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A 5-cm dipole for the SSC-DE-1

Description: A 5cm SSC superconducting dipole that develops 6.6 tesla at 5790 A is proposed. The two layer magnet has 12% more transfer function than the present design as a result of using thin collars and close in'' iron. The thin collars provide precise positioning of the coils; they also provide minimum prestress (perhaps 2000 psi) as aid for magnet assembly. A welded skin around the iron provides the final prestress and shapes and the coil geometry. A prestressed aluminum bar placed between the vertically split iron yokes provides precise control of the gap between yokes halves and is designed to allow gap to close tightly during cooldown so that there is no decrease of prestress. In order to reduce the effect of iron saturation on the field multipoles the iron ID has been optimized to an elliptical shape. The coil inner layer is a 30 strand cable with 1.3:1 cu/sc. The outer layer is a 36 strand cable wit 1.8:1 cu/sc. At the operating field of 6.6 tesla the current density in the copper is 666 A/mm{sup 2} and 760 A/mm{sup 2} in the inner and outer layers respectively. The magnet short sample performance is limited by the inner layer. Operating at 4.35 K the maximum current and central field are 6896 A and 7.95 tesla. The calculated operating short sample temperature at 6.6 tesla and 5798 A is 5.17 K (0.82 K temperature margin). The magnet stored energy is 100.0 (KJ/m) at the 5790 A operating current. A mechanically similar 5cm bore two layer dipole for the cable test facility (D-16B-1) has been recently built and tested. The magnet had no collars and the iron was placed directly on the coil OD. The magnet's first quench was at 7 tesla with 6000 A and it reached 7.6 tesla at ...
Date: April 30, 1990
Creator: Caspi, S.

60-day safety screen results and final report for tank 241-C-111, auger samples 95-Aug-002, 95-Aug-003, 95-Aug-016, and 95-Aug-017

Description: This report presents the details of the auger sampling events for underground waste tank C-111. The samples were shipped to the 222-S laboratories were they underwent safety screening analysis and primary ferricyanide analysis. The samples were analyzed for alpha total, total organic carbon, cyanide, Ni, moisture, and temperature differentials. The results of this analysis are presented in this document.
Date: May 30, 1995
Creator: Rice, A.D.

105-K Basin material design basis feed description for spent nuclear fuel project facilities. Volume 2: Sludge

Description: Volume 2 provides the design feed compositions for the baseline K East and K West Basin sludge process streams expected to be generated during Spent Nuclear Fuel (SNF) Project activities. Four types of feeds are required to support evaluation of specific facility and process considerations during the development of new facilities and processes. These four design feeds provide nominal and bounding conditions for design evaluations. Volume 2 includes definition of inventories for: (1) KE and KW Basins sludge locations (pit sludges, floor sludge, canister.sludge, and wash sludge components), (2) nominal feed for each of five process feed streams, (3) shielding design feed, (4) safety/regulatory assessment feed, and (5) criticality assessment feed.
Date: August 30, 1998
Creator: Pearce, K. L.

200 Area effluent treatment facility process control plan 98-02

Description: This Process Control Plan (PCP) provides a description of the background information, key objectives, and operating criteria defining Effluent Treatment Facility (ETF) Campaign 98-02 as required per HNF-IP-0931 Section 37, Process Control Plans. Campaign 98-62 is expected to process approximately 18 millions gallons of groundwater with an assumption that the UP-1 groundwater pump will be shut down on June 30, 1998. This campaign will resume the UP-1 groundwater treatment operation from Campaign 97-01. The Campaign 97-01 was suspended in November 1997 to allow RCRA waste in LERF Basin 42 to be treated to meet the Land Disposal Restriction Clean Out requirements. The decision to utilize ETF as part of the selected interim remedial action of the 200-UP-1 Operable Unit is documented by the Declaration of the Record of Decision, (Ecology, EPA and DOE 1997). The treatment method was chosen in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) as amended by the Superfund Amendments and Reauthorization Act of 1986 (SARA), the Hanford Federal Facility Agreement and Consent Order (known as the Tri-Party Agreement or TPA), and to the extent practicable, the National Oil and Hazardous Substances Pollution Contingency Plan (NCP).
Date: January 30, 1998
Creator: Le, E.Q.

