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Sample records for facility-b mftf-b axicell

  1. Mirror Fusion Test Facility-B (MFTF-B) axicell configuration: NbTi magnet system. Manufacturing/producibility final report. Volume 2

    International Nuclear Information System (INIS)

    Ritschel, A.J.; White, W.L.

    1985-05-01

    This Final MFTF-B Manufacturing/Producibility Report covers facilities, tooling plan, manufacturing sequence, schedule and performance, producibility, and lessons learned for the solenoid, axicell, and transition coils, as well as a deactivation plan, conclusions, references, and appendices

  2. High field Nb/sub 3/Sn Axicell insert coils for the Mirror Fusion Test Facility-B (MFTF-B) axicell configuration. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Baldi, R.W.; Tatro, R.E.; Scanlan, R.M.; Agarwal, K.L.; Bailey, R.E.; Burgeson, J.E.; Kim, I.K.; Magnuson, G.D.; Mallett, B.D.; Pickering, J.L.

    1984-03-01

    Two 12-tesla superconducting insert coils are being designed by General Dynamics Convair Division for the axicell regions of MFTF-B for Lawrence Livermore National Laboratory. A major challenge of this project is to ensure that combined fabrication and operational strains induced in the conductor are within stringent limitations of the relatively brittle Nb/sub 3/Sn superconductor filaments. These coils are located in the axicell region of MFTF-B. They have a clear-bore diameter of 36.195cm (14.25 inches) and consist of 27 double pancakes (i.e., 54 pancakes per coil) would on an electrically insulated 304LN stainless steel/bobbin helium vessel. Each pancake has 57 turns separated by G-10CR insulation. The complete winding bundle has 4.6 million ampere-turns and uniform current density of 2007 A/cm/sup 2/. In conjunction with the other magnets in the system, they produce a 12-tesla central field and a 12.52-tesla peak field. A multifilamentary Nb/sub 3/Sn conductor was selected to meet these requirements. The conductor consists of a monolithic insert soldered into a copper stabilizer. Sufficient cross-sectional area and work-hardening of the copper stabilizer has been provided for the conductor to self-react the electromagnetic Lorentz force induced hoop stresses with normal operational tensile strains less than 0.07 percent.

  3. High field Nb3Sn Axicell insert coils for the Mirror Fusion Test Facility-B (MFTF-B) axicell configuration. Final report

    International Nuclear Information System (INIS)

    Baldi, R.W.; Tatro, R.E.; Scanlan, R.M.

    1984-03-01

    Two 12-tesla superconducting insert coils are being designed by General Dynamics Convair Division for the axicell regions of MFTF-B for Lawrence Livermore National Laboratory. A major challenge of this project is to ensure that combined fabrication and operational strains induced in the conductor are within stringent limitations of the relatively brittle Nb 3 Sn superconductor filaments. These coils are located in the axicell region of MFTF-B. They have a clear-bore diameter of 36.195cm (14.25 inches) and consist of 27 double pancakes (i.e., 54 pancakes per coil) would on an electrically insulated 304LN stainless steel/bobbin helium vessel. Each pancake has 57 turns separated by G-10CR insulation. The complete winding bundle has 4.6 million ampere-turns and uniform current density of 2007 A/cm 2 . In conjunction with the other magnets in the system, they produce a 12-tesla central field and a 12.52-tesla peak field. A multifilamentary Nb 3 Sn conductor was selected to meet these requirements. The conductor consists of a monolithic insert soldered into a copper stabilizer. Sufficient cross-sectional area and work-hardening of the copper stabilizer has been provided for the conductor to self-react the electromagnetic Lorentz force induced hoop stresses with normal operational tensile strains less than 0.07 percent

  4. Axicell MFTF-B superconducting-magnet system

    International Nuclear Information System (INIS)

    Wang, S.T.; Bulmer, R.; Hanson, C.; Hinkle, R.; Kozman, T.; Shimer, D.; Tatro, R.; VanSant, J.; Wohlwend, J.

    1982-01-01

    The Axicell MFTF-B magnet system will provide the field environment necessary for tandem mirror plasma physics investigation with thermal barriers. The performance of the device will stimulate DT to achieve energy break-even plasma conditions. Operation will be with deuterium only. There will be 24 superconducting coils consisting of 2 sets of yin-yang pairs, 14 central-cell solenoids, 2 sets of axicell mirror-coil pairs, and 2 transition coils between the axicell mirror coil-pairs and the yin-yang coils. This paper describes the progress in the design and construction of MFTF-B Superconducting-Magnet System

  5. Mirror Fusion Test Facility-B (MFTF-B) axicell configuration: NbTi magnet system. Design and analysis summary. Volume 1

    International Nuclear Information System (INIS)

    Heathman, J.H.; Wohlwend, J.W.

    1985-05-01

    This report summarizes the designs and analyses produced by General Dynamics Convair for the four Axicell magnets (A1 and A20, east and west), the four Transition magnets (T1 and T2, east and west), and the twelve Solenoid magnets (S1 through S6, east and west). Over four million drawings and specifications, in addition to detailed stress analysis, thermal analysis, electrical, instrumentation, and verification test reports were produced as part of the MFTF-B design effort. Significant aspects of the designs, as well as key analysis results, are summarized in this report. In addition, drawing trees and lists off detailed analysis and test reports included in this report define the locations of the detailed design and analysis data

  6. Mirror Fusion Test Facility-B (MFTF-B) axicell configuration: NbTi magnet system. Design and analysis summary. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Heathman, J.H.; Wohlwend, J.W.

    1985-05-01

    This report summarizes the designs and analyses produced by General Dynamics Convair for the four Axicell magnets (A1 and A20, east and west), the four Transition magnets (T1 and T2, east and west), and the twelve Solenoid magnets (S1 through S6, east and west). Over four million drawings and specifications, in addition to detailed stress analysis, thermal analysis, electrical, instrumentation, and verification test reports were produced as part of the MFTF-B design effort. Significant aspects of the designs, as well as key analysis results, are summarized in this report. In addition, drawing trees and lists off detailed analysis and test reports included in this report define the locations of the detailed design and analysis data.

  7. Axicell design for the end plugs of MFTF-B

    International Nuclear Information System (INIS)

    Thomassen, K.I.; Karpenko, V.N.

    1982-01-01

    Certain changes in the end-plug design in the Mirror Fusion Test Facility (MFTF-B) are described. The Laboratory (LLNL) proposes to implement these changes as soon as possible in order to construct the machine in an axicell configuration. The present physics and technology goals as well as the project cost and schedule will not be affected by these changes

  8. Progress on axicell MFTF-B superconducting magnet systems

    International Nuclear Information System (INIS)

    Wang, S.T.; Kozman, T.A.; Hanson, C.L.; Shimer, D.W.; VanSant, J.H.; Zbasnik, J.

    1983-01-01

    Since the entire Mirror Fusion Test Facility (MFTF-B) Magnet System was reconfigured from the original A-cell to an axicell design, much progress has been made on the design, fabrication, and installation planning. The axicell MFTF-B magnet array consists of a total of 26 large superconducting main coils. This paper provides an engineering overview of the progress of these coils. Recent studies on the effects of field errors on the plasma at the recircularizing region (transition coils) show that small field errors will generate large displacements of the field lines. These field errors might enhance radial electron heat transport and deteriorate the plasma confinement. Therefore, 16 superconducting trim coils have been designed to correct the coil misalignments. Progress of the trim coils are reported also

  9. Physics basis for an axicell design for the end plugs of MFTF-B

    International Nuclear Information System (INIS)

    Baldwin, D.E.; Logan, B.G.

    1982-01-01

    The primary motivation for conversion of MFTF-B to an axicell configuration lies in its engineering promise as a reactor geometry based on circular high-magnetic-field coils. In comparing this configuration to the previous A-cell geometry, we find a number of differences that might significantly affect the physics performance. The purpose of the present document is to examine those features and to assess their impact on the performance of the axicell, as compared to the A-cell configuration, for MFTF-B. In so doing, we address only those issues thought to be affected by the change in geometry and refer to the original report Physics Basis for MFTF-B, for discussion of those issues thought not to be affected. In Sec. 1, we summarize these physics issues. In Sec. 2, we describe operating scenarios in the new configuration. In the Appendices, we discuss those physics issues that require more detailed treatment

  10. Static and dynamic analyses on the MFTF [Mirror Fusion Test Facility]-B Axicell Vacuum Vessel System: Final report

    International Nuclear Information System (INIS)

    Ng, D.S.

    1986-09-01

    The Mirror Fusion Test Facility (MFTF-B) at Lawrence Livermore National Laboratory (LLNL) is a large-scale, tandem-mirror-fusion experiment. MFTF-B comprises many highly interconnected systems, including a magnet array and a vacuum vessel. The vessel, which houses the magnet array, is supported by reinforced concrete piers and steel frames resting on an array of foundations and surrounded by a 7-ft-thick concrete shielding vault. The Pittsburgh-Des Moines (PDM) Corporation, which was awarded the contract to design and construct the vessel, carried out fixed-base static and dynamic analyses of a finite-element model of the axicell vessel and magnet systems, including the simulation of various loading conditions and three postulated earthquake excitations. Meanwhile, LLNL monitored PDM's analyses with modeling studies of its own, and independently evaluated the structural responses of the vessel in order to define design criteria for the interface members and other project equipment. The assumptions underlying the finite-element model and the behavior of the axicell vessel are described in detail in this report, with particular emphasis placed on comparing the LLNL and PDM studies and on analyzing the fixed-base behavior with the soil-structure interaction, which occurs between the vessel and the massive concrete vault wall during a postulated seismic event. The structural members that proved sensitive to the soil effect are also reevaluated

  11. Options for axisymmetric operation of MFTF-B

    International Nuclear Information System (INIS)

    Fenstermacher, M.E.; Devoto, R.S.; Thomassen, K.I.

    1986-01-01

    The flexibility of MFTF-B for axisymmetric experiments has been investigated. Interhcanging the axicell coils and increasing their separation results in an axisymmetric plug cell with 12:1 and 6:1 inner and outer mirror ratios, respectively. For axisymmetric operation, the sloshing-ion neutral beams, ECRH gyrotrons, and the pumping system would be moved to the axicell. Stabilization by E-rings could be explored in this configuration. With the addition of octopole magnets, off-axis multipole stabilization could also be tested. Operating points for octopole and E-ring-stabilized configurations with properties similar to those of the quadrupole MFTF-B, namely T/sub ic/ = 10 - 15 keV and n/sub c/ approx. = 3 x 10 13 cm -3 , have been obtained. Because of the negligible radial transport of central-cell ions, the required neutral-beam power in the central cell has been dramatically reduced. In addition, because MHD stabilization is achieved by off-axis hot electrons in both cases, much lower barrier beta is possible, which aids in reducing the barrier ECRH power. Total ECRH power in the end cell is projected to be approx. =1 MW. Possible operating points for both octopole and E-ring configurations are described along with the stability considerations involved

  12. Design and fabrication of the superconducting-magnet system for the Mirror Fusion Test Facility (MFTF-B)

    International Nuclear Information System (INIS)

    Tatro, R.E.; Wohlwend, J.W.; Kozman, T.A.

    1982-01-01

    The superconducting magnet system for the Mirror Fusion Test Facility (MFTF-B) consists of 24 magnets; i.e. two pairs of C-shaped Yin-Yang coils, four C-shaped transition coils, four solenoidal axicell coils, and a 12-solenoid central cell. General Dynamics Convair Division has designed all the coils and is responsible for fabricating 20 coils. The two Yin-Yang pairs (four coils) are being fabricated by the Lawrence Livermore National Laboratory. Since MFTF-B is not a magnet development program, but rather a major physics experiment critical to the mirror fusion program, the basic philosophy has been to use proven materials and analytical techniques wherever possible. The transition and axicell coils are currently being analyzed and designed, while fabrication is under way on the solenoid magnets

  13. MFTF-B plasma-diagnostic system

    International Nuclear Information System (INIS)

    Throop, A.L.; Goerz, D.A.; Thomas, S.R.

    1981-01-01

    This paper describes the current design status of the plasma diagnostic system for MFTF-B. In this paper we describe the system requirement changes which have occurred as a result of the funded rescoping of the original MFTF facility into MFTF-B. We outline the diagnostic instruments which are currently planned, and present an overview of the diagnostic system

  14. Central cell confinement in MFTF-B

    International Nuclear Information System (INIS)

    Jong, R.A.

    1981-01-01

    The point code TANDEM has been used to survey the range of plasma parameters which can be attained in MFTF-B. The code solves for the electron and ion densities and temperatures in the central cell, yin-yang, barrier, and A-cell regions as well as the plasma potential in each region. In these studies, the A-cell sloshing ion beams were fixed while the neutral beams in the yin-yang and central cell, the gas feed in the central cell, and the applied ECRH power β, central cell ion density and temperature, and the confining potential are discussed

  15. Magnetic shielding tests for MFTF-B neutral beamlines

    International Nuclear Information System (INIS)

    Kerns, J.; Fabyan, J.; Wood, R.; Koger, P.

    1983-01-01

    A test program to determine the effectiveness of various magnetic shielding designs for MFTF-B beamlines was established at Lawrence Livermore National Laboratory (LLNL). The proposed one-tenth-scale shielding-design models were tested in a uniform field produced by a Helmholtz coil pair. A similar technique was used for the MFTF source-injector assemblies, and the model test results were confirmed during the Technology Demonstration in 1982. The results of these tests on shielding designs for MFTF-B had an impact on the beamline design for MFTF-B. The iron-core magnet and finger assembly originally proposed were replaced by a simple, air-core, race-track-coil, bending magnet. Only the source injector needs to be magnetically shielded from the fields of approximately 400 gauss

  16. Neutral-beam aiming and calorimetry for MFTF-B

    International Nuclear Information System (INIS)

    Goldner, A.I.; Margolies, D.

    1981-01-01

    The vessel for the Tandem Mirror Fusion Test Facility (MFTF-B) will have up to eleven 0.5-s-duration neutral-beam injectors for the initial heating of the MFTF-B plasma. Knowing the exact alignment of the beams and their total power is critical to the performance of the experiment. Using prototype aiming and calorimetry systems on the High Voltage Test Stand (HVTS) at Lawrence Livermore National Laboratory (LLNL), we hope to prove our ability to obtain an aiming accuracy of +-1 cm at the plasma and a calorimetric accuracy of +-5% of the actual total beam energy

  17. 1000 kW ICRH amplifiers for MFTF-B

    International Nuclear Information System (INIS)

    Boksberger, U.

    1986-01-01

    For the startup of the MFTF-B ICRH heating will be applied. Two commercial amplifiers derived from standard broadcast transmitters provide 1000 kW RF power each into a matching system for any VSWR as high as 1.5. Emphasis is put on the specific environment of magnetic fields and seismic loads as well as to the particular RF power control requirements and remote operation. Also addressed is the amplifier's performance into a typical load. The load variations due to the MFTF-B plasma coupling were calculated by TRW

  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. D-T axicell magnet system for MFTF-α+T

    International Nuclear Information System (INIS)

    Srivastava, V.C.

    1983-01-01

    The configuration and design of the deuterium-tritium (D-T) axicell superconducting magnets for the Mirror Fusion Test Facility (MFTF-α+T) are described. The MFTF-α+T is an upgrade of the MFTF-B, with new end-plug magnets and a neutron-producing central D-T axicell section. The 4-m long axicell - its length defined by the 12-T peaks in the mirror field - is beam fueled and heated by two beam lines, each with four neutral beam injection ports. Two large superconducting coils (means diameter approx. 3.8 m) located at Z = +-2.40 m, in conjunction with a small copper coil located outside the test volume region, produce the 4.5-T mirror midplane field. This background field is augmented by two copper coils to create the 12-T peak mirror fields at Z = +-2 m. The central region of the axicell accommodates a 1-m-long, replaceable blanket test module. The length (4 m) of the axicell was chosen to provide relatively uniform neutron wall loading over the test module. In many respects, this axicell is less than full scale, but it could be viewed as a short section of a reactor, complete with the support systems and technologies associated with a mirror reactor. The peak field at the superconducting coils is 10.8 T. The coils employ hybrid superconducting winding - Nb 3 Sn conductor in the 8- to 12-T region and NbTi in the 0- to 8-T region. The winding is cryostable and is cooled by a 4.2 K liquid helium bath. The conductor design, the winding design, and the performance analyses for these superconducting coils are described

  20. Physics conceptual design for the MFTF-B transition coil

    International Nuclear Information System (INIS)

    Baldwin, D.E.; Bulmer, R.H.

    1982-01-01

    The physics constraints related to finite-β equilibria, β limits due to curvature-driven MHD modes, and ion transport in the central cell. These physics constraints had to be satisfied subject to certain non-physics constraints. Principal among these were the geometric and structural features of the existing MFTF-B magnet set and the required access for neutral beams for pumping. These constraints and their origins are discussed

  1. Maintenance and availability considerations for MFTF-B upgrade

    International Nuclear Information System (INIS)

    Spampinato, P.T.

    1983-01-01

    The upgrade of the Mirror Fusion Test Facility (MFTF-B) tandem mirror device incorporates the operation of advanced systems plus the requirement for remote maintenance. To determine if the operating availability goal of this device is achievable, an assessment of component lifetimes was made, along with estimates of device downtime. Key subsystem components were considered from the magnet, heating, impurity control, pumping, and test module systems. Component replacements were grouped into three categories, and a lifetime operating plan, including component replacements, was developed. It was determined that this device could achieve a 10% operating availability

  2. Electrical supply for MFTF-B superconducting magnet system

    International Nuclear Information System (INIS)

    Shimer, D.W.; Owen, E.W.

    1985-01-01

    The MFTF-B magnet system consists of 42 superconducting magnets which must operate continuously for long periods of time. The magnet power supply system is designed to meet the operational requirements of accuracy, flexibility, and reliability. The superconducting magnets require a protection system to protect against critical magnet faults of quench, current lead overtemperature, and overcurrent. The protection system is complex because of the large number of magnets, the strong coupling between magnets, and the high reliability requirement. This paper describes the power circuits and the components used in the design

  3. Design of the electromagnetic fluctuations diagnostic for MFTF-B

    International Nuclear Information System (INIS)

    House, P.A.; Goerz, D.A.; Martin, R.

    1983-01-01

    The Electromagnetic Fluctuations (EMF) diagnostic will be used to monitor ion fluctuations which could be unstable in MFTF-B. Each probe assembly includes a high impedance electrostatic probe to measure potential fluctuations, and a group of nested, single turn loops to measure magnetic fluctuations in three directions. Eventually, more probes and loops will be added to each probe assembly for making more detailed measurements. The sensors must lie physically close to the plasma edge and are radially positionable. Also, probes at separate axial locations can be positioned to connect along the same magnetic field line. These probes are similar in concept to the rf probes used on TMX, but the high thermal load for 30-second shots on MFTF-B requires a water-cooled design along with temperature monitors. Each signal channel has a bandwidth of .001 to 150 MHz and is monitored by up to four different data channels which obtain amplitude and frequency information. This paper describes the EMF diagnostic and presents the detailed mechanical and electrical designs

  4. Design and fabrication of the MFTF-B magnet system

    International Nuclear Information System (INIS)

    Tatro, R.E.; Kozman, T.A.

    1985-09-01

    The MFTF-B superconducting magnet system consists of 40 NbTi magnets and two Nb 3 Sn magnets. General Dynamics (GD) designed all magnets except for the small trim coils. GD then fabricated 20 NbTi magnets, while LLNL fabricated 20 NbTi magnets and two Nb 3 Sn magnets. The design phase was completed in February 1984 and included the competitive procurement of magnet structural fabrication, superconductor, G-10CR insulation, support struts and bearings, vapor-cooled leads, and thermal shields for all magnets. Fabrication of all magnets was completed in March 1985. At GD, dual assembly lines were necessary during fabrication in order to meet the aggressive LLNL schedule. The entire magnet system has been installed and aligned at LLNL, and Tech Demo tests will be performed during September-November 1985

  5. Data triggered data processing at MFTF-B

    International Nuclear Information System (INIS)

    Jackson, R.J.; Balch, T.R.; Preckshot, G.G.

    1985-01-01

    A primary characteristic of most batch systems is that the input data files must exist before jobs are scheduled. On the Mirror Fusion Test Facility (MFTF-B) at Lawrence Livermore National Laboratory we schedule jobs to process experimental data to be collected during a five minute shot cycle. Our data-driven processing system emulates a coarsely granular data flow architecture. Processing jobs are scheduled before the experimental data is collected. Processing jobs ''fire'', or execute, as input data becomes available. Similar to UNIX ''pipes'', data produced by upstream processing nodes may be used as inputs by following nodes. Users, working on our networked SUN workstations, specify data processing templates which define processes and their data dependencies. Data specifications indicate the source of data; actual associations with specific data instantiations are made when the jobs are scheduled. We report here on details of diagnostic data processing and our experiences

  6. Alternative connections for the large MFTF-B solenoids

    International Nuclear Information System (INIS)

    Owen, E.W.; Shimer, D.W.; Wang, S.T.

    1983-01-01

    The MFTF-B central-cell solenoids are a set of twelve closely coupled, large superconducting magnets with similar but not exactly equal currents. Alternative methods of connecting them to their power supplies and dump resistors are investigated. The circuits are evaluated for operating conditions and fault conditions. The factors considered are the voltage to ground during a dump, short circuits, open circuits, quenches, and failure of the protection system to detect a quench. Of particular interest are the current induced in coils that remain superconducting when one or more coils quench. The alternative connections include separate power supplies, combined power supplies, individual dump resistors, series dump resistors and combinations of these. A new circuit that contains coupling resistors is proposed. The coupling resistors do not affect normal fast dumps but reduce the peak induced currents while also reducing the energy rating of the dump resistors. Another novel circuit, the series circuit with diodes, is discussed in detail

  7. Sparking protection for MFTF-B Neutral Beam Power Supplies

    International Nuclear Information System (INIS)

    Cummings, D.B.

    1983-01-01

    This paper describes the upgrade of MFTF-B Neutral Beam Power Supplies for sparking protection. High performance ion sources spark repeatedly so ion source power supplies must be insensitive to sparking. The hot deck houses the series tetrode, arc and filament supplies, and controls. Hot deck shielding has been upgraded and a continuous shield around the arc, filament, gradient grid, and control cables now extends from the hot deck, through the core snubber, to the source. The shield carries accelerating current and connects only to the source. Shielded source cables go through an outer duct which now connects to a ground plane under the hot deck. This hybrid transmission line is a low inductance path for sparks discharging the stray capacitance of the hot deck and isolation transformers, reducing coupling to building steel. Parallel DC current return cables inside the duct lower inductance to reduce inductive turn-off transients. MOVs to ground further limit surges in the remote power supply return. Single point grounding is at the source. No control or rectifier components have been damaged nor are there any known malfunctions due to sparking up to 80 kV output

  8. MFTF-B quasi-optical ECRH transmission system

    International Nuclear Information System (INIS)

    Yugo, J.J.; Shearer, J.W.; Ziolkowski, R.W.

    1983-01-01

    The microwave transmission system for ERCH on MFTF-B will utilize quasi-optical transmission techniques. The system consists of ten gyrotron oscillators: two gyrotrons at 28 GHz, two at 35 GHz, and six at 56 GHz. The 28 and 35 GHz gyrotrons both heat the electrons in the end plug (potential peak) while the 56 GHz sources heat the minimum-B anchor region (potential minimum). Microwaves are launched into a pair of cylindrical mirrors that form a pseudo-cavity which directs the microwaves through the plasma numerous times before they are lost out of the cavity. The cavity allows the microwave beam to reach the resonance zone over a wide range of plasma densities and temperatures. The fundamental electron cyclotron resonance moves to higher axial positions as a result of beta-depression of the magnetic field, doppler shifting of the resonance, and relativistic mass corrections for the electrons. With this system the microwave beam will reach the resonance surface at the correct angle of incidence for any density or temperature without active aiming of the antennas. The cavity also allows the beam to make multiple passes through the plasma to increase the heating efficiency at low temperatures and densities when the single pass absorption is low. In addition, neutral beams and diagnostics have an unobstructed view of the plasma

  9. Sparking protection for MFTF-B neutral beam power supplies

    International Nuclear Information System (INIS)

    Cummings, D.B.

    1983-01-01

    This paper describes the upgrade of MFTF-B Neutral Beam Power Supplies for sparking protection. High performance ion sources spark repeatedly so ion source power supplies must be insensitive to sparking. The hot deck houses the series tetrode, arc and filament supplies, and controls. Hot deck shielding has been upgraded and a continuous shield around the arc, filament, gradient grid, and control cables now extends from the hot deck, through the core snubber, to the source. The shield carries accelerating current and connects only to the source. Shielded source cables go through an outer duct which now connects to a ground plane under the hot deck. This hybrid transmission line is a low inductance path for sparks discharging the stray capacitance of the hot deck and isolation transformers, reducing coupling to building steel. Parallel dc current return cables inside the duct lower inductance to reduce inductive turn-off transients. MOVs to ground further limit surges in the remote power supply return. Single point grounding is at the source. No control or rectifier components have been damaged nor are there any known malfunctions due to sparking up to 80 kV output

  10. Report on the engineering test of the LBL 30 second neutral beam source for the MFTF-B project

    International Nuclear Information System (INIS)

    Vella, M.C.; Pincosy, P.A.; Hauck, C.A.; Pyle, R.V.

    1984-08-01

    Positive ion based neutral beam development in the US has centered on the long pulse, Advanced Positive Ion Source (APIS). APIS eventually focused on development of 30 second sources for MFTF-B. The Engineering Test was part of competitive testing of the LBL and ORNL long pulse sources carried out for the MFTF-B Project. The test consisted of 500 beam shots with 80 kV, 30 second deuterium, and was carried out on the Neutral Beam Engineering Test Facility (NBETF). This report summarizes the results of LBL testing, in which the LBL APIS demonstrated that it would meet the requirements for MFTF-B 30 second sources. In part as a result of this test, the LBL design was found to be suitable as the baseline for a Common Long Pulse Source design for MFTF-B, TFTR, and Doublet Upgrade

  11. Design features of the solenoid magnets for the central cell of the MFTF-B

    International Nuclear Information System (INIS)

    Wohlwend, J.W.; Tatro, R.E.; Ring, D.S.

    1981-01-01

    The 14 superconducting solenoid magnets which form the central cell of the MFTF-B are being designed and fabricated by General Dynamics for the Lawrence Livermore National Laboratory. Each solenoid coil has a mean diameter of five meters and contains 600 turns of a proven conductor type. Structural loading resulting from credible fault events, cooldown and warmup requirements, and manufacturing processes consistent with other MFTF-B magnets have been considered in the selection of 304 LN as the structural material for the magnet. The solenoid magnets are connected by 24 intercoil beams and 20 solid struts which resist the longitudinal seismic and electromagnetic attractive forces and by 24 hanger/side supports which react magnet dead weight and seismic loads. A modular arrangement of two solenoid coils within a vacuum vessel segment allow for sequential checkout and installation

  12. Startup experience with the MFTF-B ECRH 100 kV dc power supply

    International Nuclear Information System (INIS)

    Bishop, S.R.; Goodman, R.A.; Wilson, J.H.

