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Analysis of the effects of corrosion probe on riser 241-AN-102-WST-16 during seismic event

Description: This analysis supports the installation activity of the corrosion probe in Tank 241-AN-102. The probe is scheduled to be installed in Riser 241-AN-102-WST-16 (formerly known as Riser 15B). The purpose of this analysis is to evaluate the potential effect of the corrosion probe on the riser during a credible seismic event. The previous analysis (HNF 1997a) considered only pump jet impingement loading.
Date: November 6, 1998
Creator: ZIADA, H.H.
Partner: UNT Libraries Government Documents Department

The National Facility physics and diagnostics

Description: This paper presents a description of the National Ignition Facility, some of the physics experiments that will be performed on it, and a description of some of the diagnostics needed to complete these experiments. Experiments are presented under the headings of: ignition physics, weapons physics or high-energy-density experimental science, weapons effects, and basic science and inertial fusion energy. The diagnostics discussed are primarily those that will be provided for early operation.
Date: August 6, 1999
Creator: Wootton, A.
Partner: UNT Libraries Government Documents Department

Acceptance test report, 241-SY-101 Flexible Receiver System, Phase 3 testing

Description: This document summarizes the results of the phase 3 acceptance test of the 241-SY-101 Flexible Receiver System (FRS). The purpose of this acceptance test is to verify the sealing integrity of the FRS to ensure that the release of waste and aerosols will be minimized during the removal of the test mixer pump from Tank 241-SY-101. The FRS is one of six major components of the Equipment Removal System, which has been designed to retrieve, transport, and store the mixer pump. This acceptance test was performed at the 306E Facility in the 300 area from January 10, 1995 to January 17, 1995. The Phase 3 test consisted of two parts. Part one was a water leak test of the seal between the blast shield and mock load distribution frame (LDF) to ensure that significant contamination of the pump pit and waste interaction with the aluminum impact-limiting material under the LDF are prevented during the pump removal operation. The second part of this acceptance test was an air leak test of the assembled flexible receiver system. The purpose of this test was to verify that the release of hazardous aerosols will be minimized if the tank dome pressure becomes slightly positive during the decontamination of the mixer pump.
Date: February 6, 1995
Creator: Ritter, G.A.
Partner: UNT Libraries Government Documents Department

KW basin backwash pit sludge measurement/video

Description: The purpose of this procedure is to gather visual and depth information and monitor underwater activities in the 105-KW SFBWP and transfer channel. Profile lighting (the use of lighting and shadows to show the surface contour) will be used to assess the contour of the sludge surface. Select measurements will also be taken to determine the actual sludge depth. The control/video station will be setup outside the radiation area or in lowest possible exposure area to reduce personnel exposure (ALARA). This procedure is to provide a mechanism to assist in fully characterizing the volume and surface topology of the sludge currently deposited in the sandfilter backwash pit (SFBWP). Surveillance Systems Engineering (SSE) personnel will gather visual information utilizing a closed circuit television (CCTV) color camera, mounted to stainless steel extension poles. Connections allow the camera to be connected with a pan and tilt to allow better positioning capabilities and to get good landscape profiling of the sediment surface. The information will be videotaped to a one-half inch NTSC or Y/C format. Underwater lighting will be accomplished by means of 500 watt underwater lamps.
Date: September 6, 1994
Creator: Dodd, E.N. Jr.
Partner: UNT Libraries Government Documents Department

Tank 241-Z-361 process and characterization history

Description: An Unreviewed Safety Question (Wagoner, 1997) was declared based on lack of adequate authorization basis for Tank 241-Z-361 in the 200W Area at Hanford. This document is a summary of the history of Tank 241-Z-361 through December 1997. Documents reviewed include engineering files, laboratory notebooks from characterization efforts, waste facility process procedures, supporting documents and interviews of people`s recollections of over twenty years ago. Records of transfers into the tank, past characterization efforts, and speculation were used to estimate the current condition of Tank 241-Z-361 and its contents. Information about the overall waste system as related to the settling tank was included to help in understanding the numbering system and process relationships. The Plutonium Finishing Plant was built in 1948 and began processing plutonium in mid-1949. The Incinerator (232-Z) operated from December 1961 until May 1973. The Plutonium Reclamation Facility (PRF, 236-Z) began operation in May 1964. The Waste Treatment Facility (242-Z) operated from August 1964 until August 1976. Waste from some processes went through transfer lines to 241-Z sump tanks. High salt and organic waste under normal operation were sent to Z-9 or Z-18 cribs. Water from the retention basin may have also passed through this tank. The transfer lines to 241-Z were numbered D-4 to D-6. The 241-Z sump tanks were numbered D-4 through D-8. The D-4, 5, and 8 drains went to the D-6 sump tank. When D-6 tank was full it was transferred to D-7 tank. Prior to transfer to cribs, the D-7 tank contents was sampled. If the plutonium content was analyzed to be more than 10 g per batch, the material was (generally) reprocessed. Below the discard limit, caustic was added and the material was sent to the cribs via the 241-Z-361 settling tank where solids settled out and the liquid overflowed by gravity ...
Date: August 6, 1998
Creator: Jones, S.A.
Partner: UNT Libraries Government Documents Department