200-UP-2 operable unit radiological surveys

Description: This report summarizes and documents the results of the radiological surveys conducted from August 17 through December 16, 1993 over a partial area of the 200-UP-2 Operable Unit, 200-W Area, Hanford Site, Richland, Washington. In addition, this report explains the survey methodology of the Mobile Surface Contamination Monitor 11 (MSCM-II) and the Ultra Sonic Ranging And Data System (USRADS). The radiological survey of the 200-UP-2 Operable Unit was conducted by the Site Investigative Surveys/Environmental Restoration Health Physics Organization of the Westinghouse Hanford Company. The survey methodology for the majority of area was based on utilization of the MSCM-II or the USRADS for automated recording of the gross beta/gamma radiation levels at or near six (6) inches from the surface soil.
Date: April 30, 1994
Creator: Wendling, M. A.

242-A Campaign 94-1 post run document

Description: The purpose of this post-run document is to summarize the results of 242-A Evaporator Campaign 94-1 as required. Campaign 94-1 represents the first Evaporator operation since 1989, following completion of the B-534 upgrades and Liquid Effluent Retention Facility (LERF) construction. The purpose of Campaign 94-1 was to concentrate dilute waste from TK-102-AW, TK-106-AW, and TK-103-AP. From an available 2.87 million gallon feedstock of dilute waste contained in 102-AW, 106-AW and 103-AP, an overall Waste Volume Reduction (WVR) of 2.39 million gallons (83% WVRF) was achieved. At the completion of the campaign, approximately 477,000 gallons of dilute double-shell slurry feed (DDSSF) was produced with a SpG. of 1.25--1.30. Total process condensate discharged to LERF was 3.09 million gallons, achieving a condensate/WVR ratio of 1.29. Throughput for Campaign 94-1 was 5.27 million gallons. Total steam condensate and cooling water discharge to B-pond was 4.7 and 216 million gallons respectively. The evaporator operated approximately 43 days of the 60 day campaign for a total operating efficiency of 73%. Campaign 94-1 was completed without any discharge limit, Operating Specification Document, or Operational Safety Requirement violations. Major problems encountered during the run included the following: (1) high CA1 deentrainment pad dP`s caused by foaming, (2) condensate pump P-C100 failure, and (3) ion exchange column dP`s and efficiency.
Date: September 30, 1994
Creator: Guthrie, M. D.

324 and 327 Facilities Environmental Effluent Specifications

Description: These effluent specifications address requirements for the 324/321 Facilities, which are undergoing stabilization activities. Effluent specifications are imposed to protect personnel, the environment and the public, by ensuring adequate implementation and compliance with federal and state regulatory requirements and Hanford programs.
Date: August 30, 1999
Creator: Johnson, D. L.

325 Facility Special Case Waste Disposition Alternatives Analysis

Description: This report addresses the disposition strategy relating to special-case waste (SCW) managed by the Pacific Northwest National Laboratory (PNNL) on the Hanford Site. All of PNNL’s SCW currently resides in the 325 Facility of Hanford’s 300 Area. This facility is operated for the U.S. Department of Energy, Richland Operations Office (RL), by PNNL. Due to the high activity levels of the waste and difficulties in characterizing, classifying, and packaging it to meet the Hanford Site Solid Waste Acceptance Criteria (DOE 1998a), the materials were listed as SCW under the Hanford Facility Agreement and Consent Order (Ecology et.al.). The Hanford Facility Agreement and Consent Order is also known as the Tri-Party Agreement.
Date: August 30, 1999
Creator: Mccoy, Michael W.

The 1995 Farm Bill: Research, Education, and Extension Issues

Description: The House Agriculture Committee has proposed extending Title XVI of the 1990 farm act (P.L. 101-624) for two years. Currently, the title will expire at the end of 1995. The title includes funding authority for the U.s. Department of Agriculture's (USDA) in-house research programs, as well as federal support for cooperative research, higher education, extension programs in the States, and several research grant programs. This report discusses efforts underway to extend this title and reform future legislation. It also outlines federal spending in these areas.
Date: November 30, 1996
Creator: Rawson, Jean M.

