The Experts below are selected from a list of 168 Experts worldwide ranked by ideXlab platform

Reynolds James - One of the best experts on this subject based on the ideXlab platform.

  • MULTI-POLLUTANT CONTROL USING MEMBRANE--BASED UP-FLOW WET ELECTROSTATIC PRECIPITATION
    Croll-Reynolds Clean Air Technologies (United States), 2004
    Co-Authors: Reynolds James
    Abstract:

    This is the Final Report of the ''Multi-Pollutant Control Using Membrane-Based Up-flow Wet Electrostatic Precipitation'' project funded by the US Department of Energy's National Energy Technology Laboratory under DOE Award No. DE-FC26-02NT41592 to Croll-Reynolds Clean Air Technologies (CRCAT). In this 18 month project, CRCAT and its team members conducted detailed emission tests of metallic and new membrane collection material within a wet electrostatic precipitator (WESP) at First Energy's Penn Power's Bruce Mansfield (BMP) plant in Shippingport, Pa. The Membrane WESP was designed to be as similar as the metallic WESP in terms of collection area, air-flow, and electrical characteristics. Both units are two-field units. The membrane unit was installed during the 2nd and 3rd quarters of 2003. Testing of the metallic unit was performed to create a baseline since the Mansfield plant had installed selective catalytic reduction equipment for NOx control and a sodium bisulfate injection system for SO3 control during the spring of 2003. Tests results on the metallic WESP were consistent with previous testing for PM2.5, SO3 mist and mercury. Testing on the membrane WESP demonstrated no adverse impact and equivalent removal efficiencies as that of the metallic WESP. Testing on both units was performed at 8,000 acfm and 15,000 acfm. Summary results are shown

  • MULTI-POLLUTANT CONTROL USING MEMBRANE--BASED UP-FLOW WET ELECTROSTATIC PRECIPITATION
    Croll-Reynolds Clean Air Technologies (United States), 2003
    Co-Authors: Reynolds James
    Abstract:

    This is the second quarterly report of the ''Multi-Pollutant Control Using Membrane-Based Upflow Wet Electrostatic Precipitation'' project funded by the US Department of Energy's National Energy Technology Laboratory under DOE Award No. DE-FC26-02NT41592 to Croll-Reynolds Clean Air Technologies (CRCAT). In this 18 month project, CRCAT and its team members will conduct detailed emission tests of metallic and new membrane collection material within a wet electrostatic precipitator (WESP) at First Energy's Penn Power's Bruce Mansfield (BMP) plant in Shippingport, Pa. Test results performed on the existing metallic WESP during November of 2002 showed consistent results with previous test results. Average collection efficiency of 89% on SO{sub 3} mist was achieved. Additionally, removal efficiencies of 62% were achieved at very high velocity, greater than 15 ft./sec. During the first quarter of 2003 final design and start of fabrication of the membrane wet ESP was undertaken

  • MULTI-POLLUTANT CONTROL USING MEMBRANE-BASED UP-FLOW WET ELECTROSTATIC PRECIPITATION
    Croll-Reynolds Clean Air Technologies (United States), 2003
    Co-Authors: Reynolds James
    Abstract:

    This is the first quarterly report of the ''Multi-Pollutant Control Using Membrane--Based Upflow Wet Electrostatic Precipitation'' project funded by the US Department of Energy's National Energy Technology Laboratory under DOE Award No. DE-FC26-02NT41592 to Croll-Reynolds Clean Air Technologies (CRCAT). In this 18 month project, CRCAT and its team members will conduct detailed emission tests of metallic and new membrane collection material within a wet electrostatic precipitator (WESP) at First Energy's Penn Power's Bruce Mansfield (BMP) plant in Shippingport, Pa. Test results performed on the existing metallic WESP during November of 2002 showed consistent results with previous test results. Average collection efficiency of 89% on SO{sub 3} mist was achieved. Additionally, removal efficiencies of 62% were achieved at very high velocity, greater than 15 ft./sec

Johnson D.m. - One of the best experts on this subject based on the ideXlab platform.

