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Transportable Xenon Laboratory (TXL-1) Operations Manual
The Transportable Xenon Laboratory Operations Manual is a guide to set up and shut down TXL, a fully contained laboratory made up of instruments to identify and measure concentrations of the radioactive isotopes of xenon by taking air samples and analyzing them. The TXL is housed in a standard-sized shipping container. TXL can be shipped to and function in any country in the world.
Date:
March 7, 2011
Creator:
Thompson, Robert C.; Stewart, Timothy L.; Willett, Jesse A. & Woods, Vincent T.
Object Type:
Report
System:
The UNT Digital Library
Technical specification for the 1.5 Tesla superconducting solenoid for the BaBar detector. Revision 1
This document sets forth the specification of the BABAR superconducting solenoid and power supply which is being supplied to the BABAR collaboration by INSTITUTO NAZIONALE DI FISICA NUCLEARE (INFN). The solenoid will be installed in the BABAR detector which will be located at Interaction Region 2 (IR2) of the PEP II machine, a positron electron collider, presently under construction at the Stanford Linear Accelerator Center (SLAC) located in Menlo Park, California. The solenoid will become part of the BABAR detector which will be used in SLAC`s high energy physics program. Intense beams of electrons and positrons are made to collide inside the solenoid magnet. High field uniformity quality, precise mechanical alignment and long term stability are essential characteristics of the solenoid. INFN will set up a committee that will provide contractual and technical oversight throughout the design, fabrication and installation phases of the BABAR solenoid construction. That committee will be the final authority to resolve any differences between these specifications and the INFN supplied drawings, in addition to any differences between these specifications or the INFN supplied drawings and the proposals from the vendor. All submissions for approval to INFN whether for design changes, material approval, design submissions or others …
Date:
March 7, 1997
Creator:
O`Connor, T. G.; Bell, R.; Fabbricatore, P.; Giorgi, M. & Hitlin, D.
Object Type:
Report
System:
The UNT Digital Library
FAST FLUX TEST FACILITY MONTHLY INFORMAL TECHNICAL PROGRESS REPORT FEBRUARY 1969
This report was prepared by Battelle-Northwest under Contract No. AT (45-1)-1830 for the Atomic Energy Commission, Division of Reactor Development and Technology, to summarize technical progress made in the Fast Flux Test Facility Program during February 1969.
Date:
March 7, 1969
Creator:
Astley, E. R.
Object Type:
Report
System:
The UNT Digital Library
Computer-aided analysis of eddy current rotating probe data.
Eddy current (EC) estimate of flaw size obtained from inservice inspection is often the primary means of assessing the structural integrity of steam generator tubes. Reliable prediction of failure pressure and leak rate in tubes with complex cracking requires more detailed information about the geometry and extent of degradation than is generally available from conventional bobbin coil examinations. High-resolution inspections with EC rotating probes are thus carried out on selected regions of tubing to provide the more extensive nondestructive evaluation (NDE) information that is needed to better assess flaw size and distribution. Interpretation of signals from complex cracking that are often distorted by coherent and incoherent noise can be a challenging NDE task. Studies at Argonne National Laboratory have demonstrated that computer-aided data analysis can be used for more accurate and efficient processing of the large amounts of data collected by such probes. The basic structure of a rule-based multiparameter data analysis algorithm is described in this paper. Multiple-frequency inspection data from a standard rotating pancake coil were used for the analyses. The codes were implemented as MATLAB scripts and provide, as the final outcome, profiles of flaw depth in a section of tube. Graphical user interface tools were devised …
Date:
March 7, 2002
Creator:
Bakhtiari, S.; Park, J. Y.; Kupperman, D. S. & Shack, W. J.
Object Type:
Article
System:
The UNT Digital Library
N-Reactor Department monthly report, February 1963
This report details activities of the N-Reactor Department during the month of February 1963.
Date:
March 7, 1963
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Supporting calculations and assumptions for use in WESF safetyanalysis
This document provides a single location for calculations and assumptions used in support of Waste Encapsulation and Storage Facility (WESF) safety analyses. It also provides the technical details and bases necessary to justify the contained results.
Date:
March 7, 1997
Creator:
Hey, B.E.
Object Type:
Report
System:
The UNT Digital Library
Graphite Irradiations at the Brookhaven Liquid Nitrogen Irradiation Facility
None
Date:
March 7, 1955
Creator:
Deegan, G. E.