1996 ICF program overview

Description: The continuing objective of the Inertial Confinement Fusion (ICF) Program is the demonstration of thermonuclear fusion ignition and energy gain in the laboratory. The underlying theme of all ICF activities as a science research and development program is the Department of Energy's (DOE's) Defense Programs (DP) science-based Stockpile Stewardship and Management (SSM) Program. The extension of current program research capabilities in the National Ignition Facility (NIF) is necessary for the ICF Program to satisfy its stewardship responsibilities. ICF resources (people and facilities) are increasingly being redirected in support of the performance, schedule, and cost goals of the NIF. One of the more important aspects of ICF research is the national nature of the program. Lawrence Livermore National Laboratory's (LLNL's) ICF Program falls within DOE's national ICF Program, which includes the Nova and Beamlet laser facilities at LLNL and the OMEGA, Nike, and Trident laser facilities at the University of Rochester (Laboratory for Laser Energetics, UR/LLE), the Naval Research Laboratory (NRL), and Los Alamos National Laboratory (LANL), respectively. The Particle Beam Fusion Accelerator (PBFA) and Saturn pulsed-power facilities are at Sandia National Laboratories (SNL). General Atomics, Inc. (GA) develops and provides many of the targets for the above experimental facilities. LLNL's ICF Program supports activities in two major interrelated areas: (1) target physics and technology (experimental, theoretical, and computational research); and (2) laser science and optics technology development. Experiments on LLNL's Nova laser primarily support ignition and weapons physics research. Experiments on LLNL's Beamlet laser support laser science and optics technology development. In addition, ICF sciences and technologies, developed as part of the DP mission goals, continue to support additional DOE objectives. These objectives are (1) to achieve diversity in energy sources through inertial fusion energy (IFE) research and (2) to maintain a competitive US economy through new development of technologies ...
Date: September 30, 1996
Creator: Correll, D

1997 toxic chemical release inventory -- Emergency Planning and Community Right-To-Know Act, Section 313

Description: Two listed toxic chemicals were used at the Hanford Site above established activity thresholds: phosphoric acid and chlorine. Because total combined quantities of chlorine released, disposed, treated, recovered through recycle operations, co-combusted for energy recovery, and transferred to off-site locations for the purpose of recycle, energy recovery, treatment, and/or disposal, amounted to less than 500 pounds, the Hanford Site qualified for the alternate one million pound threshold for chlorine. Accordingly, this Toxic Chemical Release Inventory includes a Form A for chlorine, and a Form B for phosphoric acid.
Date: June 30, 1998
Creator: Zaloudek, D. E.

1998 Annual Report - Environmental Restoration Division

Description: This is a 1998 annual report for Environmental Restoration. Environmental Restoration's accomplishments were significant in 1998. The division, including its support organizations, completed one year without a lost time accident. It also met 111 enforceable agreement milestones on time, with more than 80% ahead of schedule. Funds used to meet these milestones were effectively utilized and $9.63 million in regulatory scope was added. Twelve new, innovative technologies were deployed, enabling ER to achieve significant progress on major field remediation projects, including: Remediation of 25 acres of radioactive burial ground; Removal of 1,300 batteries for recycling; Removal and safe storage of a radioactive underground tank; Extraction of 115,000 pounds of solvent; and Installation of 9 new recirculation wells and a second GeoSiphon Cell for additional removal of solvent Final Records of Decision were made for 9 base unit sites. No Further Action decisions were made for 61 additional sites.
Date: December 30, 1998
Creator: Davis, L.B.

2nd Quarterly technical progress report for geothermal system temperature-depth database

Description: At the Southern Methodist University Geothermal Laboratory in Dallas, Texas, the Earth`s surface and internal temperature are studied. With financial support from the U.S. Department of Energy, a data base containing geothermal temperature well information for the United States is being developed. During this calendar quarter, activity with this project has continued involving several different tasks: planning and development of the geothermal system thermal-well data base and temperature-depth data, development of the specifications for the data base, and completion of an initial inventory of the geothermal areas for which data are available.
Date: July 30, 1997
Creator: Blackwell, D.D.

3D field harmonics

Description: We have developed an harmonic representation for the three dimensional field components within the windings of accelerator magnets. The form by which the field is presented is suitable for interfacing with other codes that make use of the 3D field components (particle tracking and stability). The field components can be calculated with high precision and reduced cup time at any location (r,{theta},z) inside the magnet bore. The same conductor geometry which is used to simulate line currents is also used in CAD with modifications more readily available. It is our hope that the format used here for magnetic fields can be used not only as a means of delivering fields but also as a way by which beam dynamics can suggest correction to the conductor geometry. 5 refs., 70 figs.
Date: March 30, 1991
Creator: Caspi, S.; Helm, M. & Laslett, L.J.

3D particle simulation of beams using the WARP code: Transport around bends

Description: WARP is a discrete-particle simulation program which was developed for studies of space charge dominated ion beams. It combines features of an accelerator code and a particle-in-cell plasma simulation. The code architecture, and techniques employed to enhance efficiency, are briefly described. Current applications are reviewed. In this paper we emphasize the physics of transport of three-dimensional beams around bends. We present a simple bent-beam PIC algorithm. Using this model, we have followed a long, thin beam around a bend in a simple racetrack system (assuming straight-pipe self-fields). Results on beam dynamics are presented; no transverse emittance growth (at mid-pulse) is observed. 11 refs., 5 figs.
Date: November 30, 1990
Creator: Friedman, A.; Grote, D.P.; Callahan, D.A.; Langdon, A.B. (Lawrence Livermore National Lab., CA (USA)) & Haber, I. (Naval Research Lab., Washington, DC (USA))

3D simulations of axially confined heavy ion beams in round and square pipes

Description: We have been using the 3d PIC code WARP6 to model the behavior of beams in a heavy ion induction accelerator; such linacs are candidates for an ICF driver. Improvements have been added to the code to model an axially confined beam using comoving axial electric fields to simulate the confining ears'' applied to the accelerating pulses in a real system. We have also added a facility for modeling a beam in a round pipe, applying a capacity matrix to each axial Fourier mode in turn. These additions are described along with results, such as the effect of pipe shape on the beam quality degradation from quadrupole misalignments. 4 refs., 6 figs., 1 tab.
Date: November 30, 1990
Creator: Grote, D.P.; Friedman, A. (Lawrence Livermore National Lab., CA (USA)) & Haber, I. (Naval Research Lab., Washington, DC (USA))

Accelerating cleanup: Paths to closure

Description: This document was previously referred to as the Draft 2006 Plan. As part of the DOE`s national strategy, the Richland Operations Office`s Paths to Closure summarizes an integrated path forward for environmental cleanup at the Hanford Site. The Hanford Site underwent a concerted effort between 1994 and 1996 to accelerate the cleanup of the Site. These efforts are reflected in the current Site Baseline. This document describes the current Site Baseline and suggests strategies for further improvements in scope, schedule and cost. The Environmental Management program decided to change the name of the draft strategy and the document describing it in response to a series of stakeholder concerns, including the practicality of achieving widespread cleanup by 2006. Also, EM was concerned that calling the document a plan could be misconstrued to be a proposal by DOE or a decision-making document. The change in name, however, does not diminish the 2006 vision. To that end, Paths to Closure retains a focus on 2006, which serves as a point in time around which objectives and goals are established.
Date: June 30, 1998
Creator: Edwards, C.

Acceptability of risk from radiation: Application to human space flight

Description: This one of NASA`s sponsored activities of the NCRP. In 1983, NASA asked NCRP to examine radiation risks in space and to make recommendations about career radiation limits for astronauts (with cancer considered as the principal risk). In conjunction with that effort, NCRP was asked to convene this symposium; objective is to examine the technical, strategic, and philosophical issues pertaining to acceptable risk and radiation in space. Nine papers are included together with panel discussions and a summary. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.
Date: April 30, 1997

Acceptance test procedure for High Pressure Water Jet System

Description: The overall objective of the acceptance test is to demonstrate a combined system. This includes associated tools and equipment necessary to perform cleaning in the 105 K East Basin (KE) for achieving optimum reduction in the level of contamination/dose rate on canisters prior to removal from the KE Basin and subsequent packaging for disposal. Acceptance tests shall include necessary hardware to achieve acceptance of the cleaning phase of canisters. This acceptance test procedure will define the acceptance testing criteria of the high pressure water jet cleaning fixture. The focus of this procedure will be to provide guidelines and instructions to control, evaluate and document the acceptance testing for cleaning effectiveness and method(s) of removing the contaminated surface layer from the canister presently identified in KE Basin. Additionally, the desired result of the acceptance test will be to deliver to K Basins a thoroughly tested and proven system for underwater decontamination and dose reduction. This report discusses the acceptance test procedure for the High Pressure Water Jet.
Date: May 30, 1995
Creator: Crystal, J.B.