Future algorithm research needs for partitioning in solid mechanics and coupled mechanical models

Description: Exceptional progress has been made in mathematical algorithm research leading to optimized mesh partitions for the highly unstructured grids occurring in finite element applications in solid mechanics. Today another research challenge presents itself. Research is needed to include boundary conditions into the algorithms for partitioning meshes. We describe below two methods we use currently to accomplish this and propose a more general approach be developed which would apply to our problems today as well as to the coupled models we envision for the future. Finally, we suggest research be considered that would incorporate partitioning methods into parallel mesh generation.
Date: October 6, 1997
Creator: Hoover, C. G.; DeGroot, A. J. & Sherwood, R. J.
Partner: UNT Libraries Government Documents Department

Design and Initial Development of Monolithic Cross-Flow Ceramic Hot-Gas Filters

Description: Advanced, coal-fueled, power generation systems utilizing pressurized fluidized bed combustion (PFBC) and integrated gasification combined cycle (IGCC) technologies are currently being developed for high-efficiency, low emissions, and low-cost power generation. In spite of the advantages of these promising technologies, the severe operating environment often leads to material degradation and loss of performance in the barrier filters used for particle entrapment. To address this problem, LoTEC Inc., and Oak Ridge National Laboratory are jointly designing and developing a monolithic cross-flow ceramic hot-gas filter. The filter concept involves a truly monolithic cross-flow design that is resistant to delamination, can be easily fabricated, and offers flexibility of geometry and material make-up. During Phase I of the program, a thermo-mechanical analysis was performed to determine how a cross-flow filter would respond both thermally and mechanically to a series of thermal and mechanical loads. The cross-flow filter mold was designed accordingly, and the materials selection was narrowed down to Ca{sub 0.5}Sr{sub 0.5}Zr{sub 4}P{sub 6}O{sub 24} (CS-50) and 2Al{sub 2}O{sub 3}-3SiO{sub 2} (mullite). A fabrication process was developed using gelcasting technology and monolithic cross-flow filters were fabricated. The program focuses on obtaining optimum filter permeability and testing the corrosion resistance of the candidate materials.
Date: June 6, 1999
Creator: Barra, C.; Limaye, S.; Stinton, D.P. & Vaubert, V.M.
Partner: UNT Libraries Government Documents Department

Nuclear Criticality Safety Department Qualification Program

Description: The Nuclear Criticality Safety Department (NCSD) is committed to developing and maintaining a staff of highly qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document defines the Qualification Program to address the NCSD technical and managerial qualification as required by the Y-1 2 Training Implementation Matrix (TIM). This Qualification Program is in compliance with DOE Order 5480.20A and applicable Lockheed Martin Energy Systems, Inc. (LMES) and Y-1 2 Plant procedures. It is implemented through a combination of WES plant-wide training courses and professional nuclear criticality safety training provided within the department. This document supersedes Y/DD-694, Revision 2, 2/27/96, Qualification Program, Nuclear Criticality Safety Department There are no backfit requirements associated with revisions to this document.
Date: September 6, 1996
Creator: Carroll, K.J.; Taylor, R.G. & Worley, C.A.
Partner: UNT Libraries Government Documents Department

ENRAF gauge reference level calculations

Description: This document describes the method for calculating reference levels for Enraf Series 854 Level Detectors as installed in the tank farms. The reference level calculation for each installed level gauge is contained herein.
Date: February 6, 1997
Creator: Huber, J.H., Fluor Daniel Hanford
Partner: UNT Libraries Government Documents Department

Predictive Models for the Determination of Pitting Corrosion Versus Inhibitor Concentrations and Temperature for Radioactive Sludge in Carbon Steel Waste Tanks