    1983-01-01

    One of the 24 Accel dc Power Supplies (ADCPS) originally intended for the Mirror Fusion Test Facility (MFTF-B) Neutral Beam Power Supply (NBPS) System has been converted to provide negative polarity output at 90 kV with a load current of 64 A dc. The load duty cycle is a pulse of 30-seconds duration with a pulse repetition period of five minutes. A new control system has been built which will serve as a prototype for the MFTF-B ADCPS controls, and a test setup was built which will be used to test the ADCPS. The Electron Cyclotron Resonance Heating (ECRH) dc Power Supply (DCPS) has been tested under both no-load and dummy-load conditions, under remote control, without notable problems. Test results indicate that the power supply should be reliable and safe to operate, and will meet the load duty requirements

  13. Startup experience with the MFTF-B ECRH 100 kV dc power supply

    International Nuclear Information System (INIS)

    Bishop, S.R.; Goodman, R.A.; Wilson, J.H.

    1983-01-01

    One of the 24 Accel DC Power Supplies (ADCPS) originally intended for the Mirror Fusion Test Facility (MFTF-B) Neutral Beam Power Supply (NBPS) System has been converted to provide negative polarity output at 90 kV with a load current of 64 A dc. The load duty cycle is a pulse of 30-seconds duration with a pulse repetition period of five minutes. A new control system has been built which will serve as a prototype for the MFTF-B ADCPS controls, and a test setup was built which will be used to test the ADCPS. The Electron Cyclotron Resonance Heating (ECRH) DC Power Supply (DCPS) has been tested under both no-load and dummy-load conditions, under remote control, without notable problems. Test results indicate that the power supply should be reliable and safe to operate, and will meet the load duty requirements

  14. Computer circuit analysis of induced currents in the MFTF-B magnet system

    International Nuclear Information System (INIS)

    Magnuson, G.D.; Woods, E.L.

    1981-01-01

    An analysis was made of the induced current behavior of the MFTF-B magnet system. Although the magnet system consists of 22 coils, because of its symmetry we considered only 11 coils in the analysis. Various combinations of the coils were dumped either singly or in groups, with the current behavior in all magnets calculated as a function of time after initiation of the dump

  15. Evaluating and tuning system response in the MFTF-B control and diagnostics computers

    International Nuclear Information System (INIS)

    Palasek, R.L.; Butner, D.N.; Minor, E.G.

    1983-01-01

    The software system running on the Supervisory Control and Diagnostics System (SCDS) of MFTF-B is, for the major part, an event driven one. Regular, periodic polling of sensors' outputs takes place only at the local level, in the sensors' corresponding local control microcomputers (LCC's). An LCC reports a sensor's value to the supervisory computer only if there was a significant change. This report is passed as a message, routed among and acted upon by a network of applications and systems tasks within the supervisory computer (SCDS). Commands from the operator's console are similarly routed through a network of tasks, but in the oppostie direction to the experiment's hardware. In a network such as this, response time is partialy determined by system traffic. Because the hardware of MFTF-B will not be connected to the computer system for another two years, we are using the local control computers to simulate the event driven traffic that we expect to see during MFTF-B operation. In this paper we show how we are using the simulator to measure and evaluate response, loading, throughput, and utilization of components within the computer system. Measurement of the system under simulation allows us to identify bottlenecks and verify their unloosening. We also use the traffic simulators to evaluate prototypes of different algorithms for selected tasks, comparing their responses under the spectrum of traffic intensities

  16. Structural design considerations in the Mirror Fusion Test Facility (MFTF-B) vacuum vessel

    International Nuclear Information System (INIS)

    Vepa, K.; Sterbentz, W.H.

    1981-01-01

    In view of favorable results from the Tandem Mirror Experiment (TMX) also at LLNL, the MFTF project is now being rescoped into a large tandem mirror configuration (MFTF-B), which is the mainline approach to a mirror fusion reactor. This paper concerns itself with the structural aspects of the design of the vessel. The vessel and its intended functions are described. The major structural design issues, especially those influenced by the analysis, are described. The objectives of the finite element analysis and their realization are discussed at length

  17. The local area network for the plasma Diagnostics System of MFTF-B

    International Nuclear Information System (INIS)

    Lau, N.H.; Minor, E.G.

    1983-01-01

    The MFTF-B Plasma Diagnostics System will be implemented in stages, beginning with a start-up set of diagnostics and evolving toward a basic set. The start-up set contains 12 diagnostics which will acquire a total of about 800 Kbytes of data per machine pulse; the basic set contains 23 diagnostics which will acquire a total of about 8 Mbytes of data per pulse. Each diagnostic is controlled by a ''Foundation System'' consisting of a DEC LSI-11/23 microcomputer connected to CAMAC via a 5 Mbits/second serial fiber-optic link and connected to a supervisory computer (Perkin-Elmer 3250) via a 9600 baud RS232 link. The Foundation System is a building block used throughout MFTF-B for control and status monitoring. However, its 9600 baud link to the supervisor presents a bottleneck for the large data transfers required by diagnostics. To overcome this bottleneck the diagnostics Foundation Systems will be connected together with an additional LSI-11/23 called the ''master'' to form a Local Area Network (LAN) for data acquisition. The Diagnostics LAN has a ring architecture with token passing arbitration

  18. Overview of the data acquisition and control system for plasma diagnostics on MFTF-B

    International Nuclear Information System (INIS)

    Wyman, R.H.; Deadrick, F.J.; Lau, N.H.; Nelson, B.C.; Preckshot, G.G.; Throop, A.L.

    1983-01-01

    For MFTF-B, the plasma diagnostics system is expected to grow from a collection of 12 types of diagnostic instruments, initially producing about 1 Megabyte of data per shot, to an expanded set of 22 diagnostics producing about 8 Megabytes of data per shot. To control these diagnostics and acquire and process the data, a system design has been developed which uses an architecture similar to the supervisory/local-control computer system which is used to control other MFTF-B subsystems. This paper presents an overview of the hardware and software that will control and acquire data from the plasma diagnostics system. Data flow paths from the instruments, through processing, and into final archived storage will be described. A discussion of anticipated data rates, including anticipated software overhead at various points of the system, is included, along with the identification of possible bottlenecks. A methodology for processing of the data is described, along with the approach to handle the planned growth in the diagnostic system. Motivations are presented for various design choices which have been made

  19. A user interface on networked workstations for MFTF-B plasma diagnostic instruments

    International Nuclear Information System (INIS)

    Balch, T.R.; Renbarger, V.L.

    1986-01-01

    A network of Sun-2/170 workstations is used to provide an interface to the MFTF-B Plasma Diagnostics System at Lawrence Livermore National Laboratory. The Plasma Diagnostics System (PDS) is responsible for control of MFTF-B plasma diagnostic instrumentation. An EtherNet Local Area Network links the workstations to a central multiprocessing system which furnishes data processing, data storage and control services for PDS. These workstations permit a physicist to command data acquisition, data processing, instrument control, and display of results. The interface is implemented as a metaphorical desktop, which helps the operator form a mental model of how the system works. As on a real desktop, functions are provided by sheets of paper (windows on a CRT screen) called worksheets. The worksheets may be invoked by pop-up menus and may be manipulated with a mouse. These worksheets are actually tasks that communicate with other tasks running in the central computer system. By making entries in the appropriate worksheet, a physicist may specify data acquisition or processing, control a diagnostic, or view a result

  20. Use of spreadsheets for interactive control of MFTF-B plasma diagnostic instruments

    International Nuclear Information System (INIS)

    Preckshot, G.G.; Goldner, A.L.; Kobayashi, A.

    1986-01-01

    The Mirror Fusion Test Facility (MFTF-B) at Lawrence Livermore National Laboratory has a variety of highly individualized plasma diagnostic instruments attached to the experiment. These instruments are controlled through graphics workstations networked to a central computer system. A distributed spreadsheet-like program runs in both the graphics workstations and in the central computer system. An interface very similar to a commercial spreadsheet program is presented to the user at a workstation. In a commercial spreadsheet program, the user may attach mathematical calculation functions to spreadsheet cells. At MFTF-B, hardware control functions, hardware monitoring functions, and communications functions, as well as mathematical functions, may be attached to cells. Both the user and feedback from instrument hardware may make entries in spreadsheet cells; any entry in a spreadsheet cell may cause reevaluation of the cell's associated functions. The spreadsheet approach makes the addition of a new instrument a matter of designing one or more spreadsheet tables with associated meta-language-defined control and communication function strings. This paper describes the details of the spreadsheets and the implementation experience

  1. Local area network for the plasma diagnostics system of MFTF-B

    International Nuclear Information System (INIS)

    Lau, N.H.; Minor, E.G.

    1983-01-01

    The MFTF-B Plasma Diagnostics System will be implemented in stages, beginning with a start-up set of diagnostics and evolving toward a basic set. The start-up set contains 12 diagnostics which will acquire a total of about 800 Kbytes of data per machine pulse; the basic set contains 23 diagnostics which will acquire a total of about 8 Mbytes of data per pulse. Each diagnostic is controlled by a Foundation System consisting of a DEC LSI-11/23 microcomputer connected to CAMAC via a 5 Mbits/second serial fiber-optic link and connected to a supervisory computer (Perkin-Elmer 3250) via a 9600 baud RS232 link. The Foundation System is a building block used throughout MFTF-B for control and status monitoring. However, its 9600 baud link to the supervisor presents a bottleneck for the large data transfers required by diagnostics. To overcome this bottleneck the diagnostics Foundation Systems will be connected together with an additional LSI-11/23 called the master to form a Local Area Network (LAN) for data acquisition

  2. Design of a magnetic field alignment diagnostic for the MFTF-B magnet system

    International Nuclear Information System (INIS)

    Deadrick, F.J.; House, P.A.; Frye, R.W.

    1985-01-01

    Magnet alignment in tandem mirror fusion machines plays a crucial role in achieving and maintaining plasma confinement. Various visual alignment tools have been described by Post et al. to align the Tara magnet system. We have designed and installed a remotely operated magnetic field alignment (MFA) diagnostic system as a part of the Mirror Fusion Test Facility (MFTF-B). It measures critical magnetic field alignment parameters of the MFTF-B coil set while under full-field operating conditions. The MFA diagnostic employs a pair of low-energy, electron beam guns on a remotely positionable probe to trace and map selected magnetic field lines. An array of precision electrical detector paddles locates the position of the electron beam, and thus the magnetic field line, at several critical points. The measurements provide a means to compute proper compensating currents to correct for mechanical misalignments of the magnets with auxiliary trim coils if necessary. This paper describes both the mechanical and electrical design of the MFA diagnostic hardware

  3. Plasma modeling of MFTF-B and the sensitivity to vacuum conditions

    International Nuclear Information System (INIS)

    Porter, G.D.; Rensink, M.

    1984-01-01

    The Mirror Fusion Test Facility (MFTF-B) is a large tandem mirror device currently under construction at Lawrence Livermore National Laboratory. The completed facility will consist of a large variety of components. Specifically, the vacuum vessel that houses the magnetic coils is basically a cylindrical vessel 60 m long and 11 m in diameter. The magnetics system consists of some 28 superconducting coils, each of which is located within the main vacuum vessel. Twenty of these coils are relatively simple solenoidal coils, but the remaining eight are of a more complicated design to provide an octupole component to certain regions of the magnetic field. The vacuum system is composed of a rough vacuum chain, used to evacuate the vessel from atmospheric pressure, and a high vacuum system, used to maintain good vacuum conditions during a plasma shot. High vacuum pumping is accomplished primarily by cryogenic panels cooled to 4.5 0 K. The MFTF-B coil set is shown together with typical axial profiles of magnetic field (a), electrostatic potential (b), and plasma density (c). The plasma is divided into nine regions axially, as labelled on the coil set in Figure 1. The central cell, which is completely azimuthally symmetric, contains a large volume plasma that is confined by a combination of the magnetic fields and the electrostatic potentials in the yin-yang cell

  4. Use of spreadsheets for interactive control of MFTF-B plasma diagnostic instruments

    International Nuclear Information System (INIS)

    Preckshot, G.G.; Goldner, A.; Kobayashi, A.

    1985-01-01

    The Mirror Fusion Test Facility (MFTF-B) at Lawrence Livermore National Laboratory has a variety of highly individualized plasma diagnostic instruments attached to the experiment. These instruments are controlled through graphics workstations networked to a central computer system. A distributed spreadsheet-like program runs in both the graphics workstations and in the central computer system. An interface very similar to a commercial spreadsheet program is presented to the user at a workstation. In a commercial spreadsheet program, the user may attach mathematical calculation functions to spreadsheet cells. At MFTF-B, hardware control functions, hardware monitoring functions, and communications functions, as well as mathematical functions, may be attached to cells. Both the user and feedback from instrument hardware may make entries in spreadsheet cells; any entry in a spreadsheet cell may cause reevaluation of the cell's associated functions. The spreadsheet approach makes the addition of a new instrument a matter of designing one or more spreadsheet tables with associated meta-language-defined control and communication function strings. We report here details of our spreadsheets and our implementation experience

  5. Drift orbits in the TMX and MFTF-B tandem mirrors

    International Nuclear Information System (INIS)

    Byers, J.A.

    1982-01-01

    Drift orbits for the TMX and MFTF-B tandem-mirror designs are followed by using a long-thin expansion of the drift equations. Unexpected asymmetries in the field-line curvatures in the yin-yang end-mirror traps, caused by the transition coils between the solenoid and the yin-yang, result in an elliptical distortion of the drift surface with a/b=1.5 at most, a perhaps tolerable deviation from omnigenity. Yushmanov-trapped particles are no worse than the bulk hot particles. Finite-beta plasma fields, coupled to the asymmetric curvature, produce sizeable banana orbits with widths comparable to the plasma radius, but these orbits are possible for only a few of the particles. Details of the transition through resonance in the solenoid are shown, including the banana shapes of the drift surfaces and the disruption of the surface in the stochastic regime. The orbits in the original design for the A-cell of MFTF-B are the most extreme; in the vacuum fields they all have an extended peanut shape that finally closes only at about 3m. This shape is strongly non-omnigenous and suggests a hollow plasma-density profile. Finite-beta B vectorxnablaB drifts can help to minimize the radial extent of these orbits, but the strength of the vacuum curvatures makes omnigenity only marginally possible. Including B vectorxnablaphi drifts makes omnigenity even more unlikely for the ions, for which the B vectorxnablaB and B vectorxnablaphi drifts are of opposite sign, and conversely helps to omnigenize the drift surfaces of the ECRH 200-keV electrons. It is argued that not every class of particles can have good, i.e. near-omnigenous drifts, regardless of the ability of phi(r) to adjust to limit the radial extent of the orbits. This lack of omnigenity leaves one with no theoretical base for describing the MHD equilibrium in the original designs, but a new magnetic field design for MFTF-B A-cell has apparently completely restored omnigenous orbits. (author)

  6. Integrated operations plan for the MFTF-B Mirror Fusion Test Facility. Volume I. Organization plan

    International Nuclear Information System (INIS)

    1981-12-01

    This plan and the accompanying MFTF-B Integrated Operations Plan are submitted in response to UC/LLNL Purchase Order 3883801, dated July 1981. The organization plan also addresses the specific tasks and trade studies directed by the scope of work. The Integrated Operations Plan, which includes a reliability, quality assurance, and safety plan and an integrated logistics plan, comprises the burden of the report. In the first section of this volume, certain underlying assumptions and observations are discussed setting the requirements and limits for organization. Section B presents the recommended structure itself. Section C Device Availability vs Maintenance and Support Efforts and Section D Staffing Levels and Skills provide backup detail and justification. Section E is a trade study on maintenance and support by LLNL staff vs subcontract and Section F is a plan for transitioning from the construction phase into operation. A brief summary of schedules and estimated costs concludes the volume

  7. Noise filtering algorithm for the MFTF-B computer based control system

    International Nuclear Information System (INIS)

    Minor, E.G.

    1983-01-01

    An algorithm to reduce the message traffic in the MFTF-B computer based control system is described. The algorithm filters analog inputs to the control system. Its purpose is to distinguish between changes in the inputs due to noise and changes due to significant variations in the quantity being monitored. Noise is rejected while significant changes are reported to the control system data base, thus keeping the data base updated with a minimum number of messages. The algorithm is memory efficient, requiring only four bytes of storage per analog channel, and computationally simple, requiring only subtraction and comparison. Quantitative analysis of the algorithm is presented for the case of additive Gaussian noise. It is shown that the algorithm is stable and tends toward the mean value of the monitored variable over a wide variety of additive noise distributions

  8. Design lessons from using programmable controllers in the MFTF-B personnel safety and interlocks system

    International Nuclear Information System (INIS)

    Branum, J.D.

    1983-01-01

    Applying programmable controllers in critical applications such as personnel safety and interlocks systems requires special considerations in the design of both hardware and software. All modern programmable controller systems feature extensive internal diagnostic capabilities to protect against problems such as program memory errors; however most, if not all present designs lack an intrinsic capability for detecting and countering failures on the field-side of their I/O modules. Many of the most common styles of I/O modules can also introduce potentially dangerous sneak circuits, even without component failure. This paper presents the most significant lessons learned to date in the design of the MFTF-B Personnel Safety and Interlocks System, which utilizes two non-redundant programmable controllers with over 800 I/O points each. Specific problems recognized during the design process as well as those discovered during initial testing and operation are discussed along with their specific solutions in hardware and software

  9. Low level signal data acquisition for the MFTF-B superconducting magnet system

    International Nuclear Information System (INIS)

    Montoya, C.R.

    1984-01-01

    Acquisition of low level signals from sensors mounted on the superconducting magnets in the Tandem Mirror Fusion Test Facility (MFTF-B) impose very strict requirements on the magnet signal conditioning and data acquisition system. Of the various types of sensors required, thermocouples and strain gages produce very low level outputs. These low level outputs must be accurately measured in the harsh environment of slowly varying magnetic fields, cryogenic temperatures, high vacuum, 80 kV pulse power, 60 Hz, 17 MHz and 28, 35, and 56 GHz electrical noise and possible neutron radiation. Successful measurements require careful attention to grounding, shielding, signal handling and processing in the data acquisition system. The magnet instrumentation system provides a means of effectively measuring both low level signals and high level signals from all types of sensors. Various methods involved in the design and implementation of the system for signal conditioning and data gathering will be presented

  10. Design and prototype results of a far-infrared interferometer for MFTF-B

    International Nuclear Information System (INIS)

    Monjes, J.A.; Throop, A.L.; Thomas, S.R.; Peebles, A.; Zu, Qin-Zin.

    1983-01-01

    A Far-Infrared (FIR) Laser Interferometer (FLI), operating at 185 μm wavelength is planned as part of the initial start-up set of plasma diagnostics for the Mirror Fusion Test Facility (MFTF-B). The FLI will consist of a heterodyne, three-chord laser interferometer which will be used initially to measure line-integrated plasma density in the high-density, center cell region of the machine. The conceptual system design and analysis has been completed. There are several unique environmental/physical constraints and performance requirements for this system which have required that technology-evaluation and prototyping experiments be completed to support the design effort and confirm the expected performance parameters. Issues which have been addressed include extensive use of long-path dielectric waveguide, coupling and control of free-space propagation of the beam, and polarization control. The results and conclusions of the design analysis and experimental measurements will be presented

  11. 12-T solenoid-design options for the MFTF-B Upgrade

    International Nuclear Information System (INIS)

    Schultz, J.H.; Diatchenko, N.

    1983-01-01

    The major options for the 12 T magnets examined here are the selection of normal, superconducting or hybrid normal/superconducting magnet systems. The tradeoffs are those between the higher initial cost of superconducting magnet system, the need for thick shielding of superconducting magnets, higher recirculating power in the normal magnets and poorly characterized reliability of lightly shielded normal magnets. The size and shielding tradeoffs among these options are illustrated. The design concepts presented here are evaluated only for the first design iteration of MFTF-B + T, mentioned above. In particular, all concepts now being considered have made topological improvements in the center cell, so that neutral beam power is no longer a strong function of choke coil size. This function was strongly favorable to the use of normal magnets over superconducting magnets and its absence will be discussed qualitatively in the cost comparisons

  12. Plasma potential formation and measurement in TMX-U and MFTF-B

    International Nuclear Information System (INIS)

    Grubb, D.P.

    1984-01-01

    Tandem mirrors control the axial variation of the plasma potential to create electrostatic plugs that improve the axial confinement of central cell ions and, in a thermal barrier tandem mirror, control the electron axial heat flow. Measurements of the spatial and temporal variations of the plasma potential are, therefore, important to the understanding of confinement in a tandem mirror. In this paper we discuss potential formation in a thermal barrier tandem mirror and examine the diagnostics and data obtained on the TMX-U device, including measurements of the thermal barrier potential profile using a diagnostic neutral beam and charged particle energy-spectroscopy. We then describe the heavy ion beam probe and other new plasma potential diagnostics that are under development for TMX-U and MFTF-B and examine problem areas where additional diagnostic development is desirable

  13. Ion cyclotron resonance heating (ICRH) start-up antenna for the mirror fusion test facility (MFTF-B)

    International Nuclear Information System (INIS)

    McCarville, T.M.; Romesser, T.E.

    1985-01-01

    The purpose of the ICRH start-up antenna on MFTF-B is to heat the plasma and control the ion distribution as the density increases during start-up. The antenna, consisting of two center fed half turn loops phased 180 0 apart, has been designed for 1 MW of input power, with a goal of coupling 400 kW into the ions. To vary the heating frequency relative to the local ion cyclotron frequency, the antenna is tunable over a range from 7.5 to 12.5 MHz. The thermal requirements common to low duty cycle ICRH antennas are especially severe for the MFTF-B antenna. The stress requirements are also unique, deriving from the possibility of seismic activity or JxB forces if the magnets unexpectedly quench. Considerable attention has been paid to contact control at high current bolt-up joints, and arranging geometries so as to minimize the possibility of voltage breakdown

  14. Design features of the A-cell and transition coils of MFTF-B

    International Nuclear Information System (INIS)

    Tatro, R.E.; Wohlwend, J.W.; Ring, D.S.

    1981-01-01

    The MFTF-B transition coil and A-cell magnet designs use variations of the copper-stabilized NbTi conductor developed by LLNL for the MFTF Yin-Yang magnets. This conductor will be wound on the one inch thick (12.7 mm) stainless steel coil forms using a two-axis winding machine similar to the existing LLNL Yin-Yang winding machine. After winding, covers will be placed over the coil and welded to the coil form to form a helium-tight jacket around the conductor. These jacketed coils are then enclosed in thick structural cases that react the large Lorentz forces on the magnets. The space between the coil jacket and case will be filled by a stainless steel bladder that will be injected with urethane. The injection bladder will provide cooling passages during cooldown as well as transmitting the Lorentz forces between the jacket and the case. The large self-equilibrating lobe-spreading forces on the magnets (29.10 6 lb, 127.0 MN) for the A-cell are reacted primarily through the thick 304 LN case into the external superstructure. The net Lorentz forces and the inertial forces on the magnet are reacted through support systems into the LLNL vacuum vessel structure

  15. Integrated operations plan for the MFTF-B Mirror Fusion Test Facility. Volume II. Integrated operations plan

    Energy Technology Data Exchange (ETDEWEB)

    1981-12-01

    This document defines an integrated plan for the operation of the Lawrence Livermore National Laboratory (LLNL) Mirror Fusion Test Facility (MFTF-B). The plan fulfills and further delineates LLNL policies and provides for accomplishing the functions required by the program. This plan specifies the management, operations, maintenance, and engineering support responsibilities. It covers phasing into sustained operations as well as the sustained operations themselves. Administrative and Plant Engineering support, which are now being performed satisfactorily, are not part of this plan unless there are unique needs.

  16. Application of structural mechanics methods to the design of large tandem mirror fusion devices (MFTF-B)

    International Nuclear Information System (INIS)

    Karpenko, V.N.; Ng, D.S.

    1985-01-01

    The Mirror Fusion Test Facility (MFTF-B) at Lawrence Livermore National Laboratory requires state-of-the-art structural-mechanics methods to deal with access constraints for plasma heating and diagnostics, alignment requirements, and load complexity and variety. Large interactive structures required an integrated analytical approach to achieve a resonable level of overall system optimization. The Tandem Magnet Generator (TMG) creates a magnet configuration for the EFFI calculation of electromagnetic-field forces that, coupled with other loads, form the input loading to magnetic and vessel finite-element models. The anlytical results provide the data base for detailed design of magnet, vessel, foundation, and interaction effects. (orig.)

  17. Integrated operations plan for the MFTF-B Mirror Fusion Test Facility. Volume II. Integrated operations plan

    International Nuclear Information System (INIS)

    1981-12-01

    This document defines an integrated plan for the operation of the Lawrence Livermore National Laboratory (LLNL) Mirror Fusion Test Facility (MFTF-B). The plan fulfills and further delineates LLNL policies and provides for accomplishing the functions required by the program. This plan specifies the management, operations, maintenance, and engineering support responsibilities. It covers phasing into sustained operations as well as the sustained operations themselves. Administrative and Plant Engineering support, which are now being performed satisfactorily, are not part of this plan unless there are unique needs

  18. Engineering study of the neutral beam and rf heating systems for DIII-D, MFTF-B, JET, JT-60 and TFTR

    International Nuclear Information System (INIS)

    Lindquist, W.B.; Staten, S.H.

    1987-01-01

    An engineering study was performed on the rf and neutral beam heating systems implemented for DIII-D, MFTF-B, JET, JT-60 and TFTR. Areas covered include: methodology used to implement the systems, technology, cost, schedule, performance, problems encountered and lessons learned. Systems are compared and contrasted in the areas studied. Summary statements were made on common problems and lessons learned. 3 refs., 6 tabs

  19. Application of structural-mechanics methods to the design of large tandem-mirror fusion devices (MFTF-B). Revision 1

    International Nuclear Information System (INIS)

    Karpenko, V.N.; Ng, D.S.

    1985-01-01

    The Mirror Fusion Test Facility (MFTF-B) at Lawrence Livermore National Laboratory requires state-of-the-art structural-mechanics methods to deal with access constraints for plasma heating and diagnostics, alignment requirements, and load complexity and variety. Large interactive structures required an integrated analytical approach to achieve a reasonable level of overall system optimization. The Tandem Magnet Generator (TMG) creates a magnet configuration for the EFFI calculation of electromagnetic-field forces that, coupled with other loads, form the input loading to magnet and vessel finite-element models. The analytical results provide the data base for detailed design of magnet, vessel, foundation, and interaction effects. 13 refs

  20. Physics basis for MFTF-B

    International Nuclear Information System (INIS)

    Baldwin, D.E.; Logan, B.G.; Simonen, T.C.

    1980-01-01

    The physics overview covers the following topics: (1) classical energetics, (2) single-particle adiabaticity and drift effects, (3) equilibrium considerations, (4) low-frequency stability, (5) microstability of plugs and barriers, and (6) electron axial thermal conduction. Operation scenarios and summaries of initial TMX results are also described

  1. Magnets for the Mirror Fusion Test Facility: testing of the first Yin-Yang and the design and development of other magnets

    International Nuclear Information System (INIS)

    Kozman, T.A.; Wang, S.T.; Chang, Y.

