleration time history data are presented as well as general observations on the overall ruggedness of various targets when subjected to impacts from different types of sources.

  5. Seismic II over I Drop Test Program results and interpretation

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, B.

    1993-03-01

    The consequences of non-seismically qualified (Category 2) objects falling and striking essential seismically qualified (Category 1) objects has always been a significant, yet analytically difficult problem, particularly in evaluating the potential damage to equipment that may result from earthquakes. Analytical solutions for impact problems are conservative and available for mostly simple configurations. In a nuclear facility, the [open quotes]sources[close quotes] and [open quotes]targets[close quotes] requiring evaluation are frequently irregular in shape and configuration, making calculations and computer modeling difficult. Few industry or regulatory rules are available on this topic even though it is a source of considerable construction upgrade costs. A drop test program was recently conducted to develop a more accurate understanding of the consequences of seismic interactions. The resulting data can be used as a means to improve the judgment of seismic qualification engineers performing interaction evaluations and to develop realistic design criteria for seismic interactions. Impact tests on various combinations of sources and targets commonly found in one Savannah River Site (SRS) nuclear facility were performed by dropping the sources from various heights onto the targets. This report summarizes results of the Drop Test Program. Force and acceleration time history data are presented as well as general observations on the overall ruggedness of various targets when subjected to impacts from different types of sources.

  6. Seismic II over I Drop Test Program results and interpretation

    International Nuclear Information System (INIS)

    Thomas, B.

    1993-03-01

    The consequences of non-seismically qualified (Category 2) objects falling and striking essential seismically qualified (Category 1) objects has always been a significant, yet analytically difficult problem, particularly in evaluating the potential damage to equipment that may result from earthquakes. Analytical solutions for impact problems are conservative and available for mostly simple configurations. In a nuclear facility, the open-quotes sourcesclose quotes and open-quotes targetsclose quotes requiring evaluation are frequently irregular in shape and configuration, making calculations and computer modeling difficult. Few industry or regulatory rules are available on this topic even though it is a source of considerable construction upgrade costs. A drop test program was recently conducted to develop a more accurate understanding of the consequences of seismic interactions. The resulting data can be used as a means to improve the judgment of seismic qualification engineers performing interaction evaluations and to develop realistic design criteria for seismic interactions. Impact tests on various combinations of sources and targets commonly found in one Savannah River Site (SRS) nuclear facility were performed by dropping the sources from various heights onto the targets. This report summarizes results of the Drop Test Program. Force and acceleration time history data are presented as well as general observations on the overall ruggedness of various targets when subjected to impacts from different types of sources

  7. Small-Scale Spray Releases: Additional Aerosol Test Results

    Energy Technology Data Exchange (ETDEWEB)

    Schonewill, Philip P.; Gauglitz, Phillip A.; Kimura, Marcia L.; Brown, G. N.; Mahoney, Lenna A.; Tran, Diana N.; Burns, Carolyn A.; Kurath, Dean E.

    2013-08-01

    One of the events postulated in the hazard analysis at the Waste Treatment and Immobilization Plant (WTP) and other U.S. Department of Energy (DOE) nuclear facilities is a breach in process piping that produces aerosols with droplet sizes in the respirable range. The current approach for predicting the size and concentration of aerosols produced in a spray leak involves extrapolating from correlations reported in the literature. These correlations are based on results obtained from small engineered spray nozzles using pure liquids with Newtonian fluid behavior. The narrow ranges of physical properties on which the correlations are based do not cover the wide range of slurries and viscous materials that will be processed in the WTP and across processing facilities in the DOE complex. To expand the data set upon which the WTP accident and safety analyses were based, an aerosol spray leak testing program was conducted by Pacific Northwest National Laboratory (PNNL). PNNL’s test program addressed two key technical areas to improve the WTP methodology (Larson and Allen 2010). The first technical area was to quantify the role of slurry particles in small breaches where slurry particles may plug the hole and prevent high-pressure sprays. The results from an effort to address this first technical area can be found in Mahoney et al. (2012a). The second technical area was to determine aerosol droplet size distribution and total droplet volume from prototypic breaches and fluids, including sprays from larger breaches and sprays of slurries for which literature data are largely absent. To address the second technical area, the testing program collected aerosol generation data at two scales, commonly referred to as small-scale and large-scale. The small-scale testing and resultant data are described in Mahoney et al. (2012b) and the large-scale testing and resultant data are presented in Schonewill et al. (2012). In tests at both scales, simulants were used to mimic the

  8. The first operation of the Delphos plant: Test results

    International Nuclear Information System (INIS)

    Sarno, A.; Noviello, G.; Cordisco, S.; Di Paola, L.; Guerra, M.