Acceptance Test Procedure: SY101 air pallet system

Description: The purpose of this test procedure is to verify that the system(s) procured to load the SY-101 Mitigation Test Pump package fulfills its functional requirements. It will also help determine the man dose expected due to handling of the package during the actual event. The scope of this procedure focuses on the ability of the air pallets and container saddles to carry the container package from the new 100 foot concrete pad into 2403-WD where it will be stored awaiting final disposition. This test attempts to simulate the actual event of depositing the SY-101 hydrogen mitigation test pump into the 2403-WD building. However, at the time of testing road modifications required to drive the 100 ton trailer into CWC were not performed. Therefore a flatbed trailer will be use to transport the container to CWC. The time required to off load the container from the 100 ton trailer will be recorded for man dose evaluation on location. The cranes used for this test will also be different than the actual event. This is not considered to be an issue due to minimal effects on man dose.
Date: May 30, 1995
Creator: Koons, B.M.

Action plan for the Tiger Team assessment report

Description: This document contains responses and planned actions that address the findings of the Tiger Team Assessment of Brookhaven National Laboratory, June 1990. In addition, the document contains descriptions of the management and organizational structure to be used in conducting planned actions, root causes for the problems identified in the findings, responses, planned actions, schedules and milestones for completing planned actions, and, where known, costs associated with planned actions.
Date: August 30, 1990

Adaptive forward-inverse modeling of reservoir fluids away from wellbores

Description: This Final Report contains the deliverables of the DeepLook Phase I project entitled, ''Adaptive Forward-Inverse Modeling of Reservoir Fluids Away from Wellbores''. The deliverables are: (i) a description of 2-D test problem results, analyses, and technical descriptions of the techniques used, (ii) a listing of program setup commands that construct and execute the codes for selected test problems (these commands are in mathematical terminology, which reinforces technical descriptions in the text), and (iii) an evaluation and recommendation regarding continuance of this project, including considerations of possible extensions to 3-D codes, additional technical scope, and budget for the out-years. The far-market objective in this project is to develop advanced technologies that can help locate and enhance the recovery of oil from heterogeneous rock formations. The specific technical objective in Phase I was to develop proof-of-concept of new forward and inverse (F-I) modeling techniques [Gelinas et al, 1998] that seek to enhance estimates (images) of formation permeability distributions and fluid motion away from wellbore volumes. This goes to the heart of improving industry's ability to jointly image reservoir permeability and flow predictions of trapped and recovered oil versus time. The estimation of formation permeability away from borehole measurements is an ''inverse'' problem. It is an inseparable part of modeling fluid flows throughout the reservoir in efforts to increase the efficiency of oil recovery at minimum cost. Classic issues of non-uniqueness, mathematical instability, noise effects, and inadequate numerical solution techniques have historically impeded progress in reservoir parameter estimations. Because information pertaining to fluid and rock properties is always sampled sparsely by wellbore measurements, a successful method for interpolating permeability and fluid data between the measurements must be: (i) physics-based, (ii) conditioned by signal-processing tenets, and (iii) solved with sufficiently rigorous mathematical and numerical techniques. Such a methodology is applied in this project, as ...
Date: July 30, 1999
Creator: Ziagos, J P; Gelinas, R J; Doss, S K & Nelson, R G

Adaptive Superplastic Forming Using NIKE2D with ISLAND

Description: Superplastic forming has emerged as an important manufacturing process for producing near-net-shape parts. The design of a superplastic forming process is more difficult than conventional manufacturing operations, and is less amenable to trial and error approaches. This paper describes a superplastic forming process design capability incorporating nonlinear finite element analysis. The material constraints to allow superplastic behavior are integrated into an external constraint equation which is solved concurrently with the nonlinear finite element equations. The implementation of this approach using the ISLAND solution control language with the nonlinear finite element code NIKE2D is discussed in detail. Superplastic forming process design problems with one and two control parameters are presented as examples.
Date: July 30, 1992
Creator: Engelmann, Bruce E.; Whirley, Robert G. & Raboin, Peter J.