    1983-01-01

    Completed in May 1981, the first Yin-Yang magnet for the tandem Mirror Fusion Test Facility (MFTF-B) at Lawrence Livermore National Laboratory (LLNL) was successfully tested in February 1982 to its full design field (7.68 T) and current (5775 A). Since that time, the entire magnet array has been reconfigured - from the original A-cell to an axicell design. The MFTF-B magnet array now contains a total of 26 large superconducting coils: 2 sets of yin-yang pairs, 2 sets of transition magnets (each containing two coils), 2 sets of axicell magnets (each containing three coils), and 12 central-cell solenoids. This paper chronicles recent magnet history - from te testing of the initial yin-yang set, through the design of the axicell configuration, to the planned development of the system

  2. Multi-megawatt neutral beams for MFTF-B

    International Nuclear Information System (INIS)

    Kerr, R.G.

    1982-01-01

    Multi-megawatt neutral-beam sources have successfully made the transition from prototype to commercial production, with some operational improvements due to the commercialization. Long pulse source operation results will be available soon

  3. Mechanical considerations for MFTF-B plasma-diagnostic system

    International Nuclear Information System (INIS)

    Thomas, S.R. Jr.; Wells, C.W.

    1981-01-01

    The reconfiguration of MFTF to a tandem mirror machine with thermal barriers has caused a significant expansion in the physical scope of plasma diagnostics. From a mechanical perspective, it complicates the plasma access, system interfaces, growth and environmental considerations. Conceptual designs characterize the general scope of the design and fabrication which remains to be done

  4. Programmable controllers replace relays in MFTF-B personnel-safety interlocks

    International Nuclear Information System (INIS)

    Branum, J.D.

    1981-01-01

    This paper describes a new approach for implementing personnel safety interlocks logic using industrial-type programmable controllers. The logic for all personnel safety interlocks except those totally internal to a subsystem is implemented in two non-redundant controllers. A high degree of fail-safe reliability is achieved by augmenting the protective features intrinsic to each controller with those provided by a small amount of external support hardware. The controllers are interfaced to the host computer system via fiber optic data links to enable display of interlock and overall system status on the control room graphic displays. When fully implemented, the controllers will perform the equivalent of over 2000 discreet relay functions

  5. Report on the experience with the Supervisory Control and Diagnostics System (SCDS) of MFTF-B

    International Nuclear Information System (INIS)

    Wyman, R.H.

    1983-01-01

    The Supervisory Control and Diagnostics System (SCDS) of MFTF is a multiprocessor computer system using graphics oriented displays with touch sensitive panels as the primary operator interface. Late in the calendar year 1981 the system was used to control an integrated test of the vacuum vessel, vacuum system, cryogenics system and the superconducting magnet of MFTF. Since the completion of those tests and starting in early calendar 1983 the system has been used for control of the neutral beam test facility at LLNL. This paper presents a short overview of SCDS for the purpose of orientation and then proceeds to describe the difficulties encountered in these preliminary encounters with reality. The band-aids used to hold things together as disaster threatened as well as the long-term solutions to the problems will be discussed. Finally, we will present some comments on system costs and management philosophy

  6. Flexibility of MFTF-B for thermal-barrier modifications and axisymmetric upgrades

    International Nuclear Information System (INIS)

    Thomassen, K.I.

    1981-01-01

    Flexibility in MFTB-B will be achieved partly by using the margins in particle and energy control designed into the machine and partly by making modest changes based on results obtained in TMX Upgrade. This latter flexibility is permitted by the schedule for vessel construction and component fabrication. The changes we might expect were determined by an examination of the processes involved in creating a thermal barrier and by speculating on the range of outcomes from TMX Upgrade experiments

  7. Normal-zone detectors for the MFTF-B coils. Revision 1

    International Nuclear Information System (INIS)

    Owen, E.W.; Shimer, D.W.

    1983-01-01

    In order to protect a set of inductively coupled superconducting magnets, it is necessary to locate and measure normal zone voltages that are small compared with the mutual and self-induced voltages. The method described in this report uses two sets of voltage measurements to locate and measure one or more normal zones in any number of coupled coils. One set of voltages is the outputs of bridges that balance out the self-induced voltages. The other set of voltages can be the voltages across the coils, although alternatives are possible. The two sets of equations form a single combined set of equations. Each normal zone location or combination of normal zones has a set of these combined equations associated with it. It is demonstrated that the normal zone can be located and the correct set chosen, allowing determination of the size of the normal zone. Only a few operations take place in a working detector: multiplication of a constant, addition, and simple decision-making. In many cases the detector for each coil, although weakly linked to the other detectors, can be considered to be independent. An example of the detector design is given for four coils with realistic parameters. The effect on accuracy of changes in the system parameters is discussed

  8. A computer model of the MFTF-B neutral beam accel dc power supply

    International Nuclear Information System (INIS)

    Wilson, J.H.

    1983-01-01

    Using the SCEPTRE circuit modeling code, a computer model was developed for the MFTF Neutral Beam Power Supply System (NBPSS) Accel DC Power Supply (ADCPS). The ADCPS provides 90 kV, 88 A, to the Accel Modulator. Because of the complex behavior of the power supply, use of the computer model is necessary to adequately understand the power supply's behavior over a wide range of load conditions and faults. The model developed includes all the circuit components and parameters, and some of the stray values. The model has been well validated for transients with times on the order of milliseconds, and with one exception, for steady-state operation. When using a circuit modeling code for a system with a wide range of time constants, it can become impossible to obtain good solutions for all time ranges at once. The present model concentrates on the millisecond-range transients because the compensating capacitor bank tends to isolate the power supply from the load for faster transients. Attempts to include stray circuit elements with time constants in the microsecond and shorter range have had little success because of hugh increases in computing time that result. The model has been successfully extended to include the accel modulator

  9. Computer model of the MFTF-B neutral beam Accel dc power supply

    International Nuclear Information System (INIS)

    Wilson, J.H.

    1983-01-01

    Using the SCEPTRE circuit modeling code, a computer model was developed for the MFTF Neutral Beam Power Supply System (NBPSS) Accel dc Power Supply (ADCPS). The ADCPS provides 90 kV, 88 A, to the Accel Modulator. Because of the complex behavior of the power supply, use of the computer model is necessary to adequately understand the power supply's behavior over a wide range of load conditions and faults. The model developed includes all the circuit components and parameters, and some of the stray values. The model has been well validated for transients with times on the order of milliseconds, and with one exception, for steady-state operation. When using a circuit modeling code for a system with a wide range of time constants, it can become impossible to obtain good solutions for all time ranges at once. The present model concentrates on the millisecond-range transients because the compensating capacitor bank tends to isolate the power supply from the load for faster transients. Attempts to include stray circuit elements with time constants in the microsecond and shorter range have had little success because of huge increases in computing time that result. The model has been successfully extended to include the accel modulator

  10. A proposed search for dark-matter axions in the 0.6--16 {mu}eV range

    Energy Technology Data Exchange (ETDEWEB)

    Hagmann, C. [California Univ., Berkeley, CA (United States). Dept. of Physics; Moltz, D.M. [Lawrence Berkeley Lab., CA (United States); Turner, M.S. [Chicago Univ., IL (United States). Dept. of Physics and Astronomy]|[Fermi National Accelerator Lab., Batavia, IL (United States); Sikivie, P.; Sullivan, N.S.; Tanner, D.B. [Florida Univ., Gainesville, FL (United States). Dept. of Physics; Bluele, A.I.; Geraskin, E.V.; Golubev, N.A.; Ishkin, V.V.; Kazachenko, O.V.; Kuzmin, V.; Polushkin, V.G. [AN SSSR, Moscow (USSR). Inst. Yadernykh Issledovanij; Anthony, P.L.; van Bibber, K.; Patrick, R.E.; Shen, S.; Slack, D.S.; Steele, J.V. [Lawrence Livermore National Lab., CA (United States); Villa, F. [Stanford Linear Accelerator Center, Menlo Park, CA (United States)

    1991-11-01

    A proposed experiment is described to search for dark-matter axions in the mass range 0.6--16 {mu}eV. The method is based on the Primakoff conversion of axions into monochromatic microwave photons inside a tunable microwave cavity in a large volume high field magnet. This proposal capitalized on the availability of two Axicell magnets from the MFTF-B fusion machine at LLNL. Assuming a local dark-matter density in axions of {rho}{sub a}= 0.3 GeV/cm{sup 3}, the axion would be found or ruled out at the 97% c.1. in the above mass range in 48 months.

  11. A proposed search for dark-matter axions in the 0. 6--16. mu. eV range

    Energy Technology Data Exchange (ETDEWEB)

    Hagmann, C. (California Univ., Berkeley, CA (United States). Dept. of Physics); Moltz, D.M. (Lawrence Berkeley Lab., CA (United States)); Turner, M.S. (Chicago Univ., IL (United States). Dept. of Physics and Astronomy Fermi National Accelerator Lab., Batavia, IL (United States)); Sikivie, P.; Sullivan, N.S.; Tanner, D.B. (Florida Univ., Gainesville, FL (United States). Dept. of Physics); Bluele, A.I

    1991-11-01

    A proposed experiment is described to search for dark-matter axions in the mass range 0.6--16 {mu}eV. The method is based on the Primakoff conversion of axions into monochromatic microwave photons inside a tunable microwave cavity in a large volume high field magnet. This proposal capitalized on the availability of two Axicell magnets from the MFTF-B fusion machine at LLNL. Assuming a local dark-matter density in axions of {rho}{sub a}= 0.3 GeV/cm{sup 3}, the axion would be found or ruled out at the 97% c.1. in the above mass range in 48 months.

  12. A proposed search for dark-matter axions in the 0.6--16 μeV range

    International Nuclear Information System (INIS)

    Hagmann, C.; Turner, M.S.; Sikivie, P.; Sullivan, N.S.; Tanner, D.B.; Villa, F.

    1991-11-01

    A proposed experiment is described to search for dark-matter axions in the mass range 0.6--16 μeV. The method is based on the Primakoff conversion of axions into monochromatic microwave photons inside a tunable microwave cavity in a large volume high field magnet. This proposal capitalized on the availability of two Axicell magnets from the MFTF-B fusion machine at LLNL. Assuming a local dark-matter density in axions of ρ a = 0.3 GeV/cm 3 , the axion would be found or ruled out at the 97% c.1. in the above mass range in 48 months

  13. MFTF-α + T shield design

    International Nuclear Information System (INIS)

    Gohar, Y.

    1985-01-01

    MFTF-α+T is a DT upgrade option of the Tandem Mirror Fusion Test Facility (MFTF-B) to study better plasma performance, and test tritium breeding blankets in an actual fusion reactor environment. The central cell insert, designated DT axicell, has a 2-MW/m 2 neutron wall loading at the first wall for blanket testing. This upgrade is completely shielded to protect the reactor components, the workers, and the general public from the radiation environment during operation and after shutdown. The shield design for this upgrade is the subject of this paper including the design criteria and the tradeoff studies to reduce the shield cost

  14. A proposed search for dark-matter axions in the 0.6--16 μeV range

    International Nuclear Information System (INIS)

    van Bibber, K.; Sikivie, P.; Sullivan, N.S.; Tanner, D.B.; Moltz, D.M.

    1991-03-01

    A proposed experiment is described to search for dark-matter axions in the mass range 0.6--16 μeV. The method is based on the Primakoff conversion of axions into monochromatic microwave photons inside a tunable microwave cavity in a large volume high field magnet, as described by Sikivie. This proposal capitalizes on the availability of two Axicell magnets from the decommissioned MFTF-B fusion machine at LLNL. Assuming a local dark-matter density in axions of ρ = 0.3 GeV/cm 3 , the axion would be found or ruled out at the 97% c.l. in the above mass range in 48 months. 13 refs., 6 figs., 2 tabs

  15. Numerical study of the mode selection in response spectrum analysis-condensed version

    International Nuclear Information System (INIS)

    Ng, D.S.

    1986-01-01

    For quality assurance of the dynamic response spectrum analysis, the Nuclear Regulatory Commission (NRC) recommends retaining all modes below the cutoff frequency at which the spectral acceleration (S/sub a/) returns to the peak zero period acceleration (ZPA). It also suggests that modes accounting for at least 90 percent of the structural masses be included in the analysis. A simple frame-type structure is generated as a baseline frame. Then groups of oscillators representing substructure are added onto the frame to study substructure behavior. A base case is established for each frame by including the specific number of modes used. The tests are conducted by incrementing the number of modes in the response spectrum analyses starting with one mode. The structural response of each modal increment is compared with the base case to identify the efficiency of mode selection method. All three methods are then applied to the MFTF-B Axicell Vacuum Vessel. The responses in critical components of the vessel, such as hangers and foundations, will be analyzed to confirm the accuracy of the selected method

  16. Thermal and structural analysis of the LBL 10 x 40 cm long pulse accelerator and the 12 x 48 cm common long pulse accelerator for TFTR, doublet III-D, and MFTF-B

    International Nuclear Information System (INIS)

    Wells, R.P.

    1985-11-01

    Stress and deflection of the grid rails of the existing, Lawrence Berkeley Laboratory (LBL) designed, 10 x 40 cm Long Pulse (neutral beam) Accelerator (40LPA) and the expanded 12 x 48 cm version, Common Long Pulse Source (CLPS), have been computed for a series of assumed heat load distributions. The combined stress from self-constraint of thermal expansion and rail holder reaction forces has been calculated. A simplification of the gradient grid rail holder was analyzed and was found to work as well or better than the original 40LPA design under the most probable operating conditions. Heat flux non-uniformity over the rail surface for both accelerator designs was estimated from 40LPA grid calorimetry data for arc and beam extraction operation. The extrapolated total heat load per rail for the CLPS was less than the 1.2 kW value used in this analysis. Under worst case assumptions, the maximum equivalent stress in any of the molybdenum grid rails was less than 20% of yield. For the anticipated heat load distribution on the gradient grid, the predicted deflection of the grid rail meets the 0.0457 mm position tolerance except under extremely non-uniform heat loads

  17. Thermal and structural analysis of the LBL 10 x 40 cm Long Pulse Accelerator and the 12 x 48 cm Common Long Pulse Accelerator for TFTR, Doublet III-D, and MFTF-B

    International Nuclear Information System (INIS)

    Wells, R.P.

    1986-01-01

    Stress and deflection of the grid rails of the existing, Lawrence Berkeley Laboratory (LBL) designed, 10 x 40 cm Long Pulse (neutral beam) Accelerator (40LPA) and the expanded 12 x 48 cm version, Common Long Pulse Source (CLPS), have been computed for a series of assumed heat load distributions. The combined stress from self-constraint of thermal expansion and rail holder reaction forces has been calculated. A simplification of the gradient grid rail holder was analyzed and was found to work as well or better than the original 40LPA design under the most probable operating conditions. Heat flux non-uniformity over the rail surface for both accelerator designs was estimated from 40LPA grid calorimetry data for arc and beam extraction operation. The extrapolated total heat load per rail for the CLPS was less than the 1.2 kW value used in this analysis. Under worst case assumptions, the maximum equivalent stress in any of the molybdenum grid rails was less than 20% of yield. For the anticipated heat load distribution on the gradient grid, the predicted deflection of the grid rail meets the 0.0457 mm position tolerant except under extremely non-uniform heat loads

  18. Configuration and layout of the tandem mirror Fusion Power Demonstrator

    International Nuclear Information System (INIS)

    Clarkson, I.R.; Neef, W.S.

    1983-01-01

    Studies have been performed during the past year to determine the configuration of a tandem mirror Fusion Power Demonstrator (FPD) machine capable of producing 1750 MW of fusion power. The FPD is seen as the next logical step after the Mirror Fusion Test Facility-B (MFTF-B) toward operation of a power reactor. The design of the FPD machine allows a phased construction: Phase I, a hydrogen or deuterium checkout machine; Phase 2, a DT breakeven machine; Phase 3, development of the Phase 2 machine to provide net power and act as a reactor demonstrator. These phases are essential to the development of remote handling equipment and the design of components that will ultimately be remotely handled. Phasing also permits more modes funding early in the program with some costs committed only after reaching major milestones

  19. Mirror Fusion vacuum technology developments

    International Nuclear Information System (INIS)

    Batzer, T.H.; Call, W.R.

    1983-01-01

    Magnetic Mirror Fusion experiments, such as MFTF-B+T (Mirror Fusion Test Facility-B, Tritium Upgrade) and foreseeable follow-on devices, have operational and maintenance requirements that have not yet been fully demonstrated. Among those associated with vacuum technology are the very-high continuous-pumping speeds, 10 7 to 10 8 l/s for D 2 , T 2 and, to a lesser extent, He; the early detection of water leaks from the very-high heat-flux neutral-beam dumps and the detection and location of leaks in the superconducting magnets not protected by guard vacuums. Possible solutions to these problems have been identified and considerable progress has been made toward successfully demonstrating their feasibility

  20. Mirror fusion vacuum technology developments

    International Nuclear Information System (INIS)

    Batzer, T.H.; Call, W.R.

    1983-01-01

    Magnetic Mirror Fusion experiments, such as MFTF-B+T (Mirror Fusion Test Facility-B, Tritium Upgrade) and foreseeable follow-on devices, have operational and maintenance requirements that have not yet been fully demonstrated. Among those associated with vacuum technology are the very-high continuous-pumping speeds, 10 7 to 10 8 l/s for D 2 , T 2 and, to a lesser extent, He; the early detection of water leaks from the very-high heat-flux neutral-beam dumps and the detection and location of leaks in the superconducting magnets not protected by guard vacuums. Possible solutions to these problems have been identified and considerable progress has been made toward successfully demonstrating their feasibility

  1. 324 Facility B-cell quality process plan

    International Nuclear Information System (INIS)

    Carlson, J.L.

    1998-01-01

    B-Cell is currently being cleaned out (i.e., removal of equipment, fixtures and residual radioactive materials) and deactivated. TPA Milestone M-89-02 dictates that all mixed waste and equipment be removed from B-Cell by 5/31/99. The following sections describe the major activities that remain for completion of the TPA milestone. These include: Size Reduce Tank 119 and Miscellaneous Equipment; Load and Ship Low-Level Waste; Remove and Size Reduce the 1B Rack; Collect Dispersible Material from Cell Floor; Remove and Size Reduce the 2A Rack; Size Reduce the 1A Rack; Load and Ship Mixed Waste to PUREX Tunnels; and Move Spent Fuel to A-Cell;

  2. 324 Facility B-Cell quality process plan

    International Nuclear Information System (INIS)

    Carlson, J.L.

    1998-01-01

    B-Cell is currently being cleaned out (i.e., removal of equipment, fixtures and residual radioactive materials) and deactivated. TPA Milestone M-89-02 dictates that all mixed waste and equipment be removed from B-Cell by 5/31/99. The following sections describe the major activities that remain for completion of the TPA milestone. This includes: (1) Size Reduce Tank 119 and Miscellaneous Equipment. This activity is the restart of hotwork in B-Cell to size reduce the remainder of Tank 119 and other miscellaneous pieces of equipment into sizes that can be loaded into a grout container. This activity also includes the process of preparing the containers for shipment from the cell. The specific activities and procedures used are detailed in a table. (2) Load and Ship Low-Level Waste. This activity covers the process of taking a grouted LLW container from B-Cell and loading it into the cask in the REC airlock and Cask Handling Area (CHA) for shipment to the LLBG. The detailed activities and procedures for this part of cell cleanout are included in second table

  3. 324 Facility B-Cell quality process plan

    International Nuclear Information System (INIS)

    Carlson, J.L.

    1998-01-01

    This report documents the quality process plan for the restart of a hot cell in the B Plant, originally a bismuth phosphate processing facility, but later converted to a waste fractionation plant. B-Cell is currently being cleaned out and deactivated. TPA Milestone M-89-02 dictates that all mixed waste and equipment be removed from B-Cell by 5/31/1999. This report describes the major activities that remain for completion of the TPA milestone

  4. Model approach for simulating the thermodynamic behavior of the MFTF cryogenic cooling systems - a status report

    International Nuclear Information System (INIS)

    Sutton, S.B.; Stein, W.; Reitter, T.A.; Hindmarsh, A.C.

    1983-01-01

    A numerical model for calculating the thermodynamic behavior of the MFTF-B cryogenic cooling system is described. Nine component types are discussed with governing equations given. The algorithm for solving the coupled set of algebraic and ordinary differential equations is described. The model and its application to the MFTF-B cryogenic cooling system has not been possible due to lack of funding

  5. Alarm points for fixed oxygen monitors

    International Nuclear Information System (INIS)

    Miller, G.C.

    1987-05-01

    Oxygen concentration monitors were installed in a vault where numerous pipes carried inert cryogens and gases to the Mirror Fusion Test Facility (MFTF-B) experimental vessel at Lawrence Livermore National Laboratory (LLNL). The problems associated with oxygen-monitoring systems and the reasons why such monitors were installed were reviewed. As a result of this review, the MFTF-B monitors were set to sound an evacuation alarm when the oxygen concentration fell below 18%. We chose the 18% alarm criterion to minimize false alarms and to allow time for personnel to escape in an oxygen-deficient environment

  6. Leak testing and repair of fusion devices

    International Nuclear Information System (INIS)

    Kozman, T.A.

    1983-01-01

    The leak testing, reporting and vacuum leak repair techniques of the MFTF yin-yang number one magnet system, the world's largest superconducting magnet system, are discussed. Based on this experience, techniques will be developed for testing and repairing leaks on the 42 MFTF-B magnets. The leak-hunting techniques for the yin-yang magnet systems were applied to two helium circuits (the coil bundle and guard vacuum; both require helium flow for magnet cooldown), their associated piping, liquid nitrogen radiation shields, and piping. Additionally, during MFTF-B operation there will be warm water plasma shields and piping that require leak checking

  7. Local control station for development, testing and maintenance of mirror fusion facility subsystem controls

    International Nuclear Information System (INIS)

    Ables, E.; Kelly, M.F.

    1985-01-01

    A Local Control Station (LCS) was designed and built to provide a simplified ad easily configurable means of controlling any Mirror Fusion Test Facility (MFTF-B) subsystem for the purpose of development, testing and maintenance of the subsystem. All MFTF-B Subsystems incorporate at least one Local Control Computer (LCC) that is connected to and accepts high level commands from one of the Supervisory Control and Diagnostic System (SCDS) computers. The LCS connects directly to the LCC in place of SCDS. The LCS communicates with the subsystem hardware using the same SCDS commands that the local control computer recognizes and as such requires no special configuration of the LCC

  8. Designs of tandem-mirror fusion reactors

    International Nuclear Information System (INIS)

    Carlson, G.A.; Barr, W.L.; Boghosian, B.M.

    1981-01-01

    We have completed a comparative evaluation of several end plug configurations for tandem mirror fusion reactors with thermal barriers. The axi-cell configuration has been selected for further study and will be the basis for a detailed conceptual design study to be carried out over the next two years. The axi-cell end plug has a simple mirror cell produced by two circular coils followed by a transition coil and a yin-yang pair, which provides for MHD stability

  9. Analysis of large scale UO2 Na interactions performed in Europe

    International Nuclear Information System (INIS)

    Berthoud, G.; Jacobs, H.; Knowles, B.

    1994-01-01

    Analysis of the European out of pile Fuel Sodium Interaction Experiments involving kilogram masses of molten oxide is reported i.e. CORECT 2 (CEA), SUS and MFTF-B (AEA), THINA (KfK). Then common conclusions are drawn. (author)

  10. Electrical energy and cost for the mirror fusion test facility

    International Nuclear Information System (INIS)

    Pence, G.

    1983-01-01

    An operational scenario has been developed for the Mirror Fusion Test Facility (MFTF-B) based on the System Requirements, our experience with existing systems, and discussions with the project engineers and designers who are responsible for the systems. This scenario was used to predict the amount of electrical energy needed for running the facility. A generic type listing is included for the equipment considered in each system. A figure shows the anticipated power drain during a five-minute shot sequence from the 115-kV substation, and from the 230-kV and direct feed substations. At this time, the three major substations that will be used for the MFTF-B are billed under three different rate schedules. A table lists these schedules and what they are anticipated as being when the facility becomes operational. The system availability, which is expected to be 0.7 or better, has not been factored into these calculations. This gives a worst case cost for the MFTF-B. Based on this study, it appears that our energy bill will be over $500 000 per month, on the average. This expenditure will constitute a significant portion of the budget needed to operate the MFTF-B. As the systems are refined, and a more accurate picture is obtained as to the size and operational cycles of the equipment, this report will be updated

  11. Computer control and data acquisition system for the Mirror Fusion Test Facility Ion Cyclotron Resonant Heating System (ICRH)

    International Nuclear Information System (INIS)

    Cheshire, D.L.; Thomas, R.A.

    1985-01-01

    The Lawrence Livermore National Laboratory (LLNL) large Mirror Fusion Test Facility (MFTF-B) will employ an Ion Cyclotron Resonant Heating (ICRH) system for plasma startup. As the MFTF-B Industrial Participant, TRW has responsibility for the ICRH system, including development of the data acquisition and control system. During the MFTF-B Supervisory Control and Diagnostic System (SCDS). For subsystem development and checkout at TRW, and for verification and acceptance testing at LLNL, the system will be run from a stand-alone computer system designed to simulate the functions of SCDS. The ''SCDS Simulator'' was developed originally for the MFTF-B ECRH System; descriptions of the hardware and software are updated in this paper. The computer control and data acquisition functions implemented for ICRH are described, including development status, and test schedule at TRW and at LLNL. The application software is written for the SCDS Simulator, but it is programmed in PASCAL and designed to facilitate conversion for use on the SCDS computers

  12. Mirror research: status and prospects

    International Nuclear Information System (INIS)

    Baldwin, D.E.

    1983-01-01

    The tandem mirror program has evolved considerably in the last decade. Of significance is the viable reactor concept embodied in the MARS design. An aggressive experimental program culminating in the operation of MFTF-B in late 1986, will provide a firm basis for refining the MARS design as necessary for constructing a reactor prototype in the 1990s

  13. Mirror Fusion Test Facility: an intermediate device to a mirror fusion reactor

    International Nuclear Information System (INIS)

    Karpenko, V.N.

    1983-01-01

    The Mirror Fusion Test Facility (MFTF-B) now under construction at Lawrence Livermore National Laboratory represents more than an order-of-magnitude step from earlier magnetic-mirror experiments toward a future mirror fusion reactor. In fact, when the device begins operating in 1986, the Lawson criteria of ntau = 10 14 cm -3 .s will almost be achieved for D-T equivalent operation, thus signifying scientific breakeven. Major steps have been taken to develop MFTF-B technologies for tandem mirrors. Steady-state, high-field, superconducting magnets at reactor-revelant scales are used in the machine. The 30-s beam pulses, ECRH, and ICRH will also introduce steady-state technologies in those systems

  14. Long-pulse beamlines for the mirror fusion test facility

    International Nuclear Information System (INIS)

    Stone, R.R.; Goldner, A.I.; Poulsen, P.