    1991-09-01

    The data collected during the O and M of the Delphos plant and the testing results are presented and discussed. Together with the maintenance influence on the operation and production of the plant, the various downtime causes are pointed out. An extensive activity has been carried out to investigate the actual behaviour of the photovoltaic generator and the power conditioning unit. The analysis of the experimental results allows to focus on the different causes of loss and suggest some actions to be taken in order to improve the plant efficiency and increase the energy production. (author)

  9. Reproducibility problems of in-service ultrasonic testing results

    International Nuclear Information System (INIS)

    Honcu, E.

    1974-01-01

    The reproducibility of the results of ultrasonic testing is the basic precondition for its successful application in in-service inspection of changes in the quality of components of nuclear power installations. The results of periodic ultrasonic inspections are not satisfactory from the point of view of reproducibility. Regardless, the ultrasonic pulse-type method is suitable for evaluating the quality of most components of nuclear installations and often the sole method which may be recommended for inspection with regard to its technical and economic aspects. (J.B.)

  10. Test beam results from a scintillating fibers-lead calorimeter

    International Nuclear Information System (INIS)

    Caria, M.

    1991-01-01

    The SpaCal collaboration has built prototypes of lead-scintillating fibers calorimter. The aim is to check predicted performances. Here are briefly mentioned results obtained from prototypes tests in beam of e, π, μ at CERN. Layers 2m long of extruded lead, were equipped with 1mm fibers in an hexagonal geometry. The ratio of scintillator to lead was 1/4. Results are presented on the most appealing features of such a calorimeter: energy resolution, homogeneity, containment and compensation. It is shown, that excellent energy resolution togehter with compensation has been achieved. (orig.)

  11. Postirradiation examination results for the Irradiation Effects Test 2

    International Nuclear Information System (INIS)

    Ploger, S.A.; Kerwin, D.K.; Croucher, D.W.

    1978-01-01

    This report presents the postirradiation examination results of Test IE-2 in the Irradiation Effects Test Series conducted under the Thermal Fuels Behavior Program. The objectives of this test were to evaluate the influence of previous cladding irradiation and fuel-cladding diametral gap on fuel rod behavior during a power ramp and during film boiling operation. Test IE-2, conducted in the Power Burst Facility at the Idaho National Engineering Laboratory, employed two 0.97-m-long pressurized water reactor type fuel rods fabricated from previously irradiated zircaloy-4 cladding and two similar rods fabricated from unirradiated cladding. The four rods were subjected to a preconditioning period, followed by a power ramp to an average peak rod power of 68 kW/m and steady state operation for one hour at an individual rod coolant mass flux of 4880 kg/s . m 2 . After a flow reduction to 2550 kg/s . m 2 , film boiling occurred on three rods. An additional flow reduction to 2245 kg/s . m 2 produced film boiling on the remaining fuel rod. Maximum time in film boiling was 90 s. None of the four fuel rods failed during the test. Damage caused by film boiling, as characterized by oxidation, oxide spalling, and collapse at fuel pellet interfaces, was found on all four rods. Film boiling regions on these rods showed evidence of fuel melting, fuel centerline void formation, and internal cladding oxidation resulting from fuel-cladding reaction. Effects of fuel-cladding diametral gap and cladding irradiation are summarized. Measured temperatures and metallographically estimated temperatures are compared at several axial fuel rod locations

  12. Test results of sodium-water reaction testing in near prototypical LMR steam generator

    International Nuclear Information System (INIS)

    Boardman, C.E.; Hui, M.; Neely, H.H.

    1990-01-01

    An extensive test program has been performed in the United States to investigate the effects of large sodium-water reaction events in LMFBR steam generators. Tests were conducted in the Large Leak Test Rig (LLTR) located at the Energy Technology Engineering Center (ETEC). The program was divided into two phases, Series I and Series II, for the purpose of satisfying near-term and long-term needs. Series II was further subdivided into large and intermediate leak tests. This paper will emphasize the Series II intermediate leak tests and resulting conclusions for steam generator design and operation. 11 figs, 2 tabs

  13. Challenges in interpretation of thyroid hormone test results

    Directory of Open Access Journals (Sweden)