Object Type:
Report
System:
The UNT Digital Library
Tools and Tool Support for the Exascale Era
None
Date:
March 7, 2011
Creator:
Schulz, M
Object Type:
Report
System:
The UNT Digital Library
Plutonium Disposition by Immobilization
The ultimate goal of the Department of Energy (DOE) Immobilization Project is to develop, construct, and operate facilities that will immobilize between 17 to 50 tonnes (MT) of U.S. surplus weapons-usable plutonium materials in waste forms that meet the ''spent fuel'' standard and are acceptable for disposal in a geologic repository. Using the ceramic can-in-canister technology selected for immobilization, surplus plutonium materials will be chemically combined into ceramic forms which will be encapsulated within large canisters of high level waste (HLW) glass. Deployment of the immobilization capability should occur by 2008 and be completed within 10 years. In support of this goal, the DOE Office of Fissile Materials Disposition (MD) is conducting development and testing (D&T) activities at four DOE laboratories under the technical leadership of Lawrence Livermore National Laboratory (LLNL). The Savannah River Site has been selected as the site for the planned Plutonium Immobilization Plant (PIP). The D&T effort, now in its third year, will establish the technical bases for the design, construction, and operation of the U. S. capability to immobilize surplus plutonium in a suitable and cost-effective manner. Based on the D&T effort and on the development of a conceptual design of the PIP, automation is …
Date:
March 7, 2000
Creator:
Gould, T.; DiSabatino, A. & Mitchell, M.
Object Type:
Article
System:
The UNT Digital Library
Review of monitoring instruments for transuranics in fuel fabrication and reprocessing plants. A progress report to the physical and technological programs, Division of Biomedical and Environmental Research, U. S. Energy Research and Development Administration
None
Date:
March 7, 1977
Creator:
Kordas, J. F. & Phelps, P. L.
Object Type:
Report
System:
The UNT Digital Library
A review of incentives, strategies and model technologies for recycling photovoltaic modules
This paper identifies existing recycling programs for consumer products with similar composition to photovoltaic (PV) modules, including cathode-ray tubes, electronic circuit boards, batteries, and automobile windshield glass. Discussed are incentives, the selection of technologies, and strategies used to recycle these products. Since the technologies for recycling these products exist, developing a process, or series of processes, for PV modules should primarily be a matter of customization. Developing an entire recycling program that is economically feasible will provide a greater challenge. Achieving this will require careful analysis of incentives, use of various combinations of strategies, and inclusion of multiple industries for additional technical processes. This can contribute to the success of a program by dividing the costs and ensuring that secondary products and materials enter into a diverse amount of markets.
Date:
March 7, 1994
Creator:
DePhillips, M.P. & Moskowitz, P.D.
Object Type:
Report
System:
The UNT Digital Library
Development and Implementation of an Ergonomics Program for Research Laboratories
None
Date:
March 7, 2006
Creator:
Roberts, T.; Yu, E. & Herbert, R.
Object Type:
Article
System:
The UNT Digital Library
Closed out Tank 241-SY-101 DACS system change request {number_sign}1--100
This report is a compilation of system change requests processed during the development of the Data Acquisition and Control System for the Tank 241-SY-101 hydrogen mitigation project. Tank 241-SY-101 is on the Hydrogen Watch List. The disposition of the request, date the change was installed, date verified, and whether an Acceptance Test Procedure was required and completed are described for each request change.
Date:
March 7, 1995
Creator:
Gauck, G. J.
Object Type:
Report
System:
The UNT Digital Library
Fuels Preparation Department monthly report, February 1961
This document details activities of the Fuels Preparation Department during the month of February 1961. (FI)
Date:
March 7, 1961
Creator:
Dickeman, R. L.
Object Type:
Report
System:
The UNT Digital Library
Phase I chemical speciation modeling of stream mixing in the LAW/HLW Envelope A Treatment
The intent of this work was to provide a first approximation of the effect of stream mixing and waste stream composition on precipitation.
Date:
March 7, 2000
Creator:
Kaplan, D.I.
Object Type:
Report
System:
The UNT Digital Library
Characterization of Microbial Communities in TCE-Contaminated Seep Zone Sediments
Hundreds of sites across the United States contain trichloroethene (TCE) contamination, including the Department of Energy's Savannah River Site (SRS) in Aiken, South Carolina. Previous studies have indicated that microorganisms are capable of efficiently degrading TCE to nonhazardous end products. In this project, molecular and growth based methods were used for microbial characterization of a TCE impacted seepzone where TCE degradation is naturally occurring. The results from this work provide clear evidence that the SRB may play a significant role in TCE degradation along the Twin Lakes seepline.
Date:
March 7, 2005
Creator:
ROBIN, BRIGMON
Object Type:
Article
System:
The UNT Digital Library
CSER 95-002: ALARA shielding for IAEA SNM container movement
This CSER qualifies use of a 5% borated, lead foil lined polyethylene 1 inch annulus as a bucket and in a small carrier to move sealed containers of plutonium. The containers are Oversize Cans or smaller containing plutonium limited in mass and H/Pu ratio by PFP storage and transportation CPS`s. These ALARA shielding units reduce personnel exposure to the radiation from the containers as they are moved for assay and other required activities.