  • Shippingport Spent Fuel Canister System Description
    Fluor Hanford Inc., 2000
    Co-Authors: Johnson D.m.
    Abstract:

    In 1978 and 1979, a total of 72 blanket fuel assemblies (BFAs), irradiated during the operating cycles of the Shippingport Atomic Power Station's Pressurized Water Reactor (PWR) Core 2 from April 1965 to February 1974, were transferred to the Hanford Site and stored in underwater storage racks in Cell 2R at the 221-T Canyon (T-Plant). The initial objective was to recover the produced plutonium in the BFAs, but this never occurred and the fuel assemblies have remained within the water storage pool to the present time. The Shippingport Spent Fuel Canister (SSFC) is a confinement system that provides safe transport functions (in conjunction with the TN-WHC cask) and storage for the BFAs at the Canister Storage Building (CSB). The current plan is for these BFAs to be retrieved from wet storage and loaded into SSFCs for dry storage. The sealed SSFCs containing BFAs will be vacuum dried, internally backfilled with helium, and leak tested to provide suitable confinement for the BFAs during transport and storage. Following completion of the drying and inerting process, the SSFCs are to be delivered to the CSB for closure welding and long-term interim storage. The CSB will provide safe handling and dry storage for the SSFCs containing the BFAs. The purpose of this document is to describe the SSFC system and interface equipment, including the technical basis for the system, design descriptions, and operations requirements. It is intended that this document will be periodically updated as more equipment design and performance specification information becomes available

  • Shippingport Spent Fuel Canister (SSFC) Design Report Project W-518
    Fluor Hanford Inc., 2000
    Co-Authors: Johnson D.m.
    Abstract:

    The SSFC Design Report Describes A spent fuel canister for Shippingport Core 2 blanket fuel assemblies. The design of the SSFC is a minor modification of the MCO. The modification is limited to the Shield Plug which remains unchanged with regard to interfaces with the canister shell. The performance characteristics remain those for the MCO, which bounds the payload of the SSFC

D.b. Illum - One of the best experts on this subject based on the ideXlab platform.

  • Fuel Summary Report: Shippingport Light Water Breeder Reactor - Rev. 2
    2002
    Co-Authors: G.l. Olson, Richard Keith Mc Cardell, D.b. Illum
    Abstract:

    The Shippingport Light Water Breeder Reactor (LWBR) was developed by Bettis Atomic Power Laboratory to demonstrate the potential of a water-cooled, thorium oxide fuel cycle breeder reactor. The LWBR core operated from 1977-82 without major incident. The fuel and fuel components suffered minimal damage during operation, and the reactor testing was deemed successful. Extensive destructive and nondestructive postirradiation examinations confirmed that the fuel was in good condition with minimal amounts of cladding deformities and fuel pellet cracks. Fuel was placed in wet storage upon arrival at the Expended Core Facility, then dried and sent to the Idaho Nuclear Technology and Engineering Center for underground dry storage. It is likely that the fuel remains in good condition at its current underground dry storage location at the Idaho Nuclear Technology and Engineering Center. Reports show no indication of damage to the core associated with shipping, loading, or storage

  • Fuel Summary Report: Shippingport Light Water Breeder Reactor
    1999
    Co-Authors: D.b. Illum, G.l. Olson, R.k. Mccardell
    Abstract:

    The Shippingport Light Water Breeder Reactor (LWBR) was developed by Bettis Atomic Power Laboratory to demonstrate the potential of a water-cooled, thorium oxide fuel cycle breeder reactor. The LWBR core operated from 1977-82 without major incident. The fuel and fuel components suffered minimal damage during operation, and the reactor testing was deemed successful. Extensive destructive and nondestructive postirradiation examinations confirmed that the fuel was in good condition with minimal amounts of cladding deformities and fuel pellet cracks. Fuel was placed in wet storage upon arrival at the Expended Core Facility, then dried and sent to the Idaho Nuclear Technology and Engineering Center for underground dry storage. It is likely that the fuel remains in good condition at its current underground dry storage location at the Idaho Nuclear Technology and Engineering Center. Reports show no indication of damage to the core associated with shipping, loading, or storage.