    1984-01-01

    We have recently obtained test results indicating that a beam of pure full-energy deuterium particles can be delivered to the plasma targets in MFTF-B. We used a close-coupled separator magnet with the ion source to separate the impurities from the full-energy deuterium particles. Our completed studies show that the usual iron-core sweep magnet and shielding used in neutral beamlines can be eliminated and the gas flow out of the beamline decreased. This design also reduces beam losses. We will use smooth-bore OFHC tube arrays brazed to manifolds for the active heat transfer surfaces. Tests indicate that both burnout and life requirements are met by this design. In this paper, we present test results and discuss the MFTF-B long-pulse beamline configuration

  15. Review of current status of high flux heat transfer techniques. Volume I. Text + Appendix A

    International Nuclear Information System (INIS)

    Bauer, W.H.; Gordon, H.S.; Lackner, H.; Mettling, J.R.; Miller, J.E.

    1980-09-01

    The scope of this work comprised two tasks. The first was to review high heat flux technology with consideration given to heat transfer panel configuration, diagnostics techniques and coolant supply. The second task was to prepare a report describing the findings of the review, to recommend the technology offering the least uncertainty for scale-up for the MFTF-B requirement and to recommend any new or perceived requirements for R and D effort

  16. Tandem mirror reactor studies at Lawrence Livermore National Laboratory, FY 1980

    Energy Technology Data Exchange (ETDEWEB)

    Carlson, G.A.; Neef, W.S. Jr.

    1981-03-20

    The principles of tandem mirror operation with thermal barriers will be demonstrated in the upgrade of the Tandem Mirror Experiment (TMX-U) in 1981 and the tandem configuration of the Mirror Fusion Test Facility (MFTF-B) in 1984. Continued analysis and conceptual design over this period will evolve the optimal configuration and parameters for a power-producing reactor. In this article we describe the progress we have made in this reactor design study effort during 1980.

  17. Superconducting magnet development capability of the LLNL [Lawrence Livermore National Laboratory] High Field Test Facility

    International Nuclear Information System (INIS)

    Miller, J.R.; Shen, S.; Summers, L.T.

    1990-02-01

    This paper discusses the following topics: High-Field Test Facility Equipment at LLNL; FENIX Magnet Facility; High-Field Test Facility (HFTF) 2-m Solenoid; Cryogenic Mechanical Test Facility; Electro-Mechanical Conductor Test Apparatus; Electro-Mechanical Wire Test Apparatus; FENIX/HFTF Data System and Network Topology; Helium Gas Management System (HGMS); Airco Helium Liquefier/Refrigerator; CTI 2800 Helium Liquefier; and MFTF-B/ITER Magnet Test Facility

  18. Electrical energy and cost for the Mirror Fusion Test Facility

    International Nuclear Information System (INIS)

    Pence, G.A.

    1983-01-01

    An operational scenario has been developed for the Mirror Fusion Test Facility (MFTF-B) based on the System Requirements, our experience with existing systems, and discussions with the project engineers and designers who are responsible for the systems. This scenario was used to predict the amount of electrical energy needed for running the facility. A generic type listing is included for the equipment considered in each system

  19. Tandem mirror reactor studies at Lawrence Livermore National Laboratory, FY 1980

    International Nuclear Information System (INIS)

    Carlson, G.A.; Neef, W.S. Jr.

    1981-01-01

    The principles of tandem mirror operation with thermal barriers will be demonstrated in the upgrade of the Tandem Mirror Experiment (TMX-U) in 1981 and the tandem configuration of the Mirror Fusion Test Facility (MFTF-B) in 1984. Continued analysis and conceptual design over this period will evolve the optimal configuration and parameters for a power-producing reactor. In this article we describe the progress we have made in this reactor design study effort during 1980

  20. Operation of the cryogenic system for the Mirror Fusion Test Facility

    International Nuclear Information System (INIS)

    Chronis, W.C.; Slack, D.S.

    1987-01-01

    The cryogenic system for the Mirror Fusion Test Facility (MFTF) at Lawrence Livermore National Laboratory (LLNL) was designed to cool the entire MFTF-B system from ambient to operating temperature in less than 10 days. The system was successfully operated in the recent plant and capital equipment (PACE) acceptance tests, and results from these tests helped us correct problem areas and improve the system

  1. Review of current status of high flux heat transfer techniques. Volume I. Text + Appendix A

    Energy Technology Data Exchange (ETDEWEB)

    Bauer, W.H.; Gordon, H.S.; Lackner, H.; Mettling, J.R.; Miller, J.E.

    1980-09-01

    The scope of this work comprised two tasks. The first was to review high heat flux technology with consideration given to heat transfer panel configuration, diagnostics techniques and coolant supply. The second task was to prepare a report describing the findings of the review, to recommend the technology offering the least uncertainty for scale-up for the MFTF-B requirement and to recommend any new or perceived requirements for R and D effort.

  2. Fabrication of ion source components by electroforming

    International Nuclear Information System (INIS)

    Schechter, D.E.; Sluss, F.

    1983-01-01

    Several components of the Oak Ridge National Laboratory (ORNL)/Magnetic Fusion Test Facility (MFTF-B) ion source have been fabricated utilizing an electroforming process. A procedure has been developed for enclosing coolant passages in copper components by electrodepositing a thick (greater than or equal to 0.75-mm) layer of copper (electroforming) over the top of grooves machined into the copper component base. Details of the procedure to fabricate acceleration grids and other ion source components are presented

  3. MFTF-. cap alpha. + T progress report

    Energy Technology Data Exchange (ETDEWEB)

    Nelson, W.D. (ed.)

    1985-04-01

    Early in FY 1983, several upgrades of the Mirror Fusion Test Facility (MFTF-B) at Lawrence Livermore National Laboratory (LLNL) were proposed to the fusion community. The one most favorably received was designated MFTF-..cap alpha..+T. The engineering design of this device, guided by LLNL, has been a principal activity of the Fusion Engineering Design Center during FY 1983. This interim progress report represents a snapshot of the device design, which was begun in FY 1983 and will continue for several years. The report is organized as a complete design description. Because it is an interim report, some parts are incomplete; they will be supplied as the design study proceeds. As described in this report, MFTF-..cap alpha..+T uses existing facilities, many MFTF-B components, and a number of innovations to improve on the physics parameters of MFTF-B. It burns deuterium-tritium and has a central-cell Q of 2, a wall loading GAMMA/sub n/ of 2 MW/m/sup 2/ (with a central-cell insert module), and an availability of 10%. The machine is fully shielded, allows hands-on maintenance of components outside the vacuum vessel 24 h after shutdown, and has provisions for repair of all operating components.

  4. MFTF-α + T progress report

    International Nuclear Information System (INIS)

    Nelson, W.D.

    1985-04-01

    Early in FY 1983, several upgrades of the Mirror Fusion Test Facility (MFTF-B) at Lawrence Livermore National Laboratory (LLNL) were proposed to the fusion community. The one most favorably received was designated MFTF-α+T. The engineering design of this device, guided by LLNL, has been a principal activity of the Fusion Engineering Design Center during FY 1983. This interim progress report represents a snapshot of the device design, which was begun in FY 1983 and will continue for several years. The report is organized as a complete design description. Because it is an interim report, some parts are incomplete; they will be supplied as the design study proceeds. As described in this report, MFTF-α+T uses existing facilities, many MFTF-B components, and a number of innovations to improve on the physics parameters of MFTF-B. It burns deuterium-tritium and has a central-cell Q of 2, a wall loading GAMMA/sub n/ of 2 MW/m 2 (with a central-cell insert module), and an availability of 10%. The machine is fully shielded, allows hands-on maintenance of components outside the vacuum vessel 24 h after shutdown, and has provisions for repair of all operating components

  5. A stand alone computer system to aid the development of mirror fusion test facility RF heating systems

    International Nuclear Information System (INIS)

    Thomas, R.A.

    1983-01-01

    The Mirror Fusion Test Facility (MFTF-B) control system architecture requires the Supervisory Control and Diagnostic System (SCDS) to communicate with a LSI-11 Local Control Computer (LCC) that in turn communicates via a fiber optic link to CAMAC based control hardware located near the machine. In many cases, the control hardware is very complex and requires a sizable development effort prior to being integrated into the overall MFTF-B system. One such effort was the development of the Electron Cyclotron Resonance Heating (ECRH) system. It became clear that a stand alone computer system was needed to simulate the functions of SCDS. This paper describes the hardware and software necessary to implement the SCDS Simulation Computer (SSC). It consists of a Digital Equipment Corporation (DEC) LSI-11 computer and a Winchester/Floppy disk operating under the DEC RT-11 operating system. All application software for MFTF-B is programmed in PASCAL, which allowed us to adapt procedures originally written for SCDS to the SSC. This nearly identical software interface means that software written during the equipment development will be useful to the SCDS programmers in the integration phase

  6. Mirror advanced reactor study (MARS)

    International Nuclear Information System (INIS)

    Henning, C.D.; Logan, B.G.; Carlson, G.A.

    1982-01-01

    The agenda for the meeting is as follows: (1) basic Tandem Mirror approach, (2) baseline design, (3) transition and Yin-Yang coils, (4) drift pump physics, (5) drift pump coil, (6) Fokker-Planck analysis, (7) ignition-alpha pumping, (8) neutral beam status, (9) axicell layout, (10) axicell radiation levels, (11) ICRH system, (12) central cell cost optimization, (13) central cell coil design, (14) gridless direct converter, (15) direct converter directions, (16) end cell structure, (17) corrosion-double wall HX, (18) central cell maintenance, (19) radioactivity, (20) PbLi blanket design, and (21) MARS schedule

  7. US superconducting magnet data base assessment for INTOR

    International Nuclear Information System (INIS)

    Schultz, J.H.; Montgomery, D.B.

    1984-01-01

    Because of its size, performance requirements and exposure to neutron and gamma irradiation, the superconducting magnet system for INTOR would represent a significant advance in superconducting magnet technology. US programs such as LCP, MFTF-B and others provide a significant data base for the INTOR application. The assessment of the adequacy of the US data base for the INTOR magnets is largely generic, and applies to the superconducting magnet systems for other magnetic confinement fusion reactors. Assessments of the data base generated by other national magnet technology programs are being prepared by the other INTOR participants

  8. TMX tandem-mirror experiments and thermal-barrier theoretical studies

    International Nuclear Information System (INIS)

    Simonen, T.C.; Baldwin, D.E.; Allen, S.L.

    1982-01-01

    This paper describes recent analysis of energy confinement in the Tandem Mirror Experiment (TMX). TMX data also indicates that warm plasma limits the amplitude of the anisotropy driven Alfven ion cyclotron (AIC) mode. Theoretical calculations show strong AIC stabilization with off-normal beam injection as planned in TMX-U and MFTF-B. This paper reports results of theoretical analysis of hot electrons in thermal barriers including electron heating calculations by Monte Carlo and Fokker-Planck codes and analysis of hot electron MHD and microinstability. Initial results from the TMX-U experiment are presented which show the presence of sloshing ions

  9. Mirror Advanced Reactor Study (MARS) final report summary

    International Nuclear Information System (INIS)

    Henning, C.D.; Logan, B.G.; Carlson, G.A.

    1983-01-01

    The Mirror Advanced Reactor Study (MARS) has resulted in an overview of a first-generation tandem mirror reactor. The central cell fusion plasma is self-sustained by alpha heating (ignition), while electron-cyclotron resonance heating and negative ion beams maintain the electrostatic confining potentials in the end plugs. Plug injection power is reduced by the use of high-field choke coils and thermal barriers, concepts to be tested in the Tandem Mirror Experiment-Upgrade (TMX-U) and Mirror Fusion Test Facility (MFTF-B) at Lawrence Livermore National Laboratory

  10. Review of MFTF yin-yang magnet displacement and magnetic field measurements and calculations

    International Nuclear Information System (INIS)

    Hanson, C.L.; Myall, J.O.; Wohlwend, J.W.

    1983-01-01

    During the recent testing of the MFTF yin-yang magnet, measurements of coil position, structural case strain, and magnetic field were made to verify calculated values. Measurements to detect magnet movement were taken throughout cooldown and during the operation of the magnet. The magnetic field at the mirror points was measured by Hall-effect probes. The magnet position, structural case strain, and magnetic field measurements indicated a reasonably close correlation with calculated values. Information obtained from the yin-yang test has been very useful in setting realistic mechanical alignment values for the new MFTF-B magnet system

  11. Thermal performance of the MFTF magnets

    International Nuclear Information System (INIS)

    VanSant, J.H.

    1983-01-01

    A yin-yang pair of liquid-helium (LHe) cooled, superconducting magnets were tested last year at the Lawrence Livermore National Laboratory (LLNL) as part of a series of tests with the Mirror Fusion Test Facility (MFTF). These tests were performed to determine the success of engineering design used in major systems of the MFTF and to provide a technical base for rescoping from a single-mirror facility to the large tandem-mirror configuration (MFTF-B) now under construction. The magnets were cooled, operated at their design current and magnetic field, and warmed to atmospheric temperature. In this report, we describe their thermal behavior during these tests

  12. Review of MFTF yin-yang magnet displacement and magnetic field measurements and calculations

    International Nuclear Information System (INIS)

    Hanson, C.L.; Myall, J.O.; Wohlwend, J.W.

    1983-01-01

    During the recent testing of the MFTF yin-yang magnet, measurements of coil position, structural case strain, and magnetic field were made to verify calculated values. Measurements to detect magnet movement were taken throughout cooldown and during the operation of the magnet. The magnetic field at the mirror points was measured by Hall-effect probes. The magnet position, structural case strain, and magntic field measurements indicated a reasonably close correlation with calculated values. Information obtained from the yin-yang test has been very useful in setting realistic mechanical alignment values for the new MFTF-B magnet system

  13. Vacuum vessel for the tandem Mirror Fusion Test Facility

    International Nuclear Information System (INIS)

    Gerich, J.W.

    1986-01-01

    In 1980, the US Department of Energy gave the Lawrence Livermore National Laboratory approval to design and build a tandem Mirror Fusion Test Facility (MFTF-B) to support the goals of the National Mirror Program. We designed the MFTF-B vacuum vessel both to maintain the required ultrahigh vacuum environment and to structurally support the 42 superconducting magnets plus auxiliary internal and external equipment. During our design work, we made extensive use of both simple and complex computer models to arrive at a cost-effective final configuration. As part of this work, we conducted a unique dynamic analysis to study the interaction of the 32,000-tonne concrete-shielding vault with the 2850-tonne vacuum vessel system. To maintain a vacuum of 2 x 10 -8 torr during the physics experiments inside the vessel, we designed a vacuum pumping system of enormous capacity. The vacuum vessel (4200-m 3 internal volume) has been fabricated and erected, and acceptance tests have been completed at the Livermore site. The rest of the machine has been assembled, and individual systems have been successfully checked. On October 1, 1985, we began a series of integrated engineering tests to verify the operation of all components as a complete system

  14. Operation of cold-cathode gauges in high magnetic fields

    International Nuclear Information System (INIS)

    Thomas, S.R. Jr.; Goerz, D.A.; Pickles, W.L.

    1985-01-01

    The Mirror Fusion Test Facility (MFTF-B), under construction at LLNL, requires measurement of the neutral gas density in high magnetic fields near the plasma at several axial regions. This Background Gas Pressure (BGP) diagnostic will help us understand the role of background neutrals in particle and power balance, particularly in the maintenance of the cold halo plasma that shields the hot core plasma from the returning neutrals. It consists of several cold-cathode, magnetron-type gauges stripped of their permanent magnets, and utilizes the MFTF-B ambient B-field in strengths of 5 to 25 kG. Similar gauges have operated in TMX-U in B-fields up to 3 kG. To determine how well the gauges will perform, we assembled a test stand which operated magnetron gauges in an external, uniform magnetic field of up to 30 kG, over a pressure range of 1E-8 T to 1E-5 T, at several cathode voltages. This paper describes the test stand and presents the results of the tests

  15. Superconducting (radiation hardened) magnets for mirror fusion devices

    International Nuclear Information System (INIS)

    Henning, C.D.; Dalder, E.N.C.; Miller, J.R.; Perkins, J.R.

    1983-01-01

    Superconducting magnets for mirror fusion have evolved considerably since the Baseball II magnet in 1970. Recently, the Mirror Fusion Test Facility (MFTF-B) yin-yang has been tested to a full field of 7.7 T with radial dimensions representative of a full scale reactor. Now the emphasis has turned to the manufacture of very high field solenoids (choke coils) that are placed between the tandem mirror central cell and the yin-yang anchor-plug set. For MFTF-B the choke coil field reaches 12 T, while in future devices like the MFTF-Upgrade, Fusion Power Demonstration and Mirror Advanced Reactor Study (MARS) reactor the fields are doubled. Besides developing high fields, the magnets must be radiation hardened. Otherwise, thick neutron shields increase the magnet size to an unacceptable weight and cost. Neutron fluences in superconducting magnets must be increased by an order of magnitude or more. Insulators must withstand 10 10 to 10 11 rads, while magnet stability must be retained after the copper has been exposed to fluence above 10 19 neutrons/cm 2

  16. Octopole and hexapole end cells for tandem mirrors

    International Nuclear Information System (INIS)

    Devoto, R.S.

    1985-01-01

    To date, nearly all operating or planned tandem mirror experiments use quadrupole magnetic fields in the end cells for stabilization of magnetohydrodynamic (MHD) instabilities. A disadvantage with quadrupole fields is the considerable aximuthal asymmetry in the magnetic field. As a result, those center-cell ions which pass into the end cell can suffer a radial deflection and be lost by radial diffusion. The diffusion can be minimized by adding C-coils to the end cell to symmetrize the geodesic curvature in the end cell. Very small radial deflection can be obtained on each field line. Such a method is used in the design of the MFTF-B experiment and the MARS reactor. A disadvantage of this approach is the large number of coils required. In addition, since ions drift azimuthally as they reflect in the end cell, even perfect cancellation on individual field lines will, in general, not lead to zero radial diffusion. One way to form a more symmetric field in the end cells is to use multipoles higher than quadrupole. The use of an octopole end cell for a small tandem-mirror reactor was recently proposed/sup L/ and has been adopted for the miniMARS reactor study. In this paper the author discusses some feature of octopole, and to a lesser extent, hexapole end cells in both reactor and experimental (MFTF-B) applications

  17. User interface on networked workstations for MFTF plasma diagnostic instruments

    International Nuclear Information System (INIS)

    Renbarger, V.L.; Balch, T.R.

    1985-01-01

    A network of Sun-2/170 workstations is used to provide an interface to the MFTF-B Plasma Diagnostics System at Lawrence Livermore National Laboratory. The Plasma Diagnostics System (PDS) is responsible for control of MFTF-B plasma diagnostic instrumentation. An EtherNet Local Area Network links the workstations to a central multiprocessing system which furnishes data processing, data storage and control services for PDS. These workstations permit a physicist to command data acquisition, data processing, instrument control, and display of results. The interface is implemented as a metaphorical desktop, which helps the operator form a mental model of how the system works. As on a real desktop, functions are provided by sheets of paper (windows on a CRT screen) called worksheets. The worksheets may be invoked by pop-up menus and may be manipulated with a mouse. These worksheets are actually tasks that communicate with other tasks running in the central computer system. By making entries in the appropriate worksheet, a physicist may specify data acquisition or processing, control a diagnostic, or view a result

  18. MFTF sensor verification computer program

    International Nuclear Information System (INIS)

    Chow, H.K.

    1984-01-01

    The design, requirements document and implementation of the MFE Sensor Verification System were accomplished by the Measurement Engineering Section (MES), a group which provides instrumentation for the MFTF magnet diagnostics. The sensors, installed on and around the magnets and solenoids, housed in a vacuum chamber, will supply information about the temperature, strain, pressure, liquid helium level and magnet voltage to the facility operator for evaluation. As the sensors are installed, records must be maintained as to their initial resistance values. Also, as the work progresses, monthly checks will be made to insure continued sensor health. Finally, after the MFTF-B demonstration, yearly checks will be performed as well as checks of sensors as problem develops. The software to acquire and store the data was written by Harry Chow, Computations Department. The acquired data will be transferred to the MFE data base computer system

  19. Fusion-power demonstration

    International Nuclear Information System (INIS)

    Henning, C.D.; Logan, B.G.; Carlson, G.A.; Neef, W.S.; Moir, R.W.; Campbell, R.B.; Botwin, R.; Clarkson, I.R.; Carpenter, T.J.

    1983-01-01

    As a satellite to the MARS (Mirror Advanced Reactor Study) a smaller, near-term device has been scoped, called the FPD (Fusion Power Demonstration). Envisioned as the next logical step toward a power reactor, it would advance the mirror fusion program beyond MFTF-B and provide an intermediate step toward commercial fusion power. Breakeven net electric power capability would be the goal such that no net utility power would be required to sustain the operation. A phased implementation is envisioned, with a deuterium checkout first to verify the plasma systems before significant neutron activation has occurred. Major tritium-related facilities would be installed with the second phase to produce sufficient fusion power to supply the recirculating power to maintain the neutral beams, ECRH, magnets and other auxiliary equipment

  20. Seismic analysis of the MFTF facility

    International Nuclear Information System (INIS)

    Maslenikov, O.R.; Johnson, J.J.; Tiong, L.W.; Mraz, M.J.

    1985-01-01

    Seismic analyses were performed on the Mirror Fusion Test Facility (MFTF-B) located at the Lawrence Livermore National Laboratory, Livermore, CA. The three major structures studied were the vacuum vessel, the concrete shielding vault, and the steel frame enclosure building. The analyses performed on these structures ranged from fixed-base response spectrum analyses to soil-structure interaction analyses including the effects of structure-to-structure interaction and foundation flexibility. The results of these studies showed that the presence of the vault significantly affects the response of the vessel; that modeling the flexibility of the vault footing is important when studying forces near the base of the wall; and that the vault had very little effect on the building response. (orig.)

  1. Final design report, September 11, 1986

    International Nuclear Information System (INIS)

    1988-11-01

    The task is to design the quasi-optical microwave components for each of five different optical paths within the MFTF-B machine. Each path contains two reflectors. The function of the two reflectors in each path is to modify the output field of a waveguide to a desired pattern within the plasma. For all five beam paths, the waveguide output is assumed to be a TE 01 mode as decided at the July 18, design review. Each optical train consists of two reflectors. The first reflector is an off axis paraboloid which focuses the beam. The first reflector also contains the groove pattern of the twist polarizer. The second reflector receives the polarized beam from the first reflector. The function of the second reflector is to modify the phase of the polarized wavefront received from the first reflector. This modification shapes the wavefront profile in the plasma

  2. Economic potential of magnetic fusion energy

    International Nuclear Information System (INIS)

    Henning, C.D.

    1981-01-01

    Scientific feasibility of magnetic fusion is no longer seriously in doubt. Rapid advances have been made in both tokamak and mirror research, leading to a demonstration in the TFTR tokamak at Princeton in 1982 and the tandem mirror MFTF-B at Livermore in 1985. Accordingly, the basis is established for an aggressive engineering thrust to develop a reactor within this century. However, care must be taken to guide the fusion program towards an economically and environmentally viable goal. While the fusion fuels are essentially free, capital costs of reactors appear to be at least as large as current power plants. Accordingly, the price of electricity will not decline, and capital availability for reactor constructions will be important. Details of reactor cost projections are discussed and mechanisms suggested for fusion power implementation. Also discussed are some environmental and safety aspects of magnetic fusion

  3. Alternative power supply and dump resistor connections for similar, mutually coupled, superconducting coils

    International Nuclear Information System (INIS)

    Owen, E.W.; Shimer, W.; Wang, S.T.

    1983-01-01

    Alternative methods of connecting similar mutually coupled coils to their power supplies and dump resistors are investigated. The circuits are evaluated for both operating and fault conditions. The factors considered are the voltage to ground during a dump, short circuits, open circuits, quenches, and failure of the protection system to detect a quench. Of particular interest are the currents induced in coils that remain superconducting when one or more coils quench. The alternative connections include combined power supplies, individual dump resistors, combined resistors and series and parallel dump resistors. A new circuit that contains ''coupling'' resistors is proposed. The coupling resistors do not affect normal fast dumps but reduce the peak induced currents while also reducing the energy rating of the dump resistors. Another novel circuit, the series circuit with diodes, is discussed. The MFTF-B central-cell solenoids are used as an example

  4. Mechanical-engineering aspects of mirror-fusion technology

    International Nuclear Information System (INIS)

    Fisher, D.K.; Doggett, J.N.

    1982-01-01

    The mirror approach to magnetic fusion has evolved from the original simple mirror cell to today's mainline effort: the tandem-mirror machine with thermal barriers. Physics and engineering research is being conducted throughout the world, with major efforts in Japan, the USSR, and the US. At least one facility under construction (MFTF-B) will approach equivalent energy breakeven in physics performance. Significant mechanical engineering development is needed, however, before a demonstration reactor can be constructed. The principal areas crucial to mirror reactor development include large high-field superconducting magnets, high-speed continuous vacuum-pumping systems, long-pulse high-power neutral-beam and rf-plasma heating systems, and efficient high-voltage high-power direct converters. Other areas common to all fusion systems include tritium handling technology, first-wall materials development, and fusion blanket design

  5. Plans for the CIT [Compact Ignition Tokamak] instrumentation and control system

    International Nuclear Information System (INIS)

    Preckshot, G.G.

    1987-01-01

    Extensive experience with previous fusion experiments (TFTR, MFTF-B and others) is driving the design of the Instrumentation and Control System (I and C) for the Compact Ignition Tokamak (CIT) to be built at Princeton. The new design will reuse much equipment from TFTR and will be subdivided into six major parts: machine control, machine data acquisition, plasma diagnostic instrument control and instrument data acquisition, the database, shot sequencing and safety interlocks. In a major departure from previous fusion experiment control systems, the CIT machine control system will be a commercial process control system. Since the machine control system will be purchased as a completely functional product, we will be able to concentrate development manpower in plasma diagnostic instrument control, data acquisition, data processing and analysis, and database systems. We will discuss the issues driving the design, give a design overview and state the requirements upon any prospective commercial process control system

  6. MFTF-progress and promise

    International Nuclear Information System (INIS)

    Thomassen, K.I.

    1980-01-01

    The Mirror Fusion Test Facility (MFTF) has been in construction at Lawrence Livermore National Laboratory (LLNL) for 3 years, and most of the major subsystems are nearing completion. Recently, the scope of this project was expanded to meet new objectives, principally to reach plasma conditions corresponding to energy break-even. To fulfill this promise, the single-cell minimum-B mirror configuration will be replaced with a tandem mirror configuration (MFTF-B). The facility must accordingly be expanded to accomodate the new geometry. This paper briefly discusses the status of the major MFTF subsystems and describes how most of the technological objectives of MFTF will be demonstrated before we install the additional systems necessary to make the tandem. It also summarizes the major features of the expanded facility

  7. Safety and protection for large scale superconducting magnets. FY 1984 report

    International Nuclear Information System (INIS)

    Thome, R.J.; Pillsbury, R.D. Jr.; Minervini, J.V.