Description: Statistical models have been developed to predict the occurrence of pitting corrosion in carbon steel waste storage tanks exposed to radioactive nuclear waste. The levels of nitrite concentrations necessary to inhibit pitting at various temperatures and nitrate concentrations were experimentally determined via electrochemical polarization and coupon immersion corrosion tests. Models for the pitting behavior were developed based on various statistical analyses of the experimental data. Feed-forward Artificial Neural Network (ANN) models, trained using the Back-Propagation of Error Algorithm, more accurately predicted conditions at which pitting occurred than the logistic regression models developed using the same data.
Date: October 6, 1998
Creator: Mickalonis, J.I.
Partner: UNT Libraries Government Documents Department

Analysis of water from K west basin canisters (second campaign)

Description: Gas and liquid samples have been obtained from a selection of the approximately 3,820 spent fuel storage canisters in the K West Basin. The samples were taken to characterize the contents of the gas and water in the canisters. The data will provide source term information for two subprojects of the Spent Nuclear Fuel Project (SNFP) (Fulton 1994): the K Basins Integrated Water Treatment System subproject (Ball 1996) and the K Basins Fuel Retrieval System subproject (Waymire 1996). The barrels of ten canisters were sampled in 1995, and 50 canisters were sampled in a second campaign in 1996. The analysis results for the gas and liquid samples of the first campaign have been reported (Trimble 1995a; Trimble 1995b; Trimble 1996a; Trimble 1996b). An analysis of cesium-137 (137CS ) data from the second campaign samples was reported (Trimble and Welsh 1997), and the gas sample results are documented in Trimble 1997. This report documents the results of all analytes of liquid samples from the second campaign.
Date: March 6, 1997
Creator: Trimble, D.J., Fluor Daniel Hanford
Partner: UNT Libraries Government Documents Department

Tank waste remediation system baseline tank waste inventory estimates for fiscal year 1995

Description: A set of tank-by-tank waste inventories is derived from historical waste models, flowsheet records, and analytical data to support the Tank Waste Remediation System flowsheet and retrieval sequence studies. Enabling assumptions and methodologies used to develop the inventories are discussed. These provisional inventories conform to previously established baseline inventories and are meant to serve as an interim basis until standardized inventory estimates are made available.
Date: December 6, 1996
Creator: Shelton, L. W.
Partner: UNT Libraries Government Documents Department

Conceptual design report, plutonium stabilization and handling,project W-460

Description: Project W-460, Plutonium Stabilization and Handling, encompasses procurement and installation of a Stabilization and Packaging System (SPS) to oxidize and package for long term storage remaining plutonium-bearing special nuclear materials currently in inventory at the Plutonium Finishing Plant (PFP), and modification of vault equipment to allow storage of resulting packages of stabilized SNM for up to fifty years. This Conceptual Design Report (CDR) provides conceptual design details for the vault modification, site preparation and site interface with the purchased SPS. Two concepts are described for vault configuration; acceleration of this phase of the project did not allow completion of analysis which would clearly identify a preferred approach.
Date: March 6, 1997
Creator: Weiss, E.V.
Partner: UNT Libraries Government Documents Department

Tank 241-BX-106: Tank characterization plan

Description: This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, and WHC 222-S Laboratory. Scope of this plan is to provide guidance for sampling and analysis of samples for tank 241-BX-106. (Waste from this tank shall be transferred to a double-shell tank.)
Date: March 6, 1995
Creator: Schreiber, R.D.
Partner: UNT Libraries Government Documents Department

Exploring the Role of Shear Stress and Severe Turbulence in Downstream Fish Passage

Description: Fish may be exposed to damaging levels of fluid shear stress and turbulence while passing through hydroelectric power plants. The generally assumed locations for such potential damage are the turbine and draft tube passages, although it is possible that fish are also injured during passage over the spillway or through sluiceways and fish bypass outfalls. Unless mitigated, fluid-induced injuries and mortality could frustrate efforts to develop advanced, fish-friendly turbines or to provide safe alternate downstream passages. The effects of shear stress and turbulence on fish are poorly understood, in part because of the difficulties in conceptualizing these phenomena, determining their magnitudes and distribution within hydroelectric systems, and then recreating them in a controlled laboratory environment. We define the fluid phenomena that are relevant to the assessment of effects on fish. The magnitudes of fluid stresses associated with man-altered aquatic environments are often considerably higher than those found in natural environments (e.g., normal river flows). However, levels of shear stresses that occur during flash floods appear to be comparable to those expected within a turbine. Past studies of the effects of shear stress on fish are of limited value, mainly because of their narrow scope and lack of instrumentation to measure velocities on appropriately small scales. A laboratory experiment to study the effects of shear stress and turbulence on fish is described.
Date: July 6, 1999
Creator: Cada, G.; Carlson, T.; Ferguson, J.; Richmond, M. & Sale, M.
Partner: UNT Libraries Government Documents Department