    Lalić Tijana

    2016-01-01

    Full Text Available Introduction. In interpreting thyroid hormones results it is preferable to think of interference and changes in concentration of their carrier proteins. Outline of Cases. We present two patients with discrepancy between the results of thyroid function tests and clinical status. The first case presents a 62-year-old patient with a nodular goiter and Hashimoto thyroiditis. Thyroid function test showed low thyroid-stimulating hormone (TSH and normal to low fT4. By determining thyroid status (ТSH, T4, fT4, T3, fT3 in two laboratories, basal and after dilution, as well as thyroxine-binding globulin (TBG, it was concluded that the thyroid hormone levels were normal. The results were influenced by heterophile antibodies leading to a false lower TSH level and suspected secondary hypothyroidism. The second case, a 40-year-old patient, was examined and followed because of the variable size thyroid nodule and initially borderline elevated TSH, after which thyroid status showed low level of total thyroid hormones and normal TSH. Based on additional analysis it was concluded that low T4 and T3 were a result of low TBG. It is a hereditary genetic disorder with no clinical significance. Conclusion. Erroneous diagnosis of thyroid disorders and potentially harmful treatment could be avoided by proving the interference or TBG deficiency whenever there is a discrepancy between the thyroid function results and the clinical picture.

  14. OECD/MCCI 2-D Core Concrete Interaction (CCI) tests : final report February 28, 2006.

    Energy Technology Data Exchange (ETDEWEB)

    Farmer, M. T.; Lomperski, S.; Kilsdonk, D. J.; Aeschlimann, R. W.; Basu, S. (Nuclear Engineering Division); (NRC)

    2011-05-23

    reactor material database for dry cavity conditions is solely one-dimensional. Although the MACE Scoping Test was carried out with a two-dimensional concrete cavity, the interaction was flooded soon after ablation was initiated to investigate debris coolability. Moreover, due to the scoping nature of this test, the apparatus was minimally instrumented and therefore the results are of limited value from the code validation viewpoint. Aside from the MACE program, the COTELS test series also investigated 2-D CCI under flooded cavity conditions. However, the input power density for these tests was quite high relative to the prototypic case. Finally, the BETA test series provided valuable data on 2-D core concrete interaction under dry cavity conditions, but these tests focused on investigating the interaction of the metallic (steel) phase with concrete. Due to these limitations, there is significant uncertainty in the partition of energy dissipated for the ablation of concrete in the lateral and axial directions under dry cavity conditions for the case of a core oxide melt. Accurate knowledge of this 'power split' is important in the evaluation of the consequences of an ex-vessel severe accident; e.g., lateral erosion can undermine containment structures, while axial erosion can penetrate the basemat, leading to ground contamination and/or possible containment bypass. As a result of this uncertainty, there are still substantial differences among computer codes in the prediction of 2-D cavity erosion behavior under both wet and dry cavity conditions. In light of the above issues, the OECD-sponsored Melt Coolability and Concrete Interaction (MCCI) program was initiated at Argonne National Laboratory. The project conducted reactor materials experiments and associated analysis to achieve the following technical objectives: (1) resolve the ex-vessel debris coolability issue through a program that focused on providing both confirmatory evidence and test data for the

  15. Tank 241-AP-105, cores 208, 209 and 210, analytical results for the final report

    International Nuclear Information System (INIS)

    Nuzum, J.L.

    1997-01-01

    This document is the final laboratory report for Tank 241-AP-105. Push mode core segments were removed from Risers 24 and 28 between July 2, 1997, and July 14, 1997. Segments were received and extruded at 222-S Laboratory. Analyses were performed in accordance with Tank 241-AP-105 Push Mode Core Sampling and Analysis Plan (TSAP) (Hu, 1997) and Tank Safety Screening Data Quality Objective (DQO) (Dukelow, et al., 1995). None of the subsamples submitted for total alpha activity (AT), differential scanning calorimetry (DSC) analysis, or total organic carbon (TOC) analysis exceeded the notification limits as stated in TSAP and DQO. The statistical results of the 95% confidence interval on the mean calculations are provided by the Tank Waste Remediation Systems Technical Basis Group, and are not considered in this report. Appearance and Sample Handling Two cores, each consisting of four segments, were expected from Tank 241-AP-105. Three cores were sampled, and complete cores were not obtained. TSAP states core samples should be transported to the laboratory within three calendar days from the time each segment is removed from the tank. This requirement was not met for all cores. Attachment 1 illustrates subsamples generated in the laboratory for analysis and identifies their sources. This reference also relates tank farm identification numbers to their corresponding 222-S Laboratory sample numbers

  16. Tank 241-T-201, core 192 analytical results for the final report

    Energy Technology Data Exchange (ETDEWEB)

    Nuzum, J.L.