    1984-11-01

    The Fusion Program is moving rapidly into design and construction of systems using magnets with stored energies in the range of hundreds of megajoules to gigajoules. For example, the toroidal field coil system alone for TFCX would store about 4 GJ and the mirror system MFTF-B would store about 1.6 GJ. Safety and protection analyses of the magnet subsystems become progressively more important as the size and complexity of the installations increase. MIT has been carrying out a program for INEL oriented toward safety and protection in large scale superconducting magnet systems. The program involves collection and analysis of information on actual magnet failures, analyses of general problems associated with safety and protection, and performance of safety oriented experiments. This report summarizes work performed in FY 1984

  8. Alternative power supply and dump resistor connections for similar, mutally coupled, superconducting coils

    International Nuclear Information System (INIS)

    Owen, E.W.; Shimer, D.W.; Wang, S.T.

    1983-01-01

    Alternative methods of connecting similar mutually coupled coils to their power supplies and dump resistors are investigated. The circuits are evaluated for both operating and fault conditions. The factors considered are the voltage to ground during a dump, short circuits, open circuits, quenches, and failure of the protection system to detect a quench. Of particular interest are the currents induced in coils that remain superconducting when one or more coils quench. The alternative connections include combined power supplies, individual dump resistors, combined resistors and series and parallel dump resistors. A new circuit that contains coupling resistors is proposed. The coupling resistors do not affect normal fast dumps but reduce the peak induced currents while also reducing the energy rating of the dump resistors. Another novel circuit, the series circuit with diodes, is discussed. The MFTF-B central-cell solenoids are used as an example

  9. Stability and disturbance of large dc superconducting magnets

    International Nuclear Information System (INIS)

    Wang, S.T.

    1981-01-01

    This paper addresses the stability aspects of several successful dc superconducting magnets such as large bubble chamber magnets, and magnets for the Mirror Fusion Test Facility and MHD Research Facility. Specifically, it will cover Argonne National Laboratory 12-Foot Bubble Chamber magnets, the 15-foot Bubble Chamber magnets at Fermi National Laboratory, the MFTF-B Magnet System at Lawrence Livermore National Laboratory, the U-25B Bypass MHD Magnet, and the CFFF Superconducting MHD magnet built by Argonne National Laboratory. All of these magnets are cooled in pool-boiling mode. Magnet design is briefly reviewed. Discussed in detail are the adopted stability critera, analyses of stability and disturbance, stability simulation, and the final results of magnet performance and the observed coil disturbances

  10. Data triggered data processing at the Mirror Fusion Test Facility

    International Nuclear Information System (INIS)

    Jackson, R.J.; Balch, T.R.; Preckshot, G.G.

    1986-01-01

    A primary characteristic of most batch systems is that the input data files must exist before jobs are scheduled. On the Mirror Fusion Test Facility (MFTF-B) at Lawrence Livermore National Laboratory the authors schedule jobs to process experimental data to be collected during a five minute shot cycle. The data driven processing system emulates a coarsely granular data flow architecture. Processing jobs are scheduled before the experimental data is collected. Processing jobs ''fire'', or execute, as input data becomes available. Similar to UNIX ''pipes'', data produced by upstream processing nodes may be used as inputs by following nodes. Users, working on the networked SUN workstations, specify data processing templates which define processes and their data dependencies. Data specifications indicate the source of data; actual associations with specific data instantiations are made when the jobs are scheduled. The authors report here on details of diagnostic data processing and their experiences

  11. Magnetic systems for fusion devices

    International Nuclear Information System (INIS)

    Henning, C.D.

    1985-02-01

    Mirror experiments have led the way in applying superconductivity to fusion research because of unique requirements for high and steady magnetic fields. The first significant applications were Baseball II at LLNL and IMP at ORNL. More recently, the MFTF-B yin-yang coil was successfully tested and the entire tandem configuration is nearing completion. Tokamak magnets have also enjoyed recent success with the large coil project tests at ORNL, preceded by single coil tests in Japan and Germany. In the USSR, the T-7 Tokamak has been operational for many years and the T-15 Tokamak is under construction, with the TF coils nearing completion. Also the Tore Supra is being built in France

  12. Mirror Fusion Test Facility magnet system

    International Nuclear Information System (INIS)

    VanSant, J.H.; Kozman, T.A.; Bulmer, R.H.; Ng, D.S.

    1981-01-01

    In 1979, R.H. Bulmer of Lawrence Livermore National Laboratory (LLNL) discussed a proposed tandem-mirror magnet system for the Mirror Fusion Test Facility (MFTF) at the 8th symposium on Engineering Problems in Fusion Research. Since then, Congress has voted funds for expanding LLNL's MFTF to a tandem-mirror facility (designated MFTF-B). The new facility, scheduled for completion by 1985, will seek to achieve two goals: (1) Energy break-even capability (Q or the ratio of fusion energy to plasma heating energy = 1) of mirror fusion, (2) Engineering feasibility of reactor-scale machines. Briefly stated, 22 superconducting magnets contained in a 11-m-diam by 65-m-long vacuum vessel will confine a fusion plasma fueled by 80 axial streaming-plasma guns and over 40 radial neutral beams. We have already completed a preliminary design of this magnet system

  13. Design of tandem mirror reactors with thermal barriers

    International Nuclear Information System (INIS)

    Carlson, G.A.

    1980-01-01

    End-plug technologies for tandem mirror reactors include high-field superconducting magnets, neutral beam injectors, and gyrotrons for electron cyclotron resonant heating (ECRH). In addition to their normal use for sustenance of the end-plug plasmas, neutral beam injectors are used for ''pumping'' trapped ions from the thermal barrier regions by charge exchange. An extra function of the axially directed pump beams is the removal of thermalized alpha particles from the reactor. The principles of tandem mirror operation with thermal barriers will be demonstrated in the upgrade of the Tandem Mirror Experiment (TMX-U) in 1981 and the tandem configuration of the Mirror fusion Test Facility (MFTF-B) in 1984

  14. Tandem mirror magnet system for the mirror fusion test facility

    International Nuclear Information System (INIS)

    Bulmer, R.H.; Van Sant, J.H.

    1980-01-01

    The Tandem Mirror Fusion Test Facility (MFTF-B) will be a large magnetic fusion experimental facility containing 22 supercounducting magnets including solenoids and C-coils. State-of-the-art technology will be used extensively to complete this facility before 1985. Niobium titanium superconductor and stainless steel structural cases will be the principle materials of construction. Cooling will be pool boiling and thermosiphon flow of 4.5 K liquid helium. Combined weight of the magnets will be over 1500 tonnes and the stored energy will be over 1600 MJ. Magnetic field strength in some coils will be more than 8 T. Detail design of the magnet system will begin early 1981. Basic requirements and conceptual design are disclosed in this paper

  15. Fusion power demonstration

    International Nuclear Information System (INIS)

    Henning, C.D.; Logan, B.G.

    1983-01-01

    As a satellite to the MARS (Mirror Advanced Reactor Study) a smaller, near-term device has been scoped, called the FPD (Fusion Power Demonstration). Envisioned as the next logical step toward a power reactor, it would advance the mirror fusion program beyond MFTF-B and provide an intermediate step toward commercial fusion power. Breakeven net electric power capability would be the goal such that no net utility power would be required to sustain the operation. A phased implementation is envisioned, with a deuterium checkout first to verify the plasma systems before significant neutron activation has occurred. Major tritium-related facilities would be installed with the second phase to produce sufficient fusion power to supply the recirculating power to maintain the neutral beams, ECRH, magnets and other auxiliary equipment

  16. Tandem mirrors for neutron production

    International Nuclear Information System (INIS)

    Doggett, J.N.

    1983-01-01

    Two mirror machine concepts are being studied as early-time, low-cost, neutron-producing devices for testing and demonstrating reactor-relevant fusion technology. The first of these concepts is for a new, small, driven, steady-state, D-T reactor, called the Technology Demonstration Facility (TDF). The second concept is for upgrades to the MFTF-B machine that burn tritium and run for pulse lengths of some hours. Both devices operate in the Kelley mode in order to provide high-wall loadings of 14-MeV neutrons, thereby providing a valuable test bed for reactor-relevant hardware and subsystems. Either one of these devices could be running in the early 1990's with first wall fluxes between 1.4 and 2.0 MW m -2

  17. MFTF-α+T end plug magnet design

    International Nuclear Information System (INIS)

    Srivastava, V.C.; O'Toole, J.A.

    1983-01-01

    The conceptual design of the end-plug magnets for MFTF-α+T is described. MFTF-α+ T is a near-term upgrade of MFTF-B, which features new end plugs to improve performance. The Fusion Engineering Design Center has performed the engineering design of MFTF-α+T under the overall direction of Lawrence Livermore National Laboratory. Each end plug consists of two Yin-Yang pairs, each with approx.2.5:1 mirror ratio and approx.5-T peak field on axis; two transition coils; and a recircularizing solenoid. This paper describes the end-plug magnet system functional requirements and presents a conceptual design that meets them. The peak field at the windings of the end-plug coils is approx.6-T. These coils are designed using the NbTi MFTF-B conductor and cooled by a 4.2K liquid helium bath. All the end-plug magnets are designed to operate in the cryostable mode with adequate quench protection for safety. Shielding requirements are stated and a summary of heat loads is provided. Field and force calculations are discussed. The field on axis is shown to meet the functional requirements. Force resultants are reported in terms of winding running loads and resultant coil forces are also given. The magnet structural support is described. A trade study to determine the optimum end-cell coil internal nuclear shield thickness and the resulting coil size based on minimizing the end-cell life cycle cost is summarized

  18. Overview and direction in the tandem mirror program

    International Nuclear Information System (INIS)

    Thomassen, K.I.

    1983-04-01

    There are two main thrusts to the tandem mirror program at the present time. One is to gather the experimental data base to verify the axicell thermal-barrier concept and the other to improve the end plugs for tandems. With such improvements one might approach the ideal fusion reactor, a simple solenoid of modular elements whose ends are but a modest perturbation on the configuration from both a cost and technological viewpoint. Progress toward these two goals is discussed here, and the directions to be taken in the immediate future are described

  19. Engineering problems of tandem-mirror reactors

    International Nuclear Information System (INIS)

    Moir, R.W.; Barr, W.L.; Boghosian, B.M.

    1981-01-01

    We have completed a comparative evaluation of several end plug configurations for tandem mirror fusion reactors with thermal barriers. The axi-cell configuration has been selected for further study and will be the basis for a detailed conceptual design study to be carried out over the next two years. The axi-cell end plug has a simple mirror cell produced by two circular coils followed by a transition coil and a yin-yang pair, which provides for MHD stability. This paper discusses some of the many engineering problems facing the designer. We estimated the direct cost to be 2$/W/sub e/. Assuming total (direct and indirect) costs to be twice this number, we need to reduce total costs by factors between 1.7 and 2.3 to compete with future LWRs levelized cost of electricity. These reductions may be possible by designing magnets producing over 20T made possible by use of combinations of superconducting and normal conducting coils as well as improvements in performance and cost of neutral beam and microwave power systems. Scientific and technological understanding and innovation are needed in the area of thermal barrier pumping - a process by which unwanted particles are removed (pumped) from certain regions of velocity and real space in the end plug. Removal of exhaust fuel ions, fusion ash and impurities by action of a halo plasma and plasma dump in the mirror end region is another challenging engineering problem discussed in this paper

  20. Proposed tandem mirror research program for FY87 presented to the MFAC subcommittee on mirror research, July 8-9, 1986

    International Nuclear Information System (INIS)

    Baldwin, D.E.; Correll, D.L.; Fowler, T.K.; Grubb, D.P.; Hershkowitz, N.; Porter, G.D.; Post, R.S.; Simonen, T.C.

    1986-01-01

    We have reexamined the goal of approx.10 13 cm -3 central-cell density with end-plugging and reconfirmed its importance as a test of thermal barrier end-plugging performance in either Tara or TMX-U. We conclude that, when all factors are considered including the impact on other programs interlinked with LLNL in the present OFE budget, the lowest cost approach to have a fair chance to meet this goal is to extend Tara operation for the full FY87. Continuation of TMX-U operation in FY87, in addition to the full year of Tara operation, would greatly improve the chance of success. Continuation of the mirror program into FY88 and beyond would be based on an experimental program in TMX-U and Tara at a minimum budget level of $25M/y, with restart of MFTF-B requiring an increase in the national fusion budget. The experimental program to be investigated by TMX-U and Tara would include improvement in the mgnetic geometry (stability, beta limits, and transport), continued plug studies (longer pulse length, impurities, drift pumping, and ECH efficiency), and transport studies (chi/sub e/, fueling, and halo formation)

  1. Development of nitronic 50 fusion welding techniques for 4 K service

    International Nuclear Information System (INIS)

    Dalder, E.N.C.; Juhas, M.C.

    1981-01-01

    The Mirror Fusion Test Facility (MFTF-B) is a large magnetic fusion energy experiment in the tandem mirror configuration. The requirement that each pair of Yin-Yang magnets, one pair at each end of the experiment, not undergo excessive lateral motion during seismic events was found to require excessively thick (> 12.7 mm) walled tubing in the support-struts, which accelerated the flow of heat inward to the 4 K magnet case from the nearby 300 K wall of the rector vessel, when any of the Cr-Ni austenite stainless steels, such as Type 304 with a 300 K yield-strength (sigma y) of 307 mpa (min.) was considered. Since the cold end of the lateral restraining strut was to be at or near 4 K, the additional constraints of good austenite stability and resistance to brittle fracture at 4 K existed. After consideration of these constraints against available information on Cr-Ni and Cr-Mn-Ni-N 2 austenitic stainless steels, grade XM-19 (Fe-22 Cr-12 Ni-5 Mn-.04 C-.02 N 2 was chosen. The mechanical properties of these welds were studied

  2. Test facility for the evaluation of microwave transmission components

    International Nuclear Information System (INIS)

    Fong, C.G.; Poole, B.R.

    1985-01-01

    A Low Power Test Facility (LPTF) was developed to evaluate the performance of Electron Cyclotron Resonance Heating (ECRH) microwave transmission components for the Mirror Fusion Test Facility (MFTF-B). The facility generates 26 to 60 GHz in modes of TE 01 , TE 02 , or TE 03 launched at power levels of 1/2 milliwatt. The propagation of the rf as it radiates from either transmitting or secondary reflecting microwave transmission components is recorded by a discriminating crystal detector mechanically manipulated at constant radius in spherical coordinates. The facility is used to test, calibrate, and verify the design of overmoded, circular waveguide components, quasi-optical reflecting elements before high power use. The test facility consists of microwave sources and metering components, such as VSWR, power and frequency meters, a rectangular TE 10 to circular TE 01 mode transducer, mode filter, circular TE 01 to 2.5 in. diameter overmoded waveguide with mode converters for combination of TE 01 to TE 03 modes. This assembly then connects to a circular waveguide launcher or the waveguide component under test

  3. Investigation of auxiliary heating in tandem mirrors and tokamaks and barrier cell pumping. Annual progress report, October 1, 1980 to December 31, 1981

    International Nuclear Information System (INIS)

    Emmert, G.A.; Scharer, J.

    1981-06-01

    The research has focussed on physics questions concerned with ECRH heating in tandem mirror plugs, pumping of tandem mirror thermal barriers by drift orbits, ICRH heating in tokamaks, and bundle divertors. We have concluded that drift-orbit pumping of thermal barriers is not feasible because the azimuthal E Vector X B Vector drift limits the excursion of trapped ions from a flux surface. We have developed a three-dimensional weakly relativistic (T/sub e/ less than or equal to 50 keV) ray tracing and absorption code for electron cyclotron heating in tandem mirror plugs and barriers. Cases run for TMX, MFTF-B and reactors at T/sub e/ > 10 keV show that strong absorption per pass is present and a careful choice of wave frequency and launch angle is required to ensure wave penetration and absorption in the plasma core. In the area of ion cyclotron frequency range heating in tokamaks, a three-dimensional hot plasma ray tracing theory and code has been developed to handle rays launched from any poloidal angle in the tokamak cross section. Wave heating in the central strong absorption zones is currently being investigated using a full wave solution for the various heating regimes

  4. Development of neutral beams for fusion plasma heating

    International Nuclear Information System (INIS)

    Haselton, H.H.; Pyle, R.V.

    1980-01-01

    A state-of-the-art account of neutral beam technology at the LBL/LLNL and ORNL facilities is given with emphasis on positive-ion-based systems. The advances made in the last few years are elaborated and problem areas are identified. The ORNL program has successfully completed the neutral injection systems for PLT, ISX-B, and most recently, PDX and the ISX-B upgrade. All of these are high current (60 to 100 A), medium energy (40 to 50 keV) systems. This program is also engaged in the development of a reactor-grade advanced positive ion system (150 to 200 kV/100 A/5 to 10 s) and a multimegawatt, long pulse (30 s) heating system for ISX-C. In a joint program, LBL and LLNL are developing and testing neutral beam injection systems based on the acceleration of positive ions for application in the 80- to 160-keV range on MFTF-B, D-III, TFTR/TFM, ETF, MNS, etc. A conceptual design of a 160-keV injection system for the German ZEPHYR project is in progress at LBL/LLNL and independently at ORNL. The laboratories are also engaged in the development of negative-ion-based systems for future applications at higher energies

  5. Annual progress report on an investigation of auxiliary heating in tandem mirrors and tokamaks for the period January 1, 1982-December 31, 1982

    International Nuclear Information System (INIS)

    Scharer, J.E.

    1982-07-01

    The research has focused on physics questions concerned with ECRF heating in tandem mirror plugs and barriers and ICRF coupling and heating in tokamaks. We have utilized a three-dimensional weakly relativistic (T/sub e/ less than or equal to 50 keV) ray tracing and absorption code we have developed for electron cyclotron heating in tandem mirror plugs and barriers. Cases run for TMX, MFTF-B and reactors at T/sub e/ > 10 keV show that strong absorption per pass is present and a careful choice of wave mode, frequency and launch angle is required to ensure wave penetration and absorption in the plasma core. At elevated electron temperatures (T/sub e/ > 10 keV), ordinary mode launch at theta approx. = 70 0 provides good single pass absorption without the edge absorption problems associated with the extraordinary mode. We have also developed an ICRF 1-D slab model to investigate coupling and heating in tokamak plasmas

  6. Fusion technology development: role of fusion facility upgrades and fission test reactors

    International Nuclear Information System (INIS)

    Hsu, P.Y.; Deis, G.A.; Longhurst, G.R.; Miller, L.G.; Schmunk, R.E.

    1983-01-01

    The near term national fusion program is unlikely to follow the aggressive logic of the Fusion Engineering Act of 1980. Faced with level budgets, a large, new fusion facility with an engineering thrust is unlikely in the near future. Within the fusion community the idea of upgrading the existing machines (TFTR, MFTF-B) is being considered to partially mitigate the lack of a design data base to ready the nation to launch an aggressive, mission-oriented fusion program with the goal of power production. This paper examines the cost/benefit issues of using fusion upgrades to develop the technology data base which will be required to support the design and construction of the next generation of fusion machines. The extent of usefulness of the nation's fission test reactors will be examined vis-a-vis the mission of the fusion upgrades. The authors show that while fission neutrons will provide a useful test environment in terms of bulk heating and tritium breeding on a submodule scale, they can play only a supporting role in designing the integrated whole modules and systems to be used in a nuclear fusion machine

  7. Development and application of specially-focused ultrasonic transducers to location and sizing of defects in 75 mm- to 127 mm-thick austenitic stainless steel weld metals

    Energy Technology Data Exchange (ETDEWEB)

    Dalder, E.N.C.; Benson, S.; McKinley, B.J.; Carodiskey, T.

    1992-08-01

    Special UT transducer parts, capable of focusing incident signals within a 25 mm {times} 25 mm {times} 25 mm volume in an austenitic stainless weld metal at depths that varied from 25 mm to 127 mm, were developed and demonstrated to be capable of detecting a defect with cross section equivalent to that of a 4.76 mm-dia flat-bottom hole. Defect length sizing could be accomplished to {plus_minus}50% for 100% of the time and to {plus_minus}25% on selected defect types as follows: porosity groups, 100%; cracks, 67%; combined slag and porosity, 60%; and linear slag indications, 59%. Extensive linear elastic-fracture-mechanics analyses were performed to establish allowable defect sizes at functions of stress, based on a cyclic-life criterion of 10{sup 3} full power cycles of the MFTF-B magnet system. These defect sizes were used to determine which UT indicating were to be removed and repaired and which were to be retained and their recorded sizes and locations.

  8. Fusion blanket testing in MFTF-α + T

    International Nuclear Information System (INIS)

    Kleefeldt, K.

    1985-01-01

    The Mirror Fusion Test Facility-α + T (MFTF-α + T) is an upgraded version of the current MFTF-B test facility at Lawrence Livermore National Laboratory, and is designed for near-term fusion-technology-integrated tests at a neutron flux of 2 MW/m 2 . Currently, the fusion community is screening blanket and related issues to determine which ones can be addressed using MFTF-α + T. In this work, the minimum testing needs to address these issues are identified for the liquid-metal-cooled blanket and the solid-breeder blanket. Based on the testing needs and on the MFTF-α + T capability, a test plan is proposed for three options; each option covers a six to seven year testing phase. The options reflect the unresolved question of whether to place the research and development (R and D) emphasis on liquid-metal or solid-breeder blankets. In each case, most of the issues discussed can be addressed to a reasonable extent in MFTF-α+T

  9. 3D equilibrium codes for mirror machines

    International Nuclear Information System (INIS)

    Kaiser, T.B.

    1983-01-01

    The codes developed for cumputing three-dimensional guiding center equilibria for quadrupole tandem mirrors are discussed. TEBASCO (Tandem equilibrium and ballooning stability code) is a code developed at LLNL that uses a further expansion of the paraxial equilibrium equation in powers of β (plasma pressure/magnetic pressure). It has been used to guide the design of the TMX-U and MFTF-B experiments at Livermore. Its principal weakness is its perturbative nature, which renders its validity for high-β calculation open to question. In order to compute high-β equilibria, the reduced MHD technique that has been proven useful for determining toroidal equilibria was adapted to the tandem mirror geometry. In this approach, the paraxial expansion of the MHD equations yields a set of coupled nonlinear equations of motion valid for arbitrary β, that are solved as an initial-value problem. Two particular formulations have been implemented in computer codes developed at NYU/Kyoto U and LLNL. They differ primarily in the type of grid, the location of the lateral boundary and the damping techniques employed, and in the method of calculating pressure-balance equilibrium. Discussions on these codes are presented in this paper. (Kato, T.)

  10. Mechanical configuration for a superconducting ignition tokamak (TIBER)

    International Nuclear Information System (INIS)

    Neef, W.S. Jr.; Johnston, B.M.

    1985-10-01

    The Lawrence Livermore National Laboratory is evaluating the engineering feasibility and economics of a superconducting ignition tokamak. Two major operational requirements had to be satisfied: (1) the conductive heat leak to the refrigerated structure had to be minimized, and (2) assembly and maintenance of the entire experiment had to be possible with remotely operated tools. The middle poloidal ''push coil'' must have many annular disks to transfer the TF-coil inward force to the post without crushing superconductor. The toppling moment on the TF-coil vertical legs is huge. A method of keying together the TF-coil cases has been developed. This forms an integrated structure that resists torque. The joining technique permits linear motion for simple assembly/disassembly. the topping moment on the outer vertical legs of the TF coils is very large. To react that moment and avoid great coil-case bulk, we have developed a method that allows the PF coil support structure to assist the TF case structure. Finite element techniques were used to determine the ability of the coal case and conductor to react the magnetic loads. The entire cold-coil structure is mounted on a circular plate that is suspended by several large tension rods, similar to the MFTF-B yin-yang support rods. The vacuum vessel is all at room temperature and is configured like a bell jar with sixteen side doors, one for each shield module

  11. Fusion technology development: role of fusion facility upgrades and fission test reactors

    International Nuclear Information System (INIS)

    Hsu, P.Y.; Deis, G.A.; Miller, L.G.; Longhurst, G.R.; Schmunk, R.E.

    1983-01-01

    The near term national fusion program is unlikely to follow the aggressive logic of the Fusion Engineering Act of 1980. Faced with level budgets, a large, new fusion facility with an engineering thrust is unlikely in the near future. Within the fusion community the idea of upgrading the existing machines (TFTR, MFTF-B) is being considered to partially mitigate the lack of a design data base to ready the nation to launch an aggressive, mission-oriented fusion program with the goal of power production. This paper examines the cost/benefit issues of using fusion upgrades to develop the technology data base which will be required to support the design and construction of the next generation of fusion machines. The extent of usefulness of the nation's fission test reactors will be examined vis-a-vis the mission of the fusion upgrades. We will show that while fission neutrons will provide a useful test environment in terms of bulk heating and tritium breeding on a submodule scale, they can play only a supporting role in designing the integrated whole modules and systems to be used in a nuclear fusion machine

  12. Development of neutral beams for fusion plasma heating

    Energy Technology Data Exchange (ETDEWEB)

    Haselton, H.H.; Pyle, R.V.

    1980-01-01

    A state-of-the-art account of neutral beam technology at the LBL/LLNL and ORNL facilities is given with emphasis on positive-ion-based systems. The advances made in the last few years are elaborated and problem areas are identified. The ORNL program has successfully completed the neutral injection systems for PLT, ISX-B, and most recently, PDX and the ISX-B upgrade. All of these are high current (60 to 100 A), medium energy (40 to 50 keV) systems. This program is also engaged in the development of a reactor-grade advanced positive ion system (150 to 200 kV/100 A/5 to 10 s) and a multimegawatt, long pulse (30 s) heating system for ISX-C. In a joint program, LBL and LLNL are developing and testing neutral beam injection systems based on the acceleration of positive ions for application in the 80- to 160-keV range on MFTF-B, D-III, TFTR/TFM, ETF, MNS, etc. A conceptual design of a 160-keV injection system for the German ZEPHYR project is in progress at LBL/LLNL and independently at ORNL. The laboratories are also engaged in the development of negative-ion-based systems for future applications at higher energies.

  13. Some introductory notes on the problem of nuclear energy by controlled fusion reactions

    International Nuclear Information System (INIS)

    Pedretti, E.