Statistical analysis of oxidation rates for K Basin fuel in dry air

Description: Test data from oxidation of K Basin fuel (SNF) samples in dry air were reviewed, and linear reaction rates were derived on a time-average basis. The derived rates were compared to literature data for unirradiated uranium in dry air using rate law of the form log(rate) = a + b (I/T). The analyses found differences between the SNF data and the literature data. Oxidation rate below 150 C was higher for K Basin fuel than for unirradiated uranium.
Date: February 6, 1998
Creator: Trimble, D.J.
Partner: UNT Libraries Government Documents Department

Engineering task plan for AX-104 residual waste volume and inventory data collection

Description: The purpose of this Engineering Task Plan is to document the strategy, equipment and responsibilities of the tasks required to preform the volume and inventory data collection of tank AX-104. The project is a part of the Hanford Tanks Initiative Plan document number WHC-SD-WM-PMP-022 Revision D.
Date: March 6, 1997
Creator: Boechler, G. N.
Partner: UNT Libraries Government Documents Department

Acceptance test report for the Westinghouse 100 ton hydraulic trailer

Description: The SY-101 Equipment Removal System 100 Ton Hydraulic Trailer was designed and built by KAMP Systems, Inc. Performance of the Acceptance Test Procedure at KAMP`s facility in Ontario, California (termed Phase 1 in this report) was interrupted by discrepancies noted with the main hydraulic cylinder. The main cylinder was removed and sent to REMCO for repair while the trailer was sent to Lampson`s facility in Pasco, Washington. The Acceptance Test Procedure was modified and performance resumed at Lampson (termed Phase 2 in this report) after receipt of the repaired cylinder. At the successful conclusion of Phase 2 testing the trailer was accepted as meeting all the performance criteria specified.
Date: March 6, 1995
Creator: Barrett, R.A.
Partner: UNT Libraries Government Documents Department

Initial recommendations for restricting gamma-ray spectrometry measurements of radionuclides for on-site inspections

Description: The US paper �Radionuclide Sampling, Sample Handling and Analytical Laboratory Equipment for Comprehensive Test Ban Treaty On-Site Inspections,� CTBT/PC/V/OSI/WSII/PR/29 identified the radionuclides of interest to an OS1 as <sup>144</sup>Ce, <sup>147</sup>Nd, <sup>141</sup>Ce, <sup>149</sup>Ba<sup>140</sup>La), <sup>95</sup> Zr(<sup>95</sup>Nb), <sup>131m</sup>Xe, <sup>133m</sup>Xe, <sup>133g</sup>Xe, <sup>135g</sup>Xe, and <sup>37</sup>Ar. All of these nuclides (except <sup>37</sup>Ar) can be measured via some form of conventional or coincidence-based gamma-ray spectrometry. The non-gaseous radionuclides [<sup>144</sup>Ce, <sup>147</sup>Nd, <sup>141</sup>Ce, <sup>140</sup>Ba(<sup>140</sup>La), and <sup>95</sup>Zr(<sup>95</sup>Nb)] can be measured via conventional high-resolution gamma-ray spectrometry using a shielded, high-purity germanium (HPGe) detector. The gaseous radionuclides <sup>131m</sup>Xe, <sup>133m</sup>Xe, <sup>133g</sup>Xe, and <sup>135g</sup>Xe are best measured (after separation from their homologous elements) via a gamma & beta/electron coincidence technique such as that described in CTBT/WGB/TL-11/5 which could utilize either a HPGe or low-resolution (NaI(TI)) gamma-ray spectrometer to detect the gamma-ray/x-ray and a plastic scintillator to detect the beta particle/electron from the decay of the various Xe isotopes. The US paper CTBT/PC/V/IOSI/WSII/PR/29 (and other papers) identified a need to limit the information that can be extracted from high-resolution gamma-ray spectra to ensure that only information relevant to an OSI is accessible. The term �blinding� has been used to describe the need to limit the information available to the Inspection Team from the high-resolution gamma-ray measurement. A better term is �measurement restriction�; the need for restricting the information is particularly relevant to conventional high-resolution gamma-ray spectrometry measurements, but not to the gamma & beta/electron coincidence-type measurements envisioned for Xe isotopes because the separation process for these radionuclides will likely eliminate any other observables. The purpose of this paper is to define functional requirements for restricting measurements via conventional high- resolution gamma-ray spectrometry systems to ensure that only the nuclides of interest to an OSI can be identified and quantified. Options discussed below include 1) acquisition and analysis of the entire high-resolution gamma-ray spectrum combined with ...
Date: November 6, 1998
Creator: Buckley, W. F.; Kreek, S. A. & Wild, J. F.
Partner: UNT Libraries Government Documents Department