    1997-08-07

    This document is the final laboratory report for Tank 241-T-201. Push mode core segments were removed from Riser 3 between April 24, 1997, and April 25, 1997. Segments were received and extruded at 222-S Laboratory. Analyses were performed in accordance with Tank 241-T-201 Push Mode Core Sampling and Analysis Plan (TSAP) (Hu, 1997), Letter of Instruction for Core Sample Analysis of Tanks 241-T-201, 241-T-202, 241-T-203, and 241-T-204 (LOI) (Bell, 1997), Additional Core Composite Sample from Drainable Liquid Samples for Tank 241-T-2 01 (ACC) (Hall, 1997), and Safety Screening Data Quality Objective (DQO) (Dukelow, et al., 1995). None of the subsamples submitted for total alpha activity (AT) or differential scanning calorimetry (DSC) analyses exceeded the notification limits stated in DQO. The statistical results of the 95% confidence interval on the mean calculations are provided by the Tank Waste Remediation Systems Technical Basis Group, and are not considered in this report.

  17. Tank 241-AP-105, cores 208, 209 and 210, analytical results for the final report

    Energy Technology Data Exchange (ETDEWEB)

    Nuzum, J.L.

    1997-10-24

    This document is the final laboratory report for Tank 241-AP-105. Push mode core segments were removed from Risers 24 and 28 between July 2, 1997, and July 14, 1997. Segments were received and extruded at 222-S Laboratory. Analyses were performed in accordance with Tank 241-AP-105 Push Mode Core Sampling and Analysis Plan (TSAP) (Hu, 1997) and Tank Safety Screening Data Quality Objective (DQO) (Dukelow, et al., 1995). None of the subsamples submitted for total alpha activity (AT), differential scanning calorimetry (DSC) analysis, or total organic carbon (TOC) analysis exceeded the notification limits as stated in TSAP and DQO. The statistical results of the 95% confidence interval on the mean calculations are provided by the Tank Waste Remediation Systems Technical Basis Group, and are not considered in this report. Appearance and Sample Handling Two cores, each consisting of four segments, were expected from Tank 241-AP-105. Three cores were sampled, and complete cores were not obtained. TSAP states core samples should be transported to the laboratory within three calendar days from the time each segment is removed from the tank. This requirement was not met for all cores. Attachment 1 illustrates subsamples generated in the laboratory for analysis and identifies their sources. This reference also relates tank farm identification numbers to their corresponding 222-S Laboratory sample numbers.

  18. Tank 241-T-201, core 192 analytical results for the final report

    International Nuclear Information System (INIS)

    Nuzum, J.L.

    1997-01-01

    This document is the final laboratory report for Tank 241-T-201. Push mode core segments were removed from Riser 3 between April 24, 1997, and April 25, 1997. Segments were received and extruded at 222-S Laboratory. Analyses were performed in accordance with Tank 241-T-201 Push Mode Core Sampling and Analysis Plan (TSAP) (Hu, 1997), Letter of Instruction for Core Sample Analysis of Tanks 241-T-201, 241-T-202, 241-T-203, and 241-T-204 (LOI) (Bell, 1997), Additional Core Composite Sample from Drainable Liquid Samples for Tank 241-T-2 01 (ACC) (Hall, 1997), and Safety Screening Data Quality Objective (DQO) (Dukelow, et al., 1995). None of the subsamples submitted for total alpha activity (AT) or differential scanning calorimetry (DSC) analyses exceeded the notification limits stated in DQO. The statistical results of the 95% confidence interval on the mean calculations are provided by the Tank Waste Remediation Systems Technical Basis Group, and are not considered in this report

  19. Automation and results of Adjacent Band Emission testing

    Science.gov (United States)

    2015-03-01

    Problem Statement : Multiple groups conduct tests in various ways - Outcomes vary based on test setup and assumptions - No standard has been established to conduct such tests - Spectrum is scarce and the need for compliance testing will only increase...

  20. Postirradiation examination results for the Irradiation Effects Test IE-5

    International Nuclear Information System (INIS)

    Cook, T.F.; Ploger, S.A.; Hobbins, R.R.

    1978-03-01

    The results are presented of the postirradiation examination of four pressurized water reactor type fuel rods which were tested in-pile under a fast power ramp and film boiling operation during Irradiation Effects (IE) Test 5. The major objectives of this test were to evaluate the effects of simulated fission products on fuel rod behavior during a fast power ramp, to determine the effects of high initial internal pressure on a fuel rod during film boiling, and to assess fuel rod property changes that occur during film boiling in a fuel rod with previously irradiated cladding. The overall condition of the rods and changes that occurred in fuel and cladding as a result of the power ramp and film boiling operation, as determined from the postirradiation examination, are reported and analyzed. Effects of the simulated fission products on fuel rod behavior during a power ramp are discussed. The effect of high internal pressure on rod behavior during film boiling is evaluated. Cladding temperatures are estimated at various axial and circumferential locations. Cladding embrittlement by oxidation is also assessed