    1988-01-01

    Written for scientists and technologist interested in, but unfamiliar with nuclear energy by controlled fusion reactions, this ''sui generis'' review paper attempts to provide the reader, as shortly as possible, with a general idea of the main issues at stake in nuclear fusion research. With the purpose of keeping this paper within a reasonable length, the various subjects are only outlined in their essence, basic features, underlying principles, etc., without entering into details, which are left to the quoted literature. Due to the particular readership of this journal, vacuum problems and/or aspects of fusion research anyhow related with vacuum science and technology are evidentiated. After reviewing fusion reactions' cross sections, fusion by accelerators and muon catalyzed fusion are described, followed by mention of Lawson's criteria and of plasma confinement features. Then, inertial confinement fusion is dealt with, also including one example of laser system (Nova), one of accelerator facility (PBFA-II) and some guesses on the classified Centurion-Halite program. Magnetic confinement fusion research is also reviewed, in particulary reporting one example of linear machine (MFTF-B), two examples of toroidal machines other than Tokamak (ATF and Eta-Beta-II) and various examples of Tokamaks, including PBX and PBX-M; TFTR, JET, JT-60, T-15 and Tore-Supra (large machines); Alcator A, FT, Alcator C/MTX, Alcator C-Mod and T-14 (compact high field machines). Tokamaks under design for ignition experiments (Ignitor, CIT, Ignitex and NET) are also illustrated. Thermal conversion of fusion power and direct generation of electricity are mentioned; conceptual design of fusion power plants are considered and illustrated by four examples (STARFIRE, WILDCAT, MARS and CASCADE). The D 3 He fuel cycle is discussed as an alternative more acceptable than Deuterium-Tritium, and thw Candor proposal is reported. After recalling past experience of the fission power development, some

  14. Superconducting wire for Lawrence Livermore National Laboratory in U.S.A

    International Nuclear Information System (INIS)

    Inoue, Itaru; Ikeda, Masaru; Tanaka, Yasuzo; Meguro, Shinichiro

    1985-01-01

    In Lawrence Livermore National Laboratory in USA, the development of a mirror type nuclear fusion reactor is carried out, and for plasma confinement, superconducting magnets are used. For the axicell coil generating a 12 T magnetic field in one of these magnets, Nb 3 Sn superconducting wires are to be used, and after the completion, it will be the largest magnet in the world as high magnetic field superconducting magnets. Furukawa Electric Co., Ltd. has completed the delivery of Nb 3 Sn superconducting wires used for this purpose. Since the Nb 3 Sn superconducting wires are very brittle, attention was paid to the manufacture to satisfy the required characteristics, and it was able to obtain the good reputation that the product was highly homogeneous as the superconducting wires of this type. In this paper, the design, manufacture and various characteristics of these superconducting wires are reported. The Nb 3 Sn superconducting wires were manufactured on industrial scale of 8 tons. The features of these Nb 3 Sn wires are the compound structure with semi-hard copper for low temperature stability and strengthening. (Kako, I.)

  15. Physics of mirror systems

    International Nuclear Information System (INIS)

    Post, R.F.

    1982-05-01

    In recent years the emphasis in research on the magnetic mirror approach to fusion has been shifted to address what are essentially economically-motivated issues. The introduction of the Tandem Mirror idea solved in principal the problem of low Q (low fusion power gain) of mirror-based fusion systems. In order to optimize the tandem mirror idea from an economic standpoint, some important improvements have been suggested. These improvements include the thermal barrier idea of Baldwin and Logan and the axicell concept of Kesner. These new modifications introduce some special physics considerations. Among these are (1) The MHD stability properties of high energy electron components in the end cells; (2) The optimization of end-cell magnetic field configurations with the objective of minimizing equilibrium parallel currents; (3) The suppression of microstabilities by use of sloshing ion distributions. Following a brief outline of tandem mirror concepts, the above three topics are discussed, with illustrative examples taken from earlier work or from recent design studies

  16. B-Cell waste classification sampling and analysis plan

    International Nuclear Information System (INIS)

    HOBART, R.L.

    1999-01-01

    This report documents the methods used to collect and analyze samples to obtain data necessary to verify and/or determine the radionuclide content of the 324 Facility B-Cell decontamination and decommissioning waste stream

  17. 40 CFR 264.52 - Content of contingency plan.

    Science.gov (United States)

    2010-07-01

    ... to air, soil, or surface water at the facility. (b) If the owner or operator has already prepared a... control equipment, communications and alarm systems (internal and external), and decontamination equipment...

  18. 40 CFR 265.52 - Content of contingency plan.

    Science.gov (United States)

    2010-07-01

    ... hazardous waste constituents to air, soil, or surface water at the facility. (b) If the owner or operator... alarm systems (internal and external), and decontamination equipment), where this equipment is required...

  19. 5 CFR 7001.102 - Restrictions on outside employment and business activities.

    Science.gov (United States)

    2010-01-01

    ... postal facility. (b) Prior approval for outside employment and business activities—(1) Requirement for..., but is not limited to, engagement as principal, proprietor, general partner, holder of a franchise...

  20. B-cell waste classification sampling plan

    International Nuclear Information System (INIS)

    HOBART, R.L.

    1999-01-01

    This report documents the methods used to collect samples and analyze data necessary to verify and/or determine the radionuclide content of the 324 Facility B-Cell decontamination and decommissioning waste stream

  1. 50 CFR 23.34 - What kinds of records may I use to show the origin of a specimen when I apply for a U.S. CITES...

    Science.gov (United States)

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    ... for wildlife by sex, size, band number, or other mark, or for plants by size or other identifying... facility: (A) Number of wildlife (by sex and age- or size-class) or plants at the facility. (B) How long... seller. (G) Marking system, if applicable. (H) Photographs or video of facility, including for wildlife...

  2. 9 CFR 3.78 - 0utdoor housing facilities.

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    ... AGRICULTURE ANIMAL WELFARE STANDARDS Specifications for the Humane Handling, Care, Treatment, and... facility at that time of year without stress or discomfort, may be kept in outdoor facilities. (b) Shelter...) The housing facility is surrounded by a natural barrier that restricts the nonhuman primates to the...

  3. Influence of Wallow on Some Hematological Parameters and Serum ...

    African Journals Online (AJOL)

    A study was conducted to determine the influence of wallow on some hematological and serum enzymes of growing pigs. Six pre-pubertal pigs of average age 2months were randomly assigned to two treatment groups, comprising of Wallow (A) and Non-Wallow facilities (B) in a Completely Randomized Design(CRD).

  4. 40 CFR 240.202-2 - Recommended procedures: Design.

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    2010-07-01

    ... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Recommended procedures: Design. 240... § 240.202-2 Recommended procedures: Design. (a) Whenever possible, thermal processing facilities should be located in areas zoned for industrial use and having adequate utilities to serve the facility. (b...

  5. 9 CFR 3.18 - Terminal facilities.

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    ... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Terminal facilities. 3.18 Section 3.18... Cats 1 Transportation Standards § 3.18 Terminal facilities. (a) Placement. Any person subject to the... inanimate cargo in animal holding areas of terminal facilities. (b) Cleaning, sanitization, and pest control...

  6. 9 CFR 3.27 - Facilities, outdoor.

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    ... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Facilities, outdoor. 3.27 Section 3.27... Pigs and Hamsters Facilities and Operating Standards § 3.27 Facilities, outdoor. (a) Hamsters shall not be housed in outdoor facilities. (b) Guinea pigs shall not be housed in outdoor facilities unless...

  7. 32 CFR 154.17 - Special access programs.

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    .... (4) Presidential mess attendants and medical personnel. (5) Other individuals filling administrative... units, and military bands who perform at Presidential functions and facilities. (B) Employees of... PRP, reinvestigation is not required so long as the individual remains in the PRP. (D) A medical...

  8. 18 CFR 250.6 - Form of application to be filed by distributor under section 7(a), seeking gas service of not...

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    ... extension or improvement of existing facilities? (b) Estimate of maximum day requirements for residential... psia), and how the estimates were derived; (c) Estimate of annual requirements for residential... psia), and how the estimates were derived. 7. Do you have or do you need a franchise to render the...

  9. 32 CFR 260.4 - Policy.

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    ... blind vending facilities. (d) Specified income from vending machines operated on DoD-controlled property... Department of Defense (Continued) OFFICE OF THE SECRETARY OF DEFENSE (CONTINUED) MISCELLANEOUS VENDING... shall be given priority in the establishment and operation of vending facilities. (b) The blind shall be...

  10. 9 CFR 82.8 - Interstate movement of eggs, other than hatching eggs, from a quarantined area.

    Science.gov (United States)

    2010-01-01

    ... arrival of the eggs at the facility. (b) Any flats or cases intended for reuse after being used to move... part 71 of this chapter before being moved to a premises where birds or poultry are kept. [61 FR 56883... be moved interstate from a quarantined area only if: (1) The eggs are accompanied by a permit...

  11. 15 CFR 700.51 - Requests for priority rating authority.

    Science.gov (United States)

    2010-01-01

    ...; and (3) Expansion, rebuilding or replacing plant facilities. (b) Rating authority for production or... may be leased only from a person engaged in the business of leasing such equipment or from a person... sponsorship of the request from the appropriate Delegate Agency. The person shall also assume any business...

  12. 33 CFR 127.1111 - Communication systems.

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Communication systems. 127.1111... systems. (a) The marine transfer area for LHG must possess a communication system that enables continuous... in charge of transfer for the facility. (b) The communication system required by paragraph (a) of...

  13. Requirements of on-site facilities

    International Nuclear Information System (INIS)

    Burchardt, H.

    1977-01-01

    1) Requirements of on-site facilities: a) brief description of supplying the site with electricity and water; communication facilities, b) necessary facilities for containment and pipeline installation, c) necessary facilities for storage, safety, accommodation of personnel, housing; workshops; 2) Site management: a) Organisation schedules for 'turn-key-jobs' and 'single commission', b) Duties of the supervisory staff. (orig.) [de

  14. 9 CFR 93.308 - Quarantine requirements.

    Science.gov (United States)

    2010-01-01

    ... Arabia, the Yemen Arab Republic, and all the regions on the continent of Africa except Morocco. (3) To... arrange for a supply of water adequate to clean and disinfect the facility. (B) All feed and bedding must... quality control standards. Following completion of the quarantine period and the release of the horses...

  15. 48 CFR 927.303 - Contract clauses.

    Science.gov (United States)

    2010-10-01

    ... is a domestic small business or nonprofit organization as defined at (FAR) 48 CFR 27.301, except... contracts for the management and operation of DOE laboratories and production facilities. (b) DOE shall not... its rights in an identified invention pursuant to 10 CFR part 784, contracting officers shall consult...

  16. 75 FR 58315 - Hazardous Waste Management System; Identification and Listing of Hazardous Waste; Direct Final...

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    2010-09-24

    ... landfill. The scrubber water blowdown will be managed in the waste water treatment plant (WWTP). The sludge... waste streams included in the petition were: the RKI fly ash, RKI bottom ash and RKI scrubber water... water blowdown waste resulting from the operations of the rotary kiln incinerator at its facility. B...

  17. 14 CFR 1213.101 - Applicability.

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    ... Aeronautics and Space NATIONAL AERONAUTICS AND SPACE ADMINISTRATION RELEASE OF INFORMATION TO NEWS AND INFORMATION MEDIA § 1213.101 Applicability. (a) This policy applies to NASA Headquarters, NASA Centers, and Component Facilities. (b) In the event of any conflict between this policy and any other NASA policy...

  18. Federal Research and Development Funding: FY2017

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    2017-01-27

    International Center (FIC) 70 70 National Library of Medicine (NLM) 396 396 Office of Director (OD) 1,571 1,716 Buildings & Facilities (B&F...operates the National Agricultural Library , one of the department’s primary information repositories for food, agriculture, and natural resource... Multicultural Scholars Program, Women and Minorities in STEM Program, Agriculture in the Classroom, and Secondary/Postsecondary Challenge Grants. For

  19. Seasonal changes in circulating gonadal steroid levels and physiological evidence for the presence of intrinsic circannual reproductive cycles in captive finless porpoises Neophocaena asiaeorientalis from the western Inland Sea, Japan.

    Science.gov (United States)

    Funasaka, Noriko; Yoshioka, Motoi; Ishibashi, Toshiaki; Tatsukawa, Toshiyuki; Shindo, Hideaki; Takada, Koji; Nakamura, Masayuki; Iwata, Tomohiko; Fujimaru, Kaoru; Tanaka, Taira

    2018-04-13

    We monitored annual fluctuations of gonadal steroid levels in three sexually mature captive finless porpoises (Neophocaena asiaeorientalis; two males and one female) from two different facilities over 56-91 months. Two animals (one male and one female) were held in an indoor tank with a sunroof (facility A) and the other male was held in an indoor tank without a sunroof (facility B). Water temperatures in both facilities reflected seasonal changes during the study period with a minor difference in the fluctuation pattern. Testosterone levels of the male in facility A were higher from spring to summer every year and exhibited a 12-month cycle. The female showed estrus cycles in 1-month intervals from summer to winter, excluding 2 anestrus years. In contrast, the period of higher testosterone levels of the male in facility B gradually initiated earlier over the years under a constant photoperiod (11.5L:12.5D) and exhibited a 9-month cycle during the first 52 months. After changing the light conditions to a natural photoperiod, its testosterone levels were high from early spring to summer for 3 consecutive years and exhibited a 12-month cycle. Our results showed that under a constant artificial photoperiod, the male in facility B failed to recognize the seasonal changes of a natural external environment, resulting in a 9-month, free-running hormone cycle.

  20. Promotional study for joint implementation program. Energy conservation and efficiency improvement for district heating system in Tashkent, Uzbekistan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    For the purpose of reducing greenhouse effect gas emissions, a study was carried out for repair/improvement of the district heating system in Tashkent City, the Republic of Uzbekistan. In the project, the following were studied: heightening of electrical insulation of the total pipeline, improvement in efficient utilization of heat energy in the thermal plant. As to the existing pipeline, heat loss is improved by 0-5% by changing it to electrical insulation pipe. In relation to the thermal plant, studied were cogeneration facility A using three 4MW gas turbines and combined cycle cogeneration facility B using two 40MW gas turbines. As a result, the amount of energy saving was 11,370 toe/y in pipeline, 12,750 toe/y in facility A and 69,000 toe/y in facility B. Further, the reduction amount of greenhouse effect gas emissions was 27,200t-CO2/y in pipeline, 30,500t-CO2/y in facility A and 164,900t-CO2/y in facility B. (NEDO)

  1. Principles and techniques for post-accident assessment and recovery in a contaminated environment of a nuclear facility

    International Nuclear Information System (INIS)

    1989-01-01

    To assist operators and public authorities alike in their advance preparation of emergency plans and in the establishment of emergency preparedness infrastructures, the IAEA has already issued several Safety Series publications dealing with these matters. This Safety Guide complements the technical guidance already published. It provides: a) Information and practical guidance relevant to assessing the off-site consequences during the late phase of a serious accident in a nuclear facility; b) Guidance on recovery operations off the site and the associated decision making process; and c) Proposals for consideration by national authorities regarding the organizational structure for the conduct of recovery operations. 52 refs, 8 figs, 4 tabs.

  2. OPALS: A COTS-based Tech Demo of Optical Communications

    Science.gov (United States)

    Oaida, Bogdan

    2012-01-01

    I. Objective: Deliver video from ISS to optical ground terminal via an optical communications link. a) JPL Phaeton/Early Career Hire (ECH) training project. b) Implemented as Class-D payload. c) Downlink at approx.30Mb/s. II. Flight System a) Optical Head Beacon Acquisition Camera. Downlink Transmitter. 2-axis Gimbal. b) Sealed Container Laser Avionics Power distribution Digital I/O board III. Implementation: a) Ground Station - Optical Communications Telescope Laboratory at Table Mountain Facility b) Flight System mounted to ISS FRAM as standard I/F. Attached externally on Express Logistics Carrier.

  3. Safeguards Summary Event List (SSEL). Pre-NRC trhough December 31, 1978

    International Nuclear Information System (INIS)

    1978-12-01

    Nine categories of events involving NRC licensed material or licensees are included. As additional information is obtained on an event, it will be incorporated in future editions. The list contains incidents as well as less significant events. The nine categories are: bomb-related (divided into two sections: (a) those events in which a bomb or explosive material was located or an explosion occurred at or in the vicinity of a licensed facility, (b) a complete chronological list), intrusion, missing and/or allegedly stolen, transportation-related, vandalism, arson, firearms-related, sabotage, and miscellaneous

  4. Acute hepatitis B outbreaks in 2 skilled nursing facilities and possible sources of transmission: North Carolina, 2009-2010.

    Science.gov (United States)

    Seña, Arlene C; Moorman, Anne; Njord, Levi; Williams, Roxanne E; Colborn, James; Khudyakov, Yury; Drobenuic, Jan; Xia, Guo-Liang; Wood, Hattie; Moore, Zack

    2013-07-01

    Acute hepatitis B virus (HBV) infections have been reported in long-term care facilities (LTCFs), primarily associated with infection control breaks during assisted blood glucose monitoring. We investigated HBV outbreaks that occurred in separate skilled nursing facilities (SNFs) to determine factors associated with transmission. Outbreak investigation with case-control studies. Two SNFs (facilities A and B) in Durham, North Carolina, during 2009-2010. Residents with acute HBV infection and controls randomly selected from HBV-susceptible residents during the outbreak period. After initial cases were identified, screening was offered to all residents, with repeat testing 3 months later for HBV-susceptible residents. Molecular testing was performed to assess viral relatedness. Infection control practices were observed. Case-control studies were conducted to evaluate associations between exposures and acute HBV infection in each facility. Six acute HBV cases were identified in each SNF. Viral phylogenetic analysis revealed a high degree of HBV relatedness within, but not between, facilities. No evaluated exposures were significantly associated with acute HBV infection in facility A; those associated with infection in facility B (all odds ratios >20) included injections, hospital or emergency room visits, and daily blood glucose monitoring. Observations revealed absence of trained infection control staff at facility A and suboptimal hand hygiene practices during blood glucose monitoring and insulin injections at facility B. These outbreaks underscore the vulnerability of LTCF residents to acute HBV infection, the importance of surveillance and prompt investigation of incident cases, and the need for improved infection control education to prevent transmission.

  5. Training courses run by the Department of Atomic Energy, India

    International Nuclear Information System (INIS)

    1981-01-01

    The Department of Atomic Energy (DAE), India, conducts a large number of courses covering a variety of fields, mainly concerned with nuclear energy and its applications. These courses are : (1) a comprehensive multidisciplinary course in nuclear sciences and engineering, (2) courses in safety aspects of: (a) the medical uses of radioisotopes, (b) research applications of ionising radiations, (c) the industrial applications of radiation sources, and (d) industrial radiography; (3) industrial radiographer's certification course, (4) course in hospital physics and radiological physics, (5) diploma course in radiation medicine, (6) courses in operation and maintenance of: (a) research reactors and facilities, (b) nuclear power reactors, and (7) course in exploration of atomic minerals. Detailed information on these courses, covering institutions of DAE conducting them, duration, academic requirements for admission to them, method of adimission, detailed syllabus, and general information such as fees, accommodation, stipend if any, etc. is given. (M.G.B.)

  6. Spiral 2 workshop

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    The accelerator and experimental facilities at GANIL will be transformed over the next 5-10 years. The centerpiece of the additions to the accelerator complex will be Spiral-2. This is the first phase of a new radioactive beam facility based on the ISOL principle. The main aim of Spiral-2 will be to produce intense, high quality beams of neutron-rich nuclei created in neutron-induced fission of heavy elements and accelerated by the existing CIME cyclotron. The principal aims of this workshop will be a) to publicize the new facilities, b) to discuss and define the science which might be carried out with them, c) to discuss the instrumentation and infrastructure required to exploit the new facilities and d) to help form collaborations of scientists wishing to design and construct the equipment needed to undertake the science programme. This document gathers most of the slides presented in the workshop.

  7. Fire protection research for energy technology projects; FY 79 year-end report

    International Nuclear Information System (INIS)

    Hasegawa, H.K.; Alvares, N.J.; Lipska, A.E.; Ford, H.; Beason, D.G.

    1981-01-01

    This report describes work performed in fiscal year 1979, on a DOE funded study entitled Fire Protection Research for Energy Technology Projects. The primary goal of this program is to ensure that fire protection measures for Fusion Energy Experiments (FEE) evolve concurrently with the complexity of FEE. Ultimately, it is planned that the detailed study of fusion experiments will provide an analytical methodology which can be applied to the full range of energy technology projects. We attempt to achieve this objective by coordinately advancing 3 (three) major task areas; (a) determine the fire hazards of current FEE facilities (b) assess the ability of accepted fire management strategies to meet and negate the hazard, (c) perform unique research into problem areas we have identified to provide input into analytical fire growth and damage assessment models

  8. Operation manual for the INEL on-line mass-separator facility

    International Nuclear Information System (INIS)

    Anderl, R.A.

    1984-06-01

    This report is an operation manual for an on-line mass-separator facility which is located in Building 661 at the Test Reactor Area of the Idaho National Engineering Laboratory. The facility provides mass-separated sources of short-lived fission-product radionuclides whose decay properties can be studied using a variety of nuclear spectroscopic techniques. This facility is unique in that it utilizes the gas-jet technique to transport fission products from a 252 Cf source located in a hot cell to the ion source of the mass separator. This document includes the following: (a) a detailed description of the facility, (b) identification of equipment hazards and safety controls, (c) detailed operating procedures for startup, continuous operation and shutdown, (d) operating procedures for the californium hot cell, and (e) an operator's manual for the automated moving tape collector/data acquisition system. 7 references, 16 figures, 8 tables

  9. Discriminative facility and its role in the perceived quality of interactional experiences.

    Science.gov (United States)

    Cheng, C; Chiu, C Y; Hong, Y Y; Cheung, J S

    2001-10-01

    Discriminative facility refers to an individual's sensitivity to subtle cues about the psychological meaning of a situation. This research aimed at examining (a) the conceptual distinctiveness of discriminative facility, (b) the situation-appropriate aspect of this construct, and (c) the relationship between discriminative facility and interpersonal experiences. Discriminative facility was assessed by a new measure of situation-appropriate behaviors across a variety of novel stressful situations. Results from study 1 showed that discriminative facility had weak positive relationships with cognitive complexity and nonsignificant relationships with self-monitoring and social desirability, indicating that discriminative facility is a unique construct. Results from Study 2 revealed that higher levels of discriminative facility were associated with higher levels of perceived social support and a greater number of pleasant interpersonal events experienced, thus providing support for the theoretical proposition that discriminative facility is an aspect of social intelligence.

  10. Vapor-cooled lead and stacks thermal performance and design analysis by finite difference techniques

    International Nuclear Information System (INIS)

    Peck, S.D.; Christensen, E.H.; O'Loughlin, J.M.

    1985-01-01

    Investigation of the combined thermal performance of the stacks and vapor cooled leads for the Mirror Fusion Test Facility-''B'' demonstrates considerable interdependency. For instance, the heat transfer to the vapor-cooled lead (VCL) from warm bus heaters, environmental enclosure, and stack is a significant additional heat load to the joule heating in the leads, proportionately higher for the lower current leads that have fewer current-carrying, counter flow coolant copper tubes. Consequently, the specific coolant flow (G/sec-kA-lead pair) increases as the lead current decreases. The definition of this interdependency and the definition of necessary thermal management has required an integrated thermal model for the entire stack/VCL assemblies

  11. Spiral 2 workshop

    International Nuclear Information System (INIS)

    2004-01-01

    The accelerator and experimental facilities at GANIL will be transformed over the next 5-10 years. The centerpiece of the additions to the accelerator complex will be Spiral-2. This is the first phase of a new radioactive beam facility based on the ISOL principle. The main aim of Spiral-2 will be to produce intense, high quality beams of neutron-rich nuclei created in neutron-induced fission of heavy elements and accelerated by the existing CIME cyclotron. The principal aims of this workshop will be a) to publicize the new facilities, b) to discuss and define the science which might be carried out with them, c) to discuss the instrumentation and infrastructure required to exploit the new facilities and d) to help form collaborations of scientists wishing to design and construct the equipment needed to undertake the science programme. This document gathers most of the slides presented in the workshop

  12. Fuel cycle based safeguards

    International Nuclear Information System (INIS)

    De Montmollin, J.M.; Higinbotham, W.A.; Gupta, D.

    1985-07-01

    In NPT safeguards the same model approach and absolute-quantity inspection goals are applied at present to all similar facilities, irrespective of the State's fuel cycle. There is a continuing interest and activity on the part of the IAEA in new NPT safeguards approaches that more directly address a State's nuclear activities as a whole. This fuel cycle based safeguards system is expected to a) provide a statement of findings for the entire State rather than only for individual facilities; b) allocate inspection efforts so as to reflect more realistically the different categories of nuclear materials in the different parts of the fuel cycle and c) provide more timely and better coordinated information on the inputs, outputs and inventories of nuclear materials in a State. (orig./RF) [de

  13. Criteria Document for B-plant's Surveillance and Maintenance Phase Safety Basis Document

    International Nuclear Information System (INIS)

    SCHWEHR, B.A.

    1999-01-01

    This document is required by the Project Hanford Managing Contractor (PHMC) procedure, HNF-PRO-705, Safety Basis Planning, Documentation, Review, and Approval. This document specifies the criteria that shall be in the B Plant surveillance and maintenance phase safety basis in order to obtain approval of the DOE-RL. This CD describes the criteria to be addressed in the S and M Phase safety basis for the deactivated Waste Fractionization Facility (B Plant) on the Hanford Site in Washington state. This criteria document describes: the document type and format that will be used for the S and M Phase safety basis, the requirements documents that will be invoked for the document development, the deactivated condition of the B Plant facility, and the scope of issues to be addressed in the S and M Phase safety basis document

  14. Establishing the estimation model on radiation level at the ambience of 60Co radiotherapy treatment room based on NCRP REPORT No.151

    International Nuclear Information System (INIS)

    Yang Haiyou; Liu Liping; Liang Yueqin; Yu Shui

    2009-01-01

    Objective: To establish the estimation model to evaluate the radiation level at the ambience of 60 Co radiotherapy treatment room. Methods: The estimation model derives from NCRP REPORT No.151- S tructural Shielding Design and Evaluation for Megavoltage X-and Gamma-Ray Radiotherapy Facilities b y making appropriate adjustment, which presents the calculation methods on radiation level at the ambience of megavoltage medical electron linear accelerator treatment room. Results: The application scope of estimation model from NCRP REPORT No.151 is extended to γ-radiotherapy facilities, and it can be regarded as a new model for calculating the radiation level at the ambience of 60 Co radiotherapy treatment room. Conclusion: The estimation model has certain reference value to evaluate the radiation level at the ambience of 60 Co radiotherapy treatment room. (authors)

  15. Accessibility to tuberculosis control services and tuberculosis programme performance in southern Ethiopia

    Directory of Open Access Journals (Sweden)

    Mesay Hailu Dangisso

    2015-11-01

    Full Text Available Background: Despite the expansion of health services and community-based interventions in Ethiopia, limited evidence exists about the distribution of and access to health facilities and their relationship with the performance of tuberculosis (TB control programmes. We aim to assess the geographical distribution of and physical accessibility to TB control services and their relationship with TB case notification rates (CNRs and treatment outcome in the Sidama Zone, southern Ethiopia. Design: We carried out an ecological study to assess physical accessibility to TB control facilities and the association of physical accessibility with TB CNRs and treatment outcome. We collected smear-positive pulmonary TB (PTB cases treated during 2003–2012 from unit TB registers and TB service data such as availability of basic supplies for TB control and geographic locations of health services. We used ArcGIS 10.2 to measure the distance from each enumeration location to the nearest TB control facilities. A linear regression analysis was employed to assess factors associated with TB CNRs and treatment outcome. Results: Over a decade the health service coverage (the health facility–to-population ratio increased by 36% and the accessibility to TB control facilities also improved. Thus, the mean distance from TB control services was 7.6 km in 2003 (ranging from 1.8 to 25.5 km between kebeles (the smallest administrative units and had decreased to 3.2 km in 2012 (ranging from 1.5 to 12.4 km. In multivariate linear regression, as distance from TB diagnostic facilities (b-estimate=−0.25, p<0.001 and altitude (b-estimate=−0.31, p<0.001 increased, the CNRs of TB decreased, whereas a higher population density was associated with increased TB CNRs. Similarly, distance to TB control facilities (b-estimate=−0.27, p<0.001 and altitude (b-estimate=−0.30, p<0.001 were inversely associated with treatment success (proportion of treatment completed or cured cases

  16. Requirements to obtain the recognition of radiological protection experts

    International Nuclear Information System (INIS)

    Arguelles, R.; Villarroel, R.; Senderos, V.; Campos, R.; Pinos, M.; Ponjuan, G.; Franco, P.; Rueda, D.