Date:
March 7, 1995
Creator:
Miller, E. M.
Object Type:
Report
System:
The UNT Digital Library
Fuels Preparation Department monthly report, February 1962
This document details activities of the Fuels Preparation Department during the month of February 1962.
Date:
March 7, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
RFI/RI work plan for the Road A Chemical Basin 904-111G
This Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI)/Remedial Investigation (RI) Work Plan has been prepared for the Road A Chemical Basin Operable Unit (RdACB OU) (904-111G). This unit is subject to the requirements of both RCRA and the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). This Work Plan presents the initial evaluation of existing unit data, applicable background data, the regulatory framework for the unit investigation, and the evaluations and decisions made during the determination of the scope and objectives of the planned Remedial Investigation/Feasibility Study (RI/FS) activities.
Date:
March 7, 2000
Creator:
Kmetz, T. F.; Vanpelt, R. & McAdams, T.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of the 183-D Water Filtration Facility for Bat Roosts and Development of a Mitigation Strategy, 100-D Area, Hanford Site
The 183-D Water Filtration Facility is located in the 100-D Area of the Hanford Site, north of Richland, Washington. It was used to provide filtered water for cooling the 105-D Reactor and supplying fire-protection and drinking water for all facilities in the 100-D Area. The facility has been inactive since the 1980s and is now scheduled for demolition. Therefore, an evaluation was conducted to determine if any part of the facility was being used as roosting habitat by bats.
Date:
March 7, 2011
Creator:
Lindsey, C. T.; Gano, K. A. & Lucas, J. G.
Object Type:
Report
System:
The UNT Digital Library
Status report on the fluidized bed incineration system for U. S. Energy Research and Development Administration transuranic waste, January--June 1976
A fluidized-bed incineration facility is being designed for installation at the Rocky Flats Plant to develop and demonstrate the process for the combustion of transuranic waste. The unit capacity will be about 82 kg/hr of combustible waste. The combustion process will utilize in situ neutralization of acid gases generated in the process. The equipment design is based on data generated on a pilot scale unit and represents a scale-up factor of nine. Title II engineering is at least 70 percent complete and construction work has begun.
Date:
March 7, 1977
Creator:
Ziegler, Donald L.; Richey, Lewis L.; Johnson, Andrew J.; Teter, Alton L.; Feng, Pen K.; Peterson, Dave J. et al.
Object Type:
Report
System:
The UNT Digital Library
Tank 241-S-111: Tank characterization plan
This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, ORNL, and PNL tank vapor program. Scope of this plan is to provide guidance for sampling and analysis of vapor samples from tank 241-S-111 (this tank is on the organic and flammable gas watch list). This tank received Redox plant waste, among other wastes.
Date:
March 7, 1995
Creator:
Homi, C. S.
Object Type:
Report
System:
The UNT Digital Library
NUCLEAR CROSS-SECTION CALCULATIONS IN THE 1 MEV TO 5 GEV RANGE WITH COMBINED SEMI-CLASSICAL AND QUANTUM MECHANICAL MODELS
In this work we describe neutron and proton induced reaction cross-sections for iron produced by the codes TNG and CEM95 in the 5 to 300 MeV energy range. TNG calculations cover the 5-90 MeV range, while CEM95 covers the 50-300 MeV high energy range. The two codes show some disagreements in the overlap energy range, both among themselves and with the experimental data, which are presently being addressed. The experimental data used are from NNDC and/or from LA150 NSE references. We also describe some developments for combining TNG and CEM95 into a new code called CETNG (Cascade Exciton TNG).
Date:
March 7, 2002
Creator:
Guimaraes, F.B.
Object Type:
Report
System:
The UNT Digital Library
Design support document for the K Basins Vertical Fuel Handling Tools
The purpose of this document is to provide the design support information for the Vertical Fuel Handling Tools, developed for the removal of N Reactor fuel elements from their storage canisters in the K Basins storage pool and insertion into the Single Fuel Element Can for subsequent shipment to a Hot Cell for examination. Examination of these N Reactor fuel elements is part of the overall characterization effort. These new hand tools are required since previous fuel movement has involved grasping the fuel in a horizontal position. These tools are required to lift an element vertically from the storage canister. Additionally, a Mark II storage canister Lip Seal Protector was designed and fabricated for use during fuel retrieval. This device was required to prevent damage to the canister lip should a fuel element accidentally be dropped during its retrieval, using the handling tools. Supporting documentation for this device is included in this document.
Date:
March 7, 1995
Creator:
Bridges, A.E.
Object Type:
Report
System:
The UNT Digital Library