Davis J.w. - One of the best experts on this subject based on the ideXlab platform.

  • Disposal of Shippingport LWBR spent Nuclear Fuel in Yucca Mountain: Waste Package Internal Criticality Analysis
    United States. Department of Energy. Yucca Mountain Project Office., 2000
    Co-Authors: Radulescu H.r., Davis J.w.
    Abstract:

    The paper presents the disposal criticality analysis for the Shippingport Light Water Breeder Reactor (LWBR) spent nuclear fuel (SNF) being considered for disposal at the potential Yucca Mountain repository. The methodology for disposal criticality analysis includes the evaluation of the potential configurations--intact through degraded--based on the supporting analyses of the physical and geochemical processes that degrade the fuel over time

  • Volumes, Masses, and Surface Areas for Shippingport LWBR Spent Nuclear Fuel in a DOE SNF Canister
    'Office of Scientific and Technical Information (OSTI)', 1999
    Co-Authors: Davis J.w.
    Abstract:

    The purpose of this calculation is to estimate volumes, masses, and surface areas associated with (a) an empty Department of Energy (DOE) 18-inch diameter, 15-ft long spent nuclear fuel (SNF) canister, (b) an empty DOE 24-inch diameter, 15-ft long SNF canister, (c) Shippingport Light Water Breeder Reactor (LWBR) SNF, and (d) the internal basket structure for the 18-in. canister that has been designed specifically to accommodate Seed fuel from the Shippingport LWBR. Estimates of volumes, masses, and surface areas are needed as input to structural, thermal, geochemical, nuclear criticality, and radiation shielding calculations to ensure the viability of the proposed disposal configuration

G.l. Olson - One of the best experts on this subject based on the ideXlab platform.

  • Fuel Summary Report: Shippingport Light Water Breeder Reactor - Rev. 2
    2002
    Co-Authors: G.l. Olson, Richard Keith Mc Cardell, D.b. Illum
    Abstract:

    The Shippingport Light Water Breeder Reactor (LWBR) was developed by Bettis Atomic Power Laboratory to demonstrate the potential of a water-cooled, thorium oxide fuel cycle breeder reactor. The LWBR core operated from 1977-82 without major incident. The fuel and fuel components suffered minimal damage during operation, and the reactor testing was deemed successful. Extensive destructive and nondestructive postirradiation examinations confirmed that the fuel was in good condition with minimal amounts of cladding deformities and fuel pellet cracks. Fuel was placed in wet storage upon arrival at the Expended Core Facility, then dried and sent to the Idaho Nuclear Technology and Engineering Center for underground dry storage. It is likely that the fuel remains in good condition at its current underground dry storage location at the Idaho Nuclear Technology and Engineering Center. Reports show no indication of damage to the core associated with shipping, loading, or storage

  • Fuel Summary Report: Shippingport Light Water Breeder Reactor
    1999
    Co-Authors: D.b. Illum, G.l. Olson, R.k. Mccardell
    Abstract:

    The Shippingport Light Water Breeder Reactor (LWBR) was developed by Bettis Atomic Power Laboratory to demonstrate the potential of a water-cooled, thorium oxide fuel cycle breeder reactor. The LWBR core operated from 1977-82 without major incident. The fuel and fuel components suffered minimal damage during operation, and the reactor testing was deemed successful. Extensive destructive and nondestructive postirradiation examinations confirmed that the fuel was in good condition with minimal amounts of cladding deformities and fuel pellet cracks. Fuel was placed in wet storage upon arrival at the Expended Core Facility, then dried and sent to the Idaho Nuclear Technology and Engineering Center for underground dry storage. It is likely that the fuel remains in good condition at its current underground dry storage location at the Idaho Nuclear Technology and Engineering Center. Reports show no indication of damage to the core associated with shipping, loading, or storage.