    2003-01-01

    The scope of this paper is to summarize the general requirements related to education, training and skill of the individual to obtain the recognition of radiological protection experts on ionizing radiation (experts on radiological protection- RP). There has been established two levels according to the grade of responsibility: Qualified expert provided with a diploma given by de Nuclear Safety Council. Technician expert on radiological protection whose certification is made by the Qualified expert that supervise their work. To obtain the diploma of qualified expert is required an official degree, a title of Architecture, Engineering or equivalent in case of no national degrees; specific training on radiological protection (300 hours) and the knowledge on safety and radiological protection of the facilities to be supervised. Three years of experience on radiological protection must be proved. To get the recognition of technician expert on radiological protection is required Formacion Profesional de Grado Superior or equivalent and specific training on safety and radiological protection. Knowledge on basis and principles of radiological protection are required. According to the type of the facilities to be supervised there are two models: A model: to deal with facilities included in RD 1836/1999 (nuclear and radioactive facilities). B model: to deal with medical X rays facilities approved under RD 1891/1991 three months of experience on the selected model must be proved. (Author)

  17. ASEAN Mineral Database and Information System (AMDIS)

    Science.gov (United States)

    Okubo, Y.; Ohno, T.; Bandibas, J. C.; Wakita, K.; Oki, Y.; Takahashi, Y.

    2014-12-01

    AMDIS has lunched officially since the Fourth ASEAN Ministerial Meeting on Minerals on 28 November 2013. In cooperation with Geological Survey of Japan, the web-based GIS was developed using Free and Open Source Software (FOSS) and the Open Geospatial Consortium (OGC) standards. The system is composed of the local databases and the centralized GIS. The local databases created and updated using the centralized GIS are accessible from the portal site. The system introduces distinct advantages over traditional GIS. Those are a global reach, a large number of users, better cross-platform capability, charge free for users, charge free for provider, easy to use, and unified updates. Raising transparency of mineral information to mining companies and to the public, AMDIS shows that mineral resources are abundant throughout the ASEAN region; however, there are many datum vacancies. We understand that such problems occur because of insufficient governance of mineral resources. Mineral governance we refer to is a concept that enforces and maximizes the capacity and systems of government institutions that manages minerals sector. The elements of mineral governance include a) strengthening of information infrastructure facility, b) technological and legal capacities of state-owned mining companies to fully-engage with mining sponsors, c) government-led management of mining projects by supporting the project implementation units, d) government capacity in mineral management such as the control and monitoring of mining operations, and e) facilitation of regional and local development plans and its implementation with the private sector.

  18. B cell remote-handled waste shipment cask alternatives study

    International Nuclear Information System (INIS)

    RIDDELLE, J.G.

    1999-01-01

    The decommissioning of the 324 Facility B Cell includes the onsite transport of grouted remote-handled radioactive waste from the 324 Facility to the 200 Areas for disposal. The grouted waste has been transported in the leased ATG Nuclear Services 3-82B Radioactive Waste Shipping Cask (3-82B cask). Because the 3-82B cask is a U.S. Nuclear Regulatory Commission (NRC)-certified Type B shipping cask, the lease cost is high, and the cask operations in the onsite environment may not be optimal. An alternatives study has been performed to develop cost and schedule information on alternative waste transportation systems to assist in determining which system should be used in the future. Five alternatives were identified for evaluation. These included continued lease of the 3-82B cask, fabrication of a new 3-82B cask, development and fabrication of an onsite cask, modification of the existing U.S. Department of Energy-owned cask (OH-142), and the lease of a different commercially available cask. Each alternative was compared to acceptance criteria for use in the B Cell as an initial screening. Only continued leasing of the 3-82B cask, fabrication of a new 3-82B cask, and the development and fabrication of an onsite cask were found to meet all of the B Cell acceptance criteria

  19. Over Batch Analysis for the LLNL Plutonium Packaging System (PuPS)

    International Nuclear Information System (INIS)

    Riley, D.; Dodson, K.

    2007-01-01

    This document addresses the concern raised in the Savannah River Site (SRS) Acceptance Criteria (Reference 1, Section 6.a.3) about receiving an item that is over batched by 1.0 kg of fissile materials. This document shows that the occurrence of this is incredible. Some of the Department of Energy Standard 3013 (DOE-STD-3013) requirements are described in Section 2.1. The SRS requirement is discussed in Section 2.2. Section 2.3 describes the way fissile materials are handled in the Lawrence Livermore National Laboratory (LLNL) Plutonium Facility (B332). Based on the material handling discussed in Section 2.3, there are only three errors that could result in a shipping container being over batched. These are: incorrect measurement of the item, selecting the wrong item to package, and packaging two items into a single shipping container. The analysis in Section 3 shows that the first two events are incredible because of the controls that exist at LLNL. The third event is physically impossible. Therefore, it is incredible for an item to be shipped to SRS that is more than 1.0 kg of fissile materials over batched

  20. Over Batch Analysis for the LLNL DOE-STD-3013 Packaging System

    International Nuclear Information System (INIS)

    Riley, D.C.; Dodson, K.

    2009-01-01

    This document addresses the concern raised in the Savannah River Site (SRS) Acceptance Criteria about receiving an item that is over batched by 1.0 kg of fissile materials. This document shows that the occurrence of this is incredible. Some of the Department of Energy Standard 3013 (DOE-STD-3013) requirements are described in Section 2.1. The SRS requirement is discussed in Section 2.2. Section 2.3 describes the way fissile materials are handled in the Lawrence Livermore National Laboratory (LLNL) Plutonium Facility (B332). Based on the material handling discussed in Section 2.3, there are only three errors that could result in a shipping container being over batched. These are: incorrect measurement of the item, selecting the wrong item to package, and packaging two items into a single shipping container. The analysis in Section 3 shows that the first two events are incredible because of the controls that exist at LLNL. The third event is physically impossible. Therefore, it is incredible for an item to be shipped to SRS that is more than 1.0 kg of fissile materials over batched.

  1. A study on implementation plan of decontamination and decommissioning R and D and evaluation of KAERI soil decontamination process

    International Nuclear Information System (INIS)

    Oh, Won Zin; Lee, K. W.; Won, H. J.; Jung, C. H.; Choi, W. K.; Kim, G. N.

    2001-08-01

    A. Decontamination Technology Development of Uranium Conversion Facility. Understanding of uranium conversion facility and related decontamination technologies, and analysis of current status of decontamination technologies. Establishment of the objective and research items of the middle and long term R and D project. Discussion of the erformance plan and about the methodology for connection with the project of environmental restoration of uranium conversion facility B. Treatment Technology Development of Uranium Sludge Analysis of the domestic and overseas research development status. Suggestion of treatment methodology of uranium slurry and cooperative R and D among industries, universities and research institute. Establishment of the objective and research items of the middle and long term R and D project. Discussion about the performance plan and about the methodology for connection with the project of environmental restoration of uranium conversion facility C. Decommissioning Technology Development Analysis of the domestic and overseas research development status and the overview of decommissioning technologies. Establishment of the objective and research items of the middle and long term R and D project. Discussion about the performance plan and about the methodology for connection with the project of TRIGA decommissioning D. Evaluation of KAERI Soil Decontamination Technology. Evaluation of soil decontamination process and the liquid decontamination waste treatment technology. Performance of soil decontamination test using solvent flushing test equipment for evaluation of residual radioactivity after decontami- nation and modeling of the results

  2. Contractor Work Preparation Process Improvement Using Lean Six Sigma

    Directory of Open Access Journals (Sweden)

    Asana Kusnadi

    2016-06-01

    Full Text Available To ensure the health and safety of their workforce and protection of their assets and the environment, a global oil and gas company operating in Indonesia requires comprehensive identification and evaluation of job hazards that were included in work permitting process prior work execution in the field. Based on 20 data points obtained in August 2013, start-working time for contractors who worked for Capital Project Management (CPM Team in Facility B was in average at 09.05 a.m. The aim of this paper is to present how the firm implemented Lean Six Sigma to reduce non-added value activities while fulfilling to its safety requirements and to share lessons learned from practical and theory testing perspective. The methodology used is Lean Six Sigma’s DMAIC (Define, Measure, Analyze, Improve, Control as mandated by the corporate policy of the firm. This research adopts a mix-methods approach, by using both qualitative and quantitative data. This study was a one year longitudinal study of the Lean Six Sigma implementation to improve contractors’ work preparation process. The improvement resulted in reduction of non-value added activities and successfully increased the available working time per day by 59.3 minutes in average. The results of this case study reconfirm Lean Six Sigma as a good management theory since it shows a consistency between the theory and the real practice in a global oil and gas company in Indonesia.

  3. Limits to the Recognizability of Flaws in Non-Destructive Testing Steam-Generator Tubes for Nuclear-Power Plants

    International Nuclear Information System (INIS)

    Kuhlmann, A.; Adamsky, F.-J.

    1965-01-01

    In the Federal Republic of Germany there are nuclear reactors under construction with steam generators inside the reactor pressure-vessel. As a result design repairs of steam- generator tubes are very difficult and cause large shut-down times of the nuclear-power plant. It is known that numerous troubles in operating conventional power plants are results of steam-generator tube damages. Because of the high total costs of these reactors it. is necessary to construct the steam generators especially in such a manner that the load factor of the power plant is as high as possible. The Technischer Überwachungs-Verein Rheinland was charged to supervise and to test fabrication and construction of the steam generators to see that this part of the plant was as free of defects as possible. The experience gained during this work is of interest for manufacture and construction of steam generators for nuclear-power plants in general. This paper deals with the efficiency limits of non-destructive testing steam-generator tubes. The following tests performed will be discussed in detail: (a) Automatic ultrasonic testing of the straight tubes in the production facility; (b) Combined ultrasonic and radiographic testing of the bent tubes and tube weldings; (c) Other non-destructive tests. (author) [fr

  4. Requirements for US regulatory approval of the International Thermonuclear Experimental Reactor (ITER)

    International Nuclear Information System (INIS)

    Petti, D.A.; Haire, J.C.

    1993-12-01

    The International Thermonuclear Experimental Reactor (ITER) is the first fusion machine that will have sufficient decay heat and activation product inventory to pose potential nuclear safety concerns. As a result, nuclear safety and environmental issues will be much more important in the approval process for the design, siting, construction, and operation of ITER in the United States than previous fusion devices, such as the Tokamak Fusion Test Reactor. The purpose of this report is (a) to provide an overview of the regulatory approval process for a Department of Energy (DOE) nuclear facility; (b) to present the dose limits used by DOE to protect workers, the public, and the environment from the risks of exposure to radiation and hazardous materials; (c) to discuss some key nuclear safety-related issues that must be addressed early in the Engineering Design Activities (EDA) to obtain regulatory approval; and (d) to provide general guidelines to the ITER Joint Central Team (JCT) concerning the development of a regulatory framework for the ITER project

  5. Microbiological monitoring of guinea pigs reared conventionally at two breeding facilities in Korea.

    Science.gov (United States)

    Park, Jong-Hwan; Seok, Seung-Hyeok; Baek, Min-Won; Lee, Hui-Young; Kim, Dong-Jae; Cho, Jung-Sik; Kim, Chuel-Kyu; Hwang, Dae-Youn; Park, Jae-Hak

    2006-10-01

    In this study, microbiological monitoring of guinea pigs reared conventionally in two facilities was performed twice in 2004, with a three-month-interval between surveys. This study was based on the recommendations of the FELASA Working Group, with some modifications. In serological tests in the first survey, some animals from facility A showed positive results for Encephalitozoon cuniculi, Sendai virus, pneumonia virus of mice (PVM), and Reovirus-3 (Reo-3); facility B showed a positive result only for E. cuniculi. The results of the second survey were similar to the first, except for the presence of Sendai virus; all animals from the two facilities were Sendai virus-negative in the second experiment. No pathogenic bacteria were cultured in the organs of any of the animals in the first survey. However, in the second survey, Bordetella bronchiseptica was cultured from the lung tissue of two 10-week-old animals from facility A. Chlamydial infection was examined by the Macchiavello method, but no animal showed positive results. Tests using fecal flotation or the KOH wet mount method showed no infection of endoparasites, protozoa, ectoparasites, or dermatophytes in any animal in both surveys. However, in the histopathological examination, an infection of protozoa-like organisms was observed in the cecum of some animals from facility A. The present study revealed that microbiological contamination was present in guinea pigs reared conventionally in two facilities in Korea, suggesting that there is a need to improve environmental conditions in order to eradicate microbial contamination.

  6. B cell remote-handled waste shipment cask alternatives study; TOPICAL

    International Nuclear Information System (INIS)

    RIDDELLE, J.G.

    1999-01-01

    The decommissioning of the 324 Facility B Cell includes the onsite transport of grouted remote-handled radioactive waste from the 324 Facility to the 200 Areas for disposal. The grouted waste has been transported in the leased ATG Nuclear Services 3-82B Radioactive Waste Shipping Cask (3-82B cask). Because the 3-82B cask is a U.S. Nuclear Regulatory Commission (NRC)-certified Type B shipping cask, the lease cost is high, and the cask operations in the onsite environment may not be optimal. An alternatives study has been performed to develop cost and schedule information on alternative waste transportation systems to assist in determining which system should be used in the future. Five alternatives were identified for evaluation. These included continued lease of the 3-82B cask, fabrication of a new 3-82B cask, development and fabrication of an onsite cask, modification of the existing U.S. Department of Energy-owned cask (OH-142), and the lease of a different commercially available cask. Each alternative was compared to acceptance criteria for use in the B Cell as an initial screening. Only continued leasing of the 3-82B cask, fabrication of a new 3-82B cask, and the development and fabrication of an onsite cask were found to meet all of the B Cell acceptance criteria

  7. Detailed design of the RF source for the 1 MV neutral beam test facility

    International Nuclear Information System (INIS)

    Marcuzzi, D.; Palma, M. Dalla; Pavei, M.; Heinemann, B.; Kraus, W.; Riedl, R.

    2009-01-01

    In the framework of the EU activities for the development of the Neutral Beam Injector for ITER, the detailed design of the Radio Frequency (RF) driven negative ion source to be installed in the 1 MV ITER Neutral Beam Test Facility (NBTF) has been carried out. Results coming from ongoing R and D on IPP test beds [A. Staebler et al., Development of a RF-Driven Ion Source for the ITER NBI System, this conference] and the design of the new ELISE facility [B. Heinemann et al., Design of the Half-Size ITER Neutral Beam Source Test Facility ELISE, this conference] brought several modifications to the solution based on the previous design. An assessment was carried out regarding the Back-Streaming positive Ions (BSI+) that impinge on the back plates of the ion source and cause high and localized heat loads. This led to the redesign of most heated components to increase cooling, and to different choices for the plasma facing materials to reduce the effects of sputtering. The design of the electric circuit, gas supply and the other auxiliary systems has been optimized. Integration with other components of the beam source has been revised, with regards to the interfaces with the supporting structure, the plasma grid and the flexible connections. In the paper the design will be presented in detail, as well as the results of the analyses performed for the thermo-mechanical verification of the components.

  8. Characterization of Carbon-Contaminated B4C-Coated Optics after Chemically Selective Cleaning with Low-Pressure RF Plasma.

    Science.gov (United States)

    Moreno Fernández, H; Rogler, D; Sauthier, G; Thomasset, M; Dietsch, R; Carlino, V; Pellegrin, E

    2018-01-22

    Boron carbide (B 4 C) is one of the few materials that is expected to be most resilient with respect to the extremely high brilliance of the photon beam generated by free electron lasers (FELs) and is thus of considerable interest for optical applications in this field. However, as in the case of many other optics operated at light source facilities, B 4 C-coated optics are subject to ubiquitous carbon contaminations. Carbon contaminations represent a serious issue for the operation of FEL beamlines due to severe reduction of photon flux, beam coherence, creation of destructive interference, and scattering losses. A variety of B 4 C cleaning technologies were developed at different laboratories with varying success. We present a study regarding the low-pressure RF plasma cleaning of carbon contaminated B 4 C test samples via inductively coupled O 2 /Ar, H 2 /Ar, and pure O 2 RF plasma produced following previous studies using the same ibss GV10x downstream plasma source. Results regarding the chemistry, morphology as well as other aspects of the B 4 C optical coating before and after the plasma cleaning are reported. We conclude that among the above plasma processes only plasma based on pure O 2 feedstock gas exhibits the required chemical selectivity for maintaining the integrity of the B 4 C optical coatings.

  9. Scope and approach to management of mixed wastes: introduction to the session

    International Nuclear Information System (INIS)

    Ausmus, B.S.

    1986-01-01

    Mixed wastes are those that are termed both radioactive and chemically hazardous based on regulatory criteria in the United States. Historically, mixed wastes that could be classified as radioactive wastes were treated, stored, and disposed under statutes governing radioactive wastes. In recent years, it has become apparent that: (a) hazardous wastes are generated in nuclear facilities; (b) many wastes are both radioactive and chemically hazardous; and (c) the management of chemically hazardous wastes and mixed wastes requires reexamination of current waste treatment/disposal methods and development/implementation of modified methods. The purpose of this session is to discuss specific aspects of the mixed waste management problems and to provide a forum for discussion of the technical and institutional barriers to problem solutions. The paper addresses several mixed waste problems and current approaches to their solutions, including: (1) mixed waste management in fuel cycle facilities; (2) mixed waste management in a US Dept. of Energy production facility; and (3) mixed wastes impacts on 10CFR61 compliance. Technical and institutional approaches to mixed waste management are explored in three areas: (1) alternatives for treatment prior to shallow land disposal; (2) potential benefits of recovery of strategic/critical materials from mixed wastes; and (3) shallow land disposal system compatibilities/problems

  10. University Students’ Perception of Demotivating Factors in Learning English as a Foreign Language

    Directory of Open Access Journals (Sweden)

    Nafiseh Hosseinpour

    2013-11-01

    Full Text Available Demotivation is a relatively new topic in the field of second or foreign language acquisition which is in need of more rigorous research. In this regard, the present study was an attempt to investigate demotivating factors in learning English as a foreign language in an Iranian context. To this end, 382 Persian learners of English were selected through stratified clustering sampling procedure to participate in this mixed method study. The Data was collected through a 40-item Likert type questionnaire. The Factor analysis of the data extracted seven factors including a inadequate facilities, b reduced self-confidence, c class characteristics, d lack of purpose to study English, e teaching methods, f teachers and teaching styles, and g negative attitudes toward English and the culture of English-speaking countries as demotivators. The Students’ perceptions of these seven factors were compared based on their general English proficiency levels. The Results revealed that low proficient learners perceived reduced self-confidence and negative attitudes more demotivating than their counterparts at other levels of proficiency.

  11. A study on implementation plan of decontamination and decommissioning R and D and evaluation of KAERI soil decontamination process

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Won Zin; Lee, K. W.; Won, H. J.; Jung, C. H.; Choi, W. K.; Kim, G. N

    2001-08-01

    A. Decontamination Technology Development of Uranium Conversion Facility. Understanding of uranium conversion facility and related decontamination technologies, and analysis of current status of decontamination technologies. Establishment of the objective and research items of the middle and long term R and D project. Discussion of the erformance plan and about the methodology for connection with the project of environmental restoration of uranium conversion facility B. Treatment Technology Development of Uranium Sludge Analysis of the domestic and overseas research development status. Suggestion of treatment methodology of uranium slurry and cooperative R and D among industries, universities and research institute. Establishment of the objective and research items of the middle and long term R and D project. Discussion about the performance plan and about the methodology for connection with the project of environmental restoration of uranium conversion facility C. Decommissioning Technology Development Analysis of the domestic and overseas research development status and the overview of decommissioning technologies. Establishment of the objective and research items of the middle and long term R and D project. Discussion about the performance plan and about the methodology for connection with the project of TRIGA decommissioning D. Evaluation of KAERI Soil Decontamination Technology. Evaluation of soil decontamination process and the liquid decontamination waste treatment technology. Performance of soil decontamination test using solvent flushing test equipment for evaluation of residual radioactivity after decontami- nation and modeling of the results.

  12. Assessment of radiation dose due to fluoroscopic procedures in patients at some selected facilities in the Greater Accra Region, Ghana

    International Nuclear Information System (INIS)

    Gyasi, E.

    2013-07-01

    Radiation doses to 182 adults patients who underwent barium enema, barium meal, barium swallow, myelogram, hysterosalpingography and urethrogram examination collectively at facilities A and B were investigated. Radiation dose was measured using kerma-area-product (KAP) meter. From the KAP readings, patient's data and other relevant information from the control console, effective dose and selective organ doses were estimated using Monte Carlo program software (PCXMC version 1.5). Quality control tests performed on the two fluoroscopy machines were found to be within the acceptance criteria. Mean effective doses were found to be 8.45 ± 0.38mSv, 7.628 ± 0.42 mSv, 1.46 ± 0.13 mSv, 2.02 ± 0.16 mSv, 0.32 ± 0.03 mSv for barium enema, barium meal, barium swallow, myelogram and urethrogram examinations respectively at Facility A. At Facility B the mean effective dose were found to be 4.12 ± 0.15 mSv, 1.83 ± 0.10 mSv, 0.81 ± 0.04 mSv, 0.53 ± 0.036 mSv and 0.27 ± 0.01 mSv for barium enema, barium meal, barium swallow, myelogram, hysterosalpingography and urethrogram examination respectively. Thymus received the highest organ dose of 29.19± 2.07mGy during barium meal studies at Facility A of all the procedures in the two hospitals. Magnitude of organ doses was observed to to be in relation with the closeness to or in the direction of the primary beam of radiation. Organ and effective doses from Facility A were relatively higher than those from Facility B in comparison by a factor of a about 2 with the exception of the barium meal examination at Facility A which was by a factor of about 4. The measured KAP readings fro the two facilities were below the international accepted reference levels with the exception of barium meal examination at Facility A which recorded a higher value of 25.96 ± 1.83 Gy.cm 2 as compared to ICRP (2001) reference value of 25 Gy.cm 2 . Longer radiation beam on time, high number of radiographs taken per patient, wide exposure beam area on

  13. Field evaluations of the VDmax approach for substantiation of a 25 kGy sterilization dose and its application to other preselected doses

    International Nuclear Information System (INIS)

    Kowalski, John B.; Herring, Craig; Baryschpolec, Lisa; Reger, John; Patel, Jay; Feeney, Mary; Tallentire, Alan

    2002-01-01

    The International and European standards for radiation sterilization require evidence of the effectiveness of a minimum sterilization dose of 25 kGy but do not provide detailed guidance on how this evidence can be generated. An approach, designated VD max , has recently been described and computer evaluated to provide safe and unambiguous substantiation of a 25 kGy sterilization dose. The approach has been further developed into a practical method, which has been subjected to field evaluations at three manufacturing facilities which produce different types of medical devices. The three facilities each used a different overall evaluation strategy: Facility A used VD max for quarterly dose audits; Facility B compared VD max and Method 1 in side-by-side parallel experiments; and Facility C, a new facility at start-up, used VD max for initial substantiation of 25 kGy and subsequent quarterly dose audits. A common element at all three facilities was the use of 10 product units for irradiation in the verification dose experiment. The field evaluations of the VD max method were successful at all three facilities; they included many different types of medical devices/product families with a wide range of average bioburden and sample item portion values used in the verification dose experiments. Overall, around 500 verification dose experiments were performed and no failures were observed. In the side-by-side parallel experiments, the outcomes of the VD max experiments were consistent with the outcomes observed with Method 1. The VD max approach has been extended to sterilization doses >25 and max method for doses other than 25 kGy must await controlled field evaluations and the development of appropriate specifications/standards

  14. Utilization of a state run public private emergency transportation service exclusively for childbirth: the Janani (maternal) Express program in Madhya Pradesh, India.

    Science.gov (United States)

    Sidney, Kristi; Ryan, Kayleigh; Diwan, Vishal; De Costa, Ayesha

    2014-01-01

    In 2009 the state government of Madhya Pradesh, India launched an emergency obstetric transportation service, Janani Express Yojana (JEY), to support the cash transfer program that promotes institutional delivery. JEY, a large scale public private partnership, lowers geographical access barriers to facility based care. The state contracts and pays private agencies to provide emergency transportation at no cost to the user. The objective was to study (a) the utilization of JEY among women delivering in health facilities, (b) factors associated with usage, (c) the timeliness of the service. A cross sectional facility based study was conducted in facilities that carried out > ten deliveries a month. Researchers who spent five days in each facility administered a questionnaire to all women who gave birth there to elicit socio-demographic characteristics and transport related details. 35% of women utilised JEY to reach a facility, however utilization varied between study districts. Uptake was highest among women from rural areas (44%), scheduled tribes (55%), and poorly educated women (40%). Living in rural areas and belonging to scheduled tribes were significant predictors for JEY usage. Almost 1/3 of JEY users (n = 104) experienced a transport related delay. The JEY service model complements the cash transfer program by providing transport to a facility to give birth. A study of the distribution of utilization in population subgroups suggests the intervention was successful in reaching the most vulnerable population, promoting equity in access. While 1/3 of women utilized the service and it saved them money; 30% experienced significant transport related delays in reaching a facility, which is comparable to women using public transportation. Further research is needed to understand why utilization is low, to explore if there is a need for service expansion at the community level and to improve the overall time efficiency of JEY.

  15. Coil-On-Plug Ignition for LOX/Methane Liquid Rocket Engines in Thermal Vacuum Environments

    Science.gov (United States)

    Melcher, John C.; Atwell, Matthew J.; Morehead, Robert L.; Hurlbert, Eric A.; Bugarin, Luz; Chaidez, Mariana

    2017-01-01

    A coil-on-plug ignition system has been developed and tested for Liquid Oxygen (LOX) / liquid methane rocket engines operating in thermal vacuum conditions. The igniters were developed and tested as part of the Integrated Cryogenic Propulsion Test Article (ICPTA), previously tested as part of the Project Morpheus test vehicle. The ICPTA uses an integrated, pressure-fed, cryogenic LOX/methane propulsion system including a reaction control system (RCS) and a main engine. The ICPTA was tested at NASA Glenn Research Center's Plum Brook Station in the Spacecraft Propulsion Research Facility (B-2) under vacuum and thermal vacuum conditions. In order to successfully demonstrate ignition reliability in the vacuum conditions and eliminate corona discharge issues, a coil-on-plug ignition system has been developed. The ICPTA uses spark-plug ignition for both the main engine igniter and the RCS. The coil-on-plug configuration eliminates the conventional high-voltage spark plug cable by combining the coil and the spark-plug into a single component. Prior to ICPTA testing at Plum Brook, component-level reaction control engine (RCE) and main engine igniter testing was conducted at NASA Johnson Space Center (JSC), which demonstrated successful hot-fire ignition using the coil-on-plug from sea-level ambient conditions down to 10(exp.-2) torr. Integrated vehicle hot-fire testing at JSC demonstrated electrical and command/data system performance. Lastly, Plum Brook testing demonstrated successful ignitions at simulated altitude conditions at 30 torr and cold thermal-vacuum conditions at 6 torr. The test campaign successfully proved that coil-on-plug technology will enable integrated LOX/methane propulsion systems in future spacecraft.

  16. Coil-On-Plug Ignition for Oxygen/Methane Liquid Rocket Engines in Thermal-Vacuum Environments

    Science.gov (United States)

    Melcher, John C.; Atwell, Matthew J.; Morehead, Robert L.; Hurlbert, Eric A.; Bugarin, Luz; Chaidez, Mariana

    2017-01-01

    A coil-on-plug ignition system has been developed and tested for Liquid Oxygen (LOX)/liquid methane (LCH4) rocket engines operating in thermal vacuum conditions. The igniters were developed and tested as part of the Integrated Cryogenic Propulsion Test Article (ICPTA), previously tested as part of the Project Morpheus test vehicle. The ICPTA uses an integrated, pressure-fed, cryogenic LOX/LCH4 propulsion system including a reaction control system (RCS) and a main engine. The ICPTA was tested at NASA Glenn Research Center's Plum Brook Station in the Spacecraft Propulsion Research Facility (B-2) under vacuum and thermal vacuum conditions. A coil-on-plug ignition system has been developed to successfully demonstrate ignition reliability at these conditions while preventing corona discharge issues. The ICPTA uses spark plug ignition for both the main engine igniter and the RCS. The coil-on-plug configuration eliminates the conventional high-voltage spark plug cable by combining the coil and the spark plug into a single component. Prior to ICPTA testing at Plum Brook, component-level reaction control engine (RCE) and main engine igniter testing was conducted at NASA Johnson Space Center (JSC), which demonstrated successful hot-fire ignition using the coil-on-plug from sea-level ambient conditions down to 10(exp -2) torr. Integrated vehicle hot-fire testing at JSC demonstrated electrical and command/data system performance. Lastly, hot-fire testing at Plum Brook demonstrated successful ignitions at simulated altitude conditions at 30 torr and cold thermal-vacuum conditions at 6 torr. The test campaign successfully proved that coil-on-plug technology will enable integrated LOX/LCH4 propulsion systems in future spacecraft.

  17. Fostering Environmental Literacy For A Changing Earth: Interactive and Participatory Outreach Programs at Biosphere 2

    Science.gov (United States)

    Pavao-Zuckerman, M.; Huxman, T.; Morehouse, B.

    2008-12-01

    Earth system and ecological sustainability problems are complex outcomes of biological, physical, social, and economic interactions. A common goal of outreach and education programs is to foster a scientifically literate community that possesses the knowledge to contribute to environmental policies and decision making. Uncertainty and variability that is both inherent in Earth system and ecological sciences can confound such goals of improved ecological literacy. Public programs provide an opportunity to engage lay-persons in the scientific method, allowing them to experience science in action and confront these uncertainties face-on. We begin with a definition of scientific literacy that expands its conceptualization of science beyond just a collection of facts and concepts to one that views science as a process to aid understanding of natural phenomena. A process-based scientific literacy allows the public, teachers, and students to assimilate new information, evaluate climate research, and to ultimately make decisions that are informed by science. The Biosphere 2 facility (B2) is uniquely suited for such outreach programs because it allows linking Earth system and ecological science research activities in a large scale controlled environment setting with outreach and education opportunities. A primary outreach goal is to demonstrate science in action to an audience that ranges from K-12 groups to retired citizens. Here we discuss approaches to outreach programs that focus on soil-water-atmosphere-plant interactions and their roles in the impacts and causes of global environmental change. We describe a suite of programs designed to vary the amount of participation a visitor has with the science process (from passive learning to data collection to helping design experiments) to test the hypothesis that active learning fosters increased scientific literacy and the creation of science advocates. We argue that a revised framing of the scientific method with a more

  18. Food irradiation in Malaysia

    International Nuclear Information System (INIS)

    Mohd Ghazali Hj Abd Rahman.

    1985-01-01

    Food irradiation has recently been visited as a technology that can contribute to the solution of problems associated with food preservation of Malaysia's agriculture produce and products thereby improving the economic status of the rural sector. However, the history of food irradiation in Malaysia is very recent. Research carried out on food irradiation only began in 1974 as a result of the installation of a 60 Co facility (initially 10,000 Ci) at the National University of Malaysia. Since its installation several studies have been carried out pertaining to the food irradiation. Presently its development has been slow. Research in this area has been confined to laboratory scale and purely academic. This limitation is due to a number of reasons, among others are: a) limited number of facilities; b) lack of expertise to conduct its research; c) other preservation methods can be improved with lower capital output. An important step towards its development was made when Malaysia actively participated in the RCA/IAEA food irradiation project, viz. the irradiation of pepper which was carried out at the National University of Malaysia in the 80's. As a result of this venture, research and development activities in food irradiation have been geared toward semi-plot scale with the view ot commercialization in the future. In 1982, a group of researchers was formed to conduct feasibility studies using irradiation techniques in trying to overcome several problems associated with our local paddy and rice. Another group is being organized by the National University of Malaysia to look into the problems associated with the preservation of frozen shrimps. (author)

  19. The Northern Marshall Islands radiological survey: A quality control program for radiochemical and gamma spectroscopy analysis

    International Nuclear Information System (INIS)

    Kehl, S.R.; Mount, M.E.; Robison, W.L.

    1995-09-01

    From 1979 to 1989, approximately 25,000 Post Northern Marshall Islands Radiological Survey (PNMIRS) samples were collected, and over 71,400 radiochemical and gamma spectroscopy analyses were performed to establish the concentration of 90 Sr, 137 Cs, 241 Am, and plutonium isotopes in soil, vegetation, fish, and animals in the Northern Marshall Islands. While the Low Level Gamma Counting Facility (B379) in the Health and Ecological Assessment (HEA) division accounted for over 80% of all gamma spectroscopy analyses, approximately 4889 radiochemical and 5437 gamma spectroscopy analyses were performed on 4784 samples of soil, vegetation, terrestrial animal, and marine organisms by outside laboratories. Four laboratories were used by Lawrence Livermore National Laboratory (LLNL) to perform the radiochemical analyses: Thermo Analytical Norcal, Richmond, California (TMA); Nuclear Energy Services, North Carolina State University (NCSU); Laboratory of Radiation Ecology, University of Washington (LRE); and Health and Ecological Assessment (HEA) division, LLNL, Livermore, California. Additionally, LRE and NCSU were used to perform gamma spectroscopy analyses. The analytical precision and accuracy were monitored by including blind duplicates and natural matrix standards in each group of samples analyzed. On the basis of reported analytical values for duplicates and standards, 88% of the gamma and 87% of the radiochemical analyses in this survey were accepted. By laboratory, 93% of the radiochemical analyses by TMA; 88% of the gamma-ray spectrometry and 100% of the radiochemistry analyses by NCSU; 89% of the gamma spectroscopy and 87% of the radiochemistry analyses by LRE; and 90% of the radiochemistry analyses performed by HEA's radiochemistry department were accepted

  20. Endoparasitos em cobaias (Cavia porcellus (Mammalia, Rodentia, Caviidae provenientes de biotérios de criação e experimentação do município do Rio de Janeiro, Brasil Endoparasites in guinea pigs (Cavia porcellus (Mammalia, Rodentia, Caviidae from breeding and experimentation animal housing of the municipality of Rio de Janeiro, Brazil

    Directory of Open Access Journals (Sweden)

    Luciana Casartelli Alves

    2007-10-01

    uncinata (34% and Giardia muris (24%. The prevalences of endoparasites found throught Ritchie's and Kinyoun's techniques in facility A were: E. caviae (74%, Balantidium sp. (68%, Cyathodinium sp. (68% and Cryptosporidium sp. (5%. In facility B: E. caviae (58%, Balantidium sp. (42%, Cyathodinium sp. (25% and G. muris (8% were found. The high prevalences in both facilities suggest that the efficacy of the sanitary barriers adopted in the prevention of parasitic infections should be revised.

  1. Nuclear material discovery or loss: the French experience

    International Nuclear Information System (INIS)

    Zanetti, S.H.

    2006-01-01

    In a nuclear facility, when a difference between the physical inventory listing and accountancy records is discovered, the French law (Article 11 of the 'Decret 81-512') requires a declaration to the High Civil Servant for Defence of the Ministry in charge of Industry. Moreover, according to article L.1333-13 of the Defence Code, in case of a suspicion of loss, theft or diversion of nuclear material, the licensee has to declare this event to the police. In the meantime, an investigation is carried out in the facility, and in cooperation with other facilities if necessary. These measures are aimed at: - Finding the lost nuclear material (if any), - Understand the causes of the problem, - Solve the differences by acting on the PIL or/and accountancy records, - Act to prevent any other occurrence of this kind of event. These actions can take place in the general field of a police investigation. After all these facts and information have been gathered, the licensee writes down a complete file which is transferred to the High Civil Servant for Defence of the Ministry in charge of Industry, in order to be analysed by his technical support body (IRSN). Thus, the IRSN is able to give its conclusion to the authority about this event, especially regarding: - The causes of the event, - Relevance and completeness of investigations, - Pertinence of the corrections, - Relevance of corrective actions, - Probability of another occurrence. This system is useful to ensure a complete follow-up of the events occurring in the various nuclear facilities in France, to have an extensive overview of the problems on a national scale. If an item is found in a facility A, numerous questions must be answered: - Where does it come from? - Since when is it in facility A? - How did it happened that this item has been transferred from facility B to facility A without the transfer of information? - We will consider these issues through examples. This kind of event can be potentially very rich in

  2. Technical Proposal Salton Sea Geothermal Power Pilot Plant Program

    Energy Technology Data Exchange (ETDEWEB)

    None

    1975-03-28

    The proposed Salton Sea Geothermal Power Pilot Plant Program comprises two phases. The objective of Phase 1 is to develop the technology for power generation from high-temperature, high-salinity geothermal brines existing in the Salton Sea known geothermal resources area. Phase 1 work will result in the following: (a) Completion of a preliminary design and cost estimate for a pilot geothermal brine utilization facility. (b) Design and construction of an Area Resource Test Facility (ARTF) in which developmental geothermal utilization concepts can be tested and evaluated. Program efforts will be divided into four sub-programs; Power Generation, Mineral Extraction, Reservoir Production, and the Area Resources Test Facility. The Power Generation Subprogram will include testing of scale and corrosion control methods, and critical power cycle components; power cycle selection based on an optimization of technical, environmental and economic analyses of candidate cycles; preliminary design of a pilot geothermal-electric generating station to be constructed in Phase 2 of this program. The Mineral Extraction Subprogram will involve the following: selection of an optimum mineral recovery process; recommendation of a brine clean-up process for well injection enhancement; engineering, construction and operation of mineral recovery and brine clean-up facilities; analysis of facility operating results from environmental, economical and technical point-of-view; preliminary design of mineral recovery and brine clean-up facilities of sufficient size to match the planned pilot power plant. The Reservoir Production Subprogram will include monitoring the operation and maintenance of brine production, handling and injection systems which were built with private funding in phase 0, and monitoring of the brine characteristics and potential subsidence effects during well production and injection. Based on the above, recommendations and specifications will be prepared for production and

  3. Tritium resources available for fusion reactors

    Science.gov (United States)

    Kovari, M.; Coleman, M.; Cristescu, I.; Smith, R.

    2018-02-01

    The tritium required for ITER will be supplied from the CANDU production in Ontario, but while Ontario may be able to supply 8 kg for a DEMO fusion reactor in the mid-2050s, it will not be able to provide 10 kg at any realistic starting time. The tritium required to start DEMO will depend on advances in plasma fuelling efficiency, burnup fraction, and tritium processing technology. It is in theory possible to start up a fusion reactor with little or no tritium, but at an estimated cost of 2 billion per kilogram of tritium saved, it is not economically sensible. Some heavy water reactor tritium production scenarios with varying degrees of optimism are presented, with the assumption that only Canada, the Republic of Korea, and Romania make tritium available to the fusion community. Results for the tritium available for DEMO in 2055 range from zero to 30 kg. CANDU and similar heavy water reactors could in theory generate additional tritium in a number of ways: (a) adjuster rods containing lithium could be used, giving 0.13 kg per year per reactor; (b) a fuel bundle with a burnable absorber has been designed for CANDU reactors, which might be adapted for tritium production; (c) tritium production could be increased by 0.05 kg per year per reactor by doping the moderator with lithium-6. If a fusion reactor is started up around 2055, governments in Canada, Argentina, China, India, South Korea and Romania will have the opportunity in the years leading up to that to take appropriate steps: (a) build, refurbish or upgrade tritium extraction facilities; (b) extend the lives of heavy water reactors, or build new ones; (c) reduce tritium sales; (d) boost tritium production in the remaining heavy water reactors. All of the alternative production methods considered have serious economic and regulatory drawbacks, and the risk of diversion of tritium or lithium-6 would also be a major concern. There are likely to be serious problems with supplying tritium for future

  4. Energy-Water Microgrid Case Study at the University of Arizona's BioSphere 2

    Science.gov (United States)

    Daw, J.; Macknick, J.; Kandt, A.; Giraldez, J.

    2016-12-01

    Microgrids can provide reliable and cost-effective energy services in a variety of conditions and locations. To date, there has been minimal effort invested in developing energy-water microgrids that demonstrate the feasibility and leverage the synergies associated with designing and operating renewable energy and water systems in a coordinated framework. Water and wastewater treatment equipment can be operated in ways to provide ancillary services to the electrical grid and renewable energy can be utilized to power water-related infrastructure, but the potential for co-managed systems has not yet been quantified or fully characterized. Co-management and optimization of energy and water resources could lead to improved reliability and economic operating conditions. Energy-water microgrids could be a promising solution to improve energy and water resource management for islands, rural communities, distributed generation, Defense operations, and many parts of the world lacking critical infrastructure.The National Renewable Energy Laboratory (NREL) and the University of Arizona have been jointly researching energy-water microgrid opportunities through an effort at the university's BioSphere 2 (B2) Earth systems science research facility. B2 is an ideal case study for an energy-water microgrid test site, given its size, its unique mission and operations, the existence and criticality of water and energy infrastructure, and its ability to operate connected-to or disconnected-from the local electrical grid. Moreover, the B2 is a premier facility for undertaking agricultural research, providing an excellent opportunity to evaluate connections and tradeoffs in the food-energy-water nexus. The research effort at B2 identified the technical potential and associated benefits of an energy-water microgrid through the evaluation of energy ancillary services and peak load reductions and quantified the potential for B2 water-related loads to be utilized and modified to provide

  5. SU-E-T-365: Estimation of Neutron Ambient Dose Equivalents for Radioprotection Exposed Workers in Radiotherapy Facilities Based On Characterization Patient Risk Estimation

    Energy Technology Data Exchange (ETDEWEB)

    Irazola, L; Terron, J; Sanchez-Doblado, F [Departamento de Fisiologia Medica y Biofisica, Universidad de Sevilla (Spain); Servicio de Radiofisica, Hospital Universitario Virgen Macarena, Sevilla (Spain); Domingo, C; Romero-Exposito, M [Departament de Fisica, Universitat Autonoma de Barcelona, Bellaterra (Spain); Garcia-Fuste, M [Health and Safety Department, ALBA Synchrotron Light Source, Cerdanyola del Valles (Spain); Sanchez-Nieto, B [Instituto de Fisica, Pontificia Universidad Catolica de Chile, Santiago (Chile); Bedogni, R [Laboratori Nazionali di Frascati, Istituto Nazionale di Fisica Nucleare (INFN) (Italy)

    2015-06-15

    Purpose: Previous measurements with Bonner spheres{sup 1} showed that normalized neutron spectra are equal for the majority of the existing linacs{sup 2}. This information, in addition to thermal neutron fluences obtained in the characterization procedure{sup 3}3, would allow to estimate neutron doses accidentally received by exposed workers, without the need of an extra experimental measurement. Methods: Monte Carlo (MC) simulations demonstrated that the thermal neutron fluence distribution inside the bunker is quite uniform, as a consequence of multiple scatter in the walls{sup 4}. Although inverse square law is approximately valid for the fast component, a more precise calculation could be obtained with a generic fast fluence distribution map around the linac, from MC simulations{sup 4}. Thus, measurements of thermal neutron fluences performed during the characterization procedure{sup 3}, together with a generic unitary spectra{sup 2}, would allow to estimate the total neutron fluences and H*(10) at any point{sup 5}. As an example, we compared estimations with Bonner sphere measurements{sup 1}, for two points in five facilities: 3 Siemens (15–23 MV), Elekta (15 MV) and Varian (15 MV). Results: Thermal neutron fluences obtained from characterization, are within (0.2–1.6×10{sup 6}) cm−{sup 2}•Gy{sup −1} for the five studied facilities. This implies ambient equivalent doses ranging from (0.27–2.01) mSv/Gy 50 cm far from the isocenter and (0.03–0.26) mSv/Gy at detector location with an average deviation of ±12.1% respect to Bonner measurements. Conclusion: The good results obtained demonstrate that neutron fluence and H*(10) can be estimated based on: (a) characterization procedure established for patient risk estimation in each facility, (b) generic unitary neutron spectrum and (c) generic MC map distribution of the fast component. [1] Radiat. Meas (2010) 45: 1391 – 1397; [2] Phys. Med. Biol (2012) 5 7:6167–6191; [3] Med. Phys (2015) 42

  6. DeSa News. No. 2, February 2006

    International Nuclear Information System (INIS)

    2006-02-01

    The international project on Evaluation and Demonstration of Safety during Decommissioning of Nuclear Facilities (DeSa Project) was launched in November 2004 with the aim of developing a harmonized methodology for the safety assessment of decommissioning activities, providing recommendations on a systematic regulatory review procedure and applying the graded approach in the development and review of safety assessments for decommissioning. Significant work has been accomplished since the first project meeting (1-5 November 2004) in the following main areas: a. Development of a draft Safety Report on Safety Assessment Methodologies for Decommissioning of Nuclear Facilities; b. Development of first draft documents on the Regulatory Review and Application of the Graded Approach to Safety Assessments for Decommissioning; c. Six nuclear facilities volunteered by Member States as candidates for the preparation of a selected number of test cases during Phase 2 of the DeSa Project; d. Presentation of the Project at three international events in Canada and USA; e. Promotion of the Project through the first DeSa newsletter and the Project website (http://wwwns.iaea.org/tech-areas/waste-safety/desa). The second DeSa Project meeting (17-21 October 2005) attracted forty-two experts from twenty-six countries with the aim to: - Review progress on the five DeSa Project working groups (WGs) [Assessment Framework and System Description, Hazard Analysis, Analysis of Results and Confidence Building, Regulatory Review and Graded Approach] activities; - Review the draft Safety Report on Safety Assessment Methodologies for Decommissioning of Nuclear Facilities, as revised by the Coordinating Group of the DeSa Project in June 2005; - Review progress and further develop recommendations on the regulatory review of safety assessments for decommissioning and the application of a graded approach to be used during the development and review of such assessments; - Develop the DeSa work plan

  7. Performance Assessment of a Low-Level Radioactive Waste Disposal Site using GoldSim Integrated Systems Model

    Science.gov (United States)

    Merrell, G.; Singh, A.; Tauxe, J.; Perona, R.; Dornsife, W.; grisak, G. E.; Holt, R. M.

    2011-12-01

    Texas Commission on Environmental Quality has approved licenses for four landfills at the Waste Control Specialists (WCS) site located in Andrews County, West Texas. The site includes a hazardous waste landfill and three landfills for radioactive waste. An updated performance assessment is necessary prior to acceptance of waste at the landfills. The updated performance assessment a) provides for more realistic and flexible dose modeling capabilities, b) addresses all plausible release and accident scenarios as they relate to the performance objectives, c) includes impact of climate and hydrologic scenarios that may impact long-term performance of the landfill, d) addresses impact of cover naturalization and degradation on the landfill, and e) incorporates uncertainty and sensitivity analysis for critical parameters. For the updated performance assessment, WCS has developed an integrated systems level performance assessment model using the GoldSim platform. GoldSim serves as a model for integrating all of the major components of a performance assessment, which include the radionuclide source term, facility design, environmental transport pathways, exposure scenarios, and radiological doses. Unlike many computer models that are based on first principles, GoldSim is a systems level model that can be used to integrate and abstract more complex sub-models into one system. This can then be used to assess the results into a unified model of the disposal system and environment. In this particular application, the GoldSim model consists of a) hydrogeologic model that simulates flow and transport through the Dockum geologic unit that underlies all of the waste facilities, b) waste cells that represent the containment unit and simulate degradation of waste forms, radionuclide leaching, and partitioning into the liquid and vapor phase within the waste unit, c) a cover system model that simulates upward diffusive transport from the underground repository to the atmosphere. In

  8. Quantitative Planetary Protection for Sample Return from Ocean Worlds

    Science.gov (United States)

    Neveu, Marc; Takano, Yoshinori; Porco, Carolyn; McKay, Christopher P.; Glavin, Daniel; Anbar, Ariel; Sherwood, Brent; Yano, Hajime

    2016-07-01

    the sample [undergoes] sterilization […], the sample container must be sealed [via] fail-safe containment with a method for verification of its operation before Earth return;" (B2) "for unsterilized samples, […] containment […] shall be maintained until [sample transfer to] an appropriate receiving facility;" (B3) "a method to 'break the chain of contact' with the target" be specified; (B4) "no uncontained hardware that contacted the target […] shall be returned to Earth;" (B5) "reviews and approval of the continuation of the flight mission shall be required [prior to] launch from Earth; leaving the target for return to Earth; and commitment to Earth reentry;" and (B6) "life detection and biohazard testing, or a proven sterilization process, shall be [a] precondition for the controlled distribution of […] the sample." These provisions and their means of evaluation could be quantified. A maximum leakage rate could be specified for particles above 10 nm (the size of prions, the smallest known pathogens [21]) (B1-B2), even for terminal velocity impact, whether unintended or otherwise (minimizing the risk of failure of reentry system elements, but requiring preservation of the samples and of sensors monitoring their thermal and structural integrity). For leak detection, He is commonly used [22], but its van-der-Waals radius of 0.14 nm could place too stringent a constraint for containment of pathogens over 70 times larger. To meet (B3)-(B4), uncontained parts in contact with ocean world material could be jettisoned prior to reentry with maximum probabilities of Earth/Moon impact, or of microbial survival upon reentry. (B6) could require either life detection prior to or after opening the sealed container [16,23-25], or sterilization [26]. Further guidance on (1) evaluating the 10 ^{-4} probability of forward contamination, (2) possibly extending this probability to ocean worlds other than Europa, (3) quantifying backward PP requirements, and (4) assessing the

  9. Limits to the Recognizability of Flaws in Non-Destructive Testing Steam-Generator Tubes for Nuclear-Power Plants; Limitations de l'Efficacite de la Detection des Defauts par Essais Non Destructifs de Tubes de Bouilleurs pour Centrales Nucleaires; Predely ehffektivnosti nedestruktivnoj defektoskopii trub parogeneratorov yadernykh ehlektrostantsij; Limites para Distinguir los Defectos en el Ensayo No Destructivo de Tubo para Generadores de Vapor Destinados a Centrales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Kuhlmann, A.; Adamsky, F. -J. [Technischer Ueberwachungs-Verein Reinland e.V., Cologne (Germany)

    1965-10-15

    In the Federal Republic of Germany there are nuclear reactors under construction with steam generators inside the reactor pressure-vessel. As a result design repairs of steam- generator tubes are very difficult and cause large shut-down times of the nuclear-power plant. It is known that numerous troubles in operating conventional power plants are results of steam-generator tube damages. Because of the high total costs of these reactors it. is necessary to construct the steam generators especially in such a manner that the load factor of the power plant is as high as possible. The Technischer Ueberwachungs-Verein Rheinland was charged to supervise and to test fabrication and construction of the steam generators to see that this part of the plant was as free of defects as possible. The experience gained during this work is of interest for manufacture and construction of steam generators for nuclear-power plants in general. This paper deals with the efficiency limits of non-destructive testing steam-generator tubes. The following tests performed will be discussed in detail: (a) Automatic ultrasonic testing of the straight tubes in the production facility; (b) Combined ultrasonic and radiographic testing of the bent tubes and tube weldings; (c) Other non-destructive tests. (author) [French] En Allemagne, on construit actuellement des generatrices nucleaires dans lesquelles les bouilleurs sont installes a l'interieur du caisson etanche du reacteur. Il s'ensuit que les reparations des tubes des bouilleurs sont tres difficiles et provoquent de longs arrets des centrales nucleaires. On sait que de nombreuses perturbations du fonctionnement des centrales classiques sont dues a des dommages dans les tubes des bouilleurs. C'est en grande partie en raison du prix de revient eleve de ces reacteurs qu'il est necessaire de construire les bouilleurs notamment de sorte que le facteur d'utilisation de la centrale soit aussi eleve que possible. C'est le ' Technischer Ueberwachungs

  10. Pressure-Fed LOX/LCH4 Reaction Control System for Spacecraft: Transient Modeling and Thermal Vacuum Hotfire Test Results

    Science.gov (United States)

    Atwell, Matthew J.; Hurlbert, Eric A.; Melcher, J. C.; Morehead, Robert L.

    2017-01-01

    An integrated cryogenic liquid oxygen, liquid methane (LOX/LCH4) reaction control system (RCS) was tested at NASA Glenn Research Center's Plum Brook Station in the Spacecraft Propulsion Research Facility (B-2) under vacuum and thermal vacuum conditions. The RCS is a subsystem of the Integrated Cryogenic Propulsion Test Article (ICPTA), a pressure-fed LOX/LCH4 propulsion system composed of a single 2,800 lbf main engine, two 28 lbf RCS engines, and two 7 lbf RCS engines. Propellants are stored in four 48 inch diameter 5083 aluminum tanks that feed both the main engine and RCS engines in parallel. Helium stored cryogenically in a composite overwrapped pressure vessel (COPV) flows through a heat exchanger on the main engine before being used to pressurize the propellant tanks to a design operating pressure of 325 psi. The ICPTA is capable of simultaneous main engine and RCS operation. The RCS engines utilize a coil-on-plug (COP) ignition system designed for operation in a vacuum environment, eliminating corona discharge issues associated with a high voltage lead. There are two RCS pods on the ICPTA, with two engines on each pod. One of these two engines is a heritage flight engine from Project Morpheus. Its sea level nozzle was removed and replaced by an 85:1 nozzle machined using Inconel 718, resulting in a maximum thrust of 28 lbf under altitude conditions. The other engine is a scaled down version of the 28 lbf engine, designed to match the core and overall mixture ratios as well as other injector characteristics. This engine can produce a maximum thrust of 7 lbf with an 85:1 nozzle that was additively manufactured using Inconel 718. Both engines are film-cooled and capable of limited duration gas-gas and gas-liquid operation, as well as steady-state liquid-liquid operation. Each pod contains one of each version, such that two engines of the same thrust level can be fired as a couple on opposite pods. The RCS feed system is composed of symmetrical 3/8 inch lines