CSER-025: PFP storage of 9.25 inch tall, 4.4 kg Pu cans on existing vault four pedestals

Description: A nuclear criticality safety analysis has been performed to increase the approved plutonium mass limit for cans stored in Vault {number_sign}4 cubicles at PFP. The cubicles were approved to hold up to 2.5 kg of plutonium on each pedestal. The purpose of this CSER is to accommodate the storage of 4.4 kg of plutonium in PuO, (5.0 kg PuO,) in Vault {number_sign}4 cubicles. The highest k{sub eff} calculated for all possible scenarios is 0.868 + 0.003 when every other cubicle is left vacant, which is well below the criticality safety limit of k{sub eff}=0.935. Consequently, an increase of plutonium mass to 4.4 kg per can is within acceptable safety limits for this configuration.
Date: February 6, 1997
Creator: Hillesland, K.E., Fluor Daniel Hanford
Partner: UNT Libraries Government Documents Department

PRELIMINARY DESIGN OF THE BEAM LOSS MONITORING SYSTEM FOR THE SNS.

Description: The SNS to be built at Oak Ridge National Laboratory will provide a high average intensity 1 GeV beam to produce spallation neutrons. Loss of a even small percentage of this intense beam would result in high radiation. The Beam Loss Monitor (ELM) system must detect such small, long term losses yet be capable of measuring infrequent short high losses. The large dynamic range presents special problems for the system design. Ion chambers will be used as the detectors. A detector originally designed for the FNAL Tevatron, was considered but concerns about ion collection times and low collection efficiency at high loss rates favor a new design. The requirements and design concepts of the proposed approach will be presented. Discussion of the design and testing of the ion chambers and the analog j-Point end electronics will be presented. The overall system design will be described.
Date: May 6, 2002
Creator: WITKOVER,R. & GASSNER,D.
Partner: UNT Libraries Government Documents Department

Electroproduction of Photons and of Pawns on the Proton in Quadrimoment of Transfer Q2=1.0GeV2. Measure Cross Sections and Extraction of Polarizabilities Generalities; Electroproduction de Photons et de Pions sur le Proton au Quadrimoment de Transfert Q2=1.0GeV2. Mesure des Sections Efficaces et Extraction des Polarisabilites Generalisees

Description: In hadronic physics, the nucleon structure and the quarks confinement are still topical issues. The neutral pion electroproduction and virtual Compton scattering (VCS) reactions allow us to access new observables that describe this structure. This work is focused on the VCS experiment performed at Jefferson Lab in 1998.
Date: November 6, 2001
Creator: Laveissiere, Geraud
Partner: UNT Libraries Government Documents Department

Inverse Bremsstrahlung Stabilization of Noise in the Generation of Ultra-short Intense Pulses by Backward Raman Amplification

Description: Inverse bremsstrahlung absorption of the pump laser beam in a backward Raman amplifier over the round-trip light transit time through the sub-critical density plasma can more than double the electron temperature of the plasma and produce time-varying axial temperature gradients. The resulting increased Landau damping of the plasma wave and detuning of the resonance can act to stabilize the pump against unwanted amplification of Langmuir noise without disrupting nonlinear amplification of the femtosecond seed pulse. Because the heating rate increases with the charge state Z, only low-Z plasmas (hydrogen, helium, or helium-hydrogen mixtures) will maintain a low enough temperature for efficient operation.
Date: November 6, 2003
Creator: Berger, Richard L.; Solodov, Daniel S. Clark Andrei; Valeo, Ernest J. & Fisch, Nathaniel J.
Partner: UNT Libraries Government Documents Department