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1996 ICF program overview
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 …
Date:
September 30, 1996
Creator:
Correll, D
Object Type:
Report
System:
The UNT Digital Library
Advanced combustor design concepts to control NO{sub x} and air toxics. Quarterly report, [July--September 1996]
Understanding the mechanisms of char-N oxidation and reduction is necessary for the accurate modeling of NO, formation from coal combustion. This statement is especially true for combustors where low- NO{sub x} combustion modification techniques have been applied because in such cases the fraction of total fuel- NO{sub x} coming from the char is very high. This study has focused on obtaining experimental data that can be used to evaluate char-N oxidation and reduction mechanisms. The ultimate goal is to use this knowledge to improve the NO{sub x} submodel in an existing computational fluid dynamics (CFD) code. Several key experimental results were outlined in the report for the quarter ending 6/96. In order to clarify certain conclusions, more data were collected and analyzed during the quarter ending 9/96. Results from these new data as well as important results not included in the 6/96 report are addressed here.
Date:
September 30, 1996
Creator:
Pershing, D.W.; Lighty, J.; Smith, P.; Spinti, J.; Veranth, J. & Domino, S.
Object Type:
Report
System:
The UNT Digital Library
Ags Proposal 923 - Search for T Violating Muon Polarization in K+ Yields M+p0vm Decay.
None
Date:
September 30, 1996
Creator:
Diwan, M. V.; Frank, J.; Gordeev, A.; Kettell, S.; Leipuner, L.; Littenberg, L. et al.
Object Type:
Article
System:
The UNT Digital Library
Altus Times (Altus, Okla.), Vol. 96, No. 171, Ed. 1 Monday, September 30, 1996
Daily newspaper from Altus, Oklahoma that includes local, state, and national news along with advertising.
Date:
September 30, 1996
Creator:
Lomenick, Rick
Object Type:
Newspaper
System:
The Gateway to Oklahoma History
The Alvin Sun (Alvin, Tex.), Vol. 106, No. 16, Ed. 1 Monday, September 30, 1996
Weekly newspaper from Alvin, Texas that includes local, state, and national news along with advertising.
Date:
September 30, 1996
Creator:
Schwind, Jim & Chionsini, Brandi
Object Type:
Newspaper
System:
The Portal to Texas History
The Baytown Sun (Baytown, Tex.), Vol. 74, No. 287, Ed. 1 Monday, September 30, 1996
Daily newspaper from Baytown, Texas that includes local, state, and national news along with advertising.
Date:
September 30, 1996
Creator:
Dobbs, Gary
Object Type:
Newspaper
System:
The Portal to Texas History
Calculation note review
This document contains a review of the calculation notes which were prepared for the Tank Waste Remediation System Basis for Interim Operation.
Date:
September 30, 1996
Creator:
Ramble, A.L.
Object Type:
Report
System:
The UNT Digital Library
Ceramic component manufacturing process development. Final report
Ceramic materials are well suited for applications where temperature, wear, and corrosion resistance are necessary. The toughness and wear resistance properties that make ceramics desirable, also make fabrication of parts difficult. The objective of this CRADA was to increase the grinding efficiency on Ceradyne Incorporated silicon nitride. This was to be accomplished through optimization of grinding wheel life and increasing silicon nitride material removal rates. Experiments were conducted to determine the relationship between grinding parameters, wheel wear, and material removal rates. Due to excessive, unexplained variation in the experimental results, a consistent relationship between the selected grinding parameters and wheel wear could not be established. Maximum material removal rates were limited by spindle and table drive power. Additional experiments were conducted to evaluate high speed grinding. When compared to conventional grinding speeds, the material removal rates using high speed grinding (13,000 SFM) increased by a factor of five to ten with no degradation of fracture strength.
Date:
September 30, 1996
Creator:
Robinson, S.
Object Type:
Report
System:
The UNT Digital Library
Chickasha Daily Express (Chickasha, Okla.), Vol. 106, No. 162, Ed. 1 Monday, September 30, 1996
Daily newspaper from Chickasha, Oklahoma that includes local, state, and national news along with advertising.
Date:
September 30, 1996
Creator:
Bush, Kent
Object Type:
Newspaper
System:
The Gateway to Oklahoma History
Clean salt process final report
A process has been demonstrated in the laboratory for separating clean, virtually non-radioactive sodium nitrate from Hanford tank waste using fractional crystallization. The name of the process is the Clean Salt Process. Flowsheet modeling has shown that the process is capable of reducing the volume of vitrified low activity waste (LAW) by 80 to 90 %. Construction of the Clean Salt processing plant would cost less than $1 10 million, and would eliminate the need for building a $2.2 billion large scale vitrification plant planned for Privatization Phase 11. Disposal costs for the vitrified LAW would also be reduced by an estimated $240 million. This report provides a summary of five years of laboratory and engineering development activities, beginning in fiscal year 1992. Topics covered include laboratory testing of a variety of processing options; proof-of-principle demonstrations with actual waste samples from Hanford tanks 241-U-110 (U-110), 241-SY-101 (101-SY), and 241-AN-102 (102-AN); descriptions of the primary solubility phase diagrams that govem the process; a review of environmental regulations governing disposition of the reclaimed salt and an assessment of the potential beneficial uses of the reclaimed salt; preliminary plant design and construction cost estimates. A detailed description is given for the large scale …
Date:
September 30, 1996
Creator:
Herting, D. L.
Object Type:
Report
System:
The UNT Digital Library
Coal Air Turbine ``CAT`` program invention 604. Eighth quarter project report and final for the project, August--September 1996
The primary objective of this ``CAT`` project is to complete a conceptual design of this unique new combination of existing technology with cost estimates to show that the ``CAT`` system offers the economic incentive with low technical risk for a plant to be built which will demonstrate its viability. The technologies involved in the components of a ``CAT`` plant are proven, and the integration of the components into a complete plant is the only new developmental activity involved. Industry and the Federal General Services Administration (GSA), require the demonstration of a ``commercial plant`` before the viability of a new concept is accepted. To satisfy this requirement the construction of a plant of commercially viable size in excess of 15 MW if cogeneration and above 30 MW if all power, is proposed. This plant will produce economical power and heat for the owner. The plant will operate for a full commercial life and continue as an operating demonstration of the viability of the technology, gathering long term life and maintenance data, all adding to the credibility of the concept.
Date:
September 30, 1996
Creator:
Foster-Pegg, R. W.
Object Type:
Report
System:
The UNT Digital Library
Critical experiments on an enriched uranium solution system containing periodically distributed strong thermal neutron absorbers
A series of 62 critical and critical approach experiments were performed to evaluate a possible novel means of storing large volumes of fissile solution in a critically safe configuration. This study is intended to increase safety and economy through use of such a system in commercial plants which handle fissionable materials in liquid form. The fissile solution`s concentration may equal or slightly exceed the minimum-critical-volume concentration; and experiments were performed for high-enriched uranium solution. Results should be generally applicable in a wide variety of plant situations. The method is called the `Poisoned Tube Tank` because strong neutron absorbers (neutron poisons) are placed inside periodically spaced stainless steel tubes which separate absorber material from solution, keeping the former free of contamination. Eight absorbers are investigated. Both square and triangular pitched lattice patterns are studied. Ancillary topics which closely model typical plant situations are also reported. They include the effect of removing small bundles of absorbers as might occur during inspections in a production plant. Not taking the tank out of service for these inspections would be an economic advantage. Another ancillary topic studies the effect of the presence of a significant volume of unpoisoned solution close to the Poisoned Tube Tank …
Date:
September 30, 1996
Creator:
Rothe, R.E.
Object Type:
Report
System:
The UNT Digital Library
DELPHI expert panel evaluation of Hanford high level waste tank failure modes and release quantities
The Failure Modes and Release Quantities of the Hanford High Level Waste Tanks due to postulated accident loads were established by a DELPHI Expert Panel consisting of both on-site and off-site experts in the field of Structure and Release. The Report presents the evaluation process, accident loads, tank structural failure conclusion reached by the panel during the two-day meeting.
Date:
September 30, 1996
Creator:
Dunford, G.L. & Han, F.C.
Object Type:
Report
System:
The UNT Digital Library
Design requirements document for the interim store phase I solidified high-level waste function 4.2.4.1.2
The U.S. Department of Energy (DOE) has embarked upon a course to acquire Hanford site.t,,nk waste tr:atment and immobilization services using privatized facilities. This plan contains a two-phased approach. Phase I is a ``proof-of-principle/commercial demonstration-scale`` effort and Phase II is a full-scale production effort. In accordance with the planned approach, interim storage and disposal of various products from privatized facilities are to be DOE furnished. The path forward adopted for Phase I solidified high-level waste (HLW) interim storage entails use of Vaut 2 and 3 in the Hanford Site Spent Nuclear Fuels Canister Storage Building (CSB), to be located in the Hanford Site 200 East Area. This design requirements document establishes the functions, with associated requirements, allocated to the Phase I solidified HLW interim storage system. These requirements will be used as the basis for conceptual design of the CSB and supporting systems. This document will also provide the basis for preparation of a performance specification for design and construction activities necessary to achieve the overall project mission.
Date:
September 30, 1996
Creator:
Calmus, R. B.
Object Type:
Report
System:
The UNT Digital Library
Design requirements document for the phase one privitization facility electrical power
None
Date:
September 30, 1996
Creator:
Singh, G.
Object Type:
Report
System:
The UNT Digital Library
Design studies for a high-resolution, transportable neutron radiography/radioscopy system
A preliminary design has been developed for a high-resolution, transportable neutron radiology system (TNRS) concept. The primary system requirement is taken to be a thermal neutron flux of 10[sup 6] n/(cm[sup 2]-sec) with a L/D ratio of 100. The approach is to use an accelerator-driven neutron source, with a radiofrequency quadrupole (RFQ) as the primary accelerator component. Initial concepts for all of the major components of the system have been developed,and selected key parts have been examined further. An overview of the system design is presented, together with brief summaries of the concepts for the ion source, low energy beam transport (LEBT), RFQ, high energy beam transport (HEBT), target, moderator, collimator, image collection, power, cooling, vacuum, structure, robotics, control system, data analysis, transport vehicle, and site support. The use of trade studies for optimizing the TNRS concept are also described.
Date:
September 30, 1996
Creator:
Gillespie, G.H.; Micklich, B.J. & McMichael, G.E.
Object Type:
Article
System:
The UNT Digital Library
DNFSB recommendation 94-1 Hanford site integrated stabilization management plan - Volumes 1-3
The Hanford Site Integrated Stabilization Management Plan (SISMP) was developed in support of the US Department of Energy's (DOE) Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1 Integrated Program Plan (IPP). Volume 1 of the SISMP identifies the technical scope and costs associated with Hanford Site plans to resolve concerns identified in DNFSB Recommendation 94-1. Volume 2 of the SISMP provides the Resource Loaded Integrated Schedules for Spent Nuclear Fuel Project and Plutonium Finishing Plant activities identified in Volume 1 of the SISMP. Volume 3 of the SISMP identifies the 35 Plutonium Environmental, Safety, and Health Vulnerabilities. The vulnerabilities range from institutional problems to specific hardware problems. Many of the identified vulnerabilities will be corrected through the stabilization and packaging activities required by the DNFSB Recommendation 94-1 Implementation Plan, the remainder will be corrected as a part of the plutonium handling facilities transition (deactivation) to the Environmental Restoration Program.
Date:
September 30, 1996
Creator:
Gerber, E.W.
Object Type:
Report
System:
The UNT Digital Library
DST pitting annual report
This report provides details of activities during FY 1996 for the double-shell tank pitting kinetics testing task.
Date:
September 30, 1996
Creator:
Anantatmula, R.P.
Object Type:
Report
System:
The UNT Digital Library
Engineering study TWRS privatization phase I roads and rail system modifications
The DOE-RL is pursuing a new business strategy of hiring private contractors for treatment of Hanford Site tank wastes. This strategy is called privatization and includes design, permitting , construction, operation and deactivation of facilities for tank waste treatment. The TWRS Privatization Infrastructure Project is part of the first phase of the initiative. It consists of several sub-projects which will provide key physical interfaces and services needed to support the privatization mission. One sub-project is to establish transport system changes needed to support the privatization initiative. Specifically, this study identifies the road and rail system modifications needed to service the privatization site in 2OOE; an area previously developed and characterized for Grout Disposal.
Date:
September 30, 1996
Creator:
Ackerman, R. L.
Object Type:
Report
System:
The UNT Digital Library
Evaluation/disposition of observations no. 6-17, 6-18, and 6-22 from site electrical assessment report, 300 area powerhouse and emergency sys.
Disposition of Observations 6-17, 6-18, 6-22 of Site Electrical Assessment Report. Application of generator differential protection, and synchro-check relay rewiring for generators of building 3621-D. In 1990, the WHC Site Electrical Task Group issued a Site Electrical Assessment Report, ``300 Area Powerhouse and Emergency System.`` This report included numerous findings and observations relating to observed deficiencies or opportunities for improvement in maintenance of the inspected electrical systems. The purpose of this letter report is to provide an evaluation and proposed disposition of Observations No. 6-1 7, 6-1 8, and 6-22 of the Site Electrical Assessment Report.
Date:
September 30, 1996
Creator:
Ahola, E.L.
Object Type:
Report
System:
The UNT Digital Library
Formulation and make-up of simulated acidic concentrated water (SAW), high ionic content aqueous solution
This procedure describes the formulation and make-up of Simulated Acidified Water (SAW), a high-ionic-content water to be used for Activity E-20-50 ''Long-Term Corrosion Studies.'' Acidic solutions at the repository may result as a consequence of microbial activity. In formulating the ionic composition of the SAW, it was attempted to simulate the acidification of high ionic content water contacting a waste package. Therefore, the composition of this water is based on the acidification of the Simulated Concentrated Water (SCW), which is described in TIP-CM-07. The pH of the solution will be controlled at a nominal value of 2.
Date:
September 30, 1996
Creator:
Gdowski, G.
Object Type:
Report
System:
The UNT Digital Library
FY96 Support to the Defense Information Systems Agency (DISA), Center for Standards (CFS) for continuing improvement of the DoD HCI Style Guide. Final report
PNNL successfully completed the three tasks: Task 1 - This task provided DISA with an updated set of design checklists that can be used to measure compliance with the Style Guide. These checklists are in Microsoft{reg_sign}Word 6.0 format. Task 2 - This task provided a discussion of two basic models for using the Style Guide and the Design Checklist, as a compliance tool and as a design tool.
Date:
September 30, 1996
Creator:
Avery, L.W.; Donohoo, D.T.; Sanchez, J.A. & Gellert, D.A.
Object Type:
Report
System:
The UNT Digital Library
Hanford site performance summary - EM funded programs (formerly known as Hanford site performance summary)
Hanford fiscal-year-to-date (FYTD) schedule performance remains unfavorable with a three percent schedule variance (-$36.6 million*) and a four percent cost variance (+$47.5 million). The schedule var-iance is attributed to EM-30, Office of Waste Management (-$21.6 million), EM-40, Office of Environmental Restoration (-$7.7 million), and EM-60, Office of Nuclear Material and Facility Stabilization (-$5.3 million). Sixty-one enforceable agreement milestones were scheduled FYTD; fifty-six were Completed on or ahead of schedule and five are overdue (see Enforceable Agreement Milestones). Notable accomplishments include: * completion of the draft Hanford FY 1997 Multi-Year Work Plans; * receipt of the draft TWRS Privatization Process Technical Baseline for review and comment; * issuance of the draft Hanford Strategic Plan for external review; * receipt of the 1997 Public/Private Partnership Award for work on the Hanford Metal Working Equipment Project; * completion of the 100-D Pond sediment removal project; * disposal of over 10,700 loose cubic yards (15,000 tons) of remediation waste since the July 1, 1996, opening of the Environmental Restoration Disposal Facility; * initiation of a program to test state-of-the-art technologies for characterizing waste burial sites slated for remediation; * completion of the 100-HR-3 Pump-and-Treat Test Program including unit shutdown and placement in safe storage; …
Date:
September 30, 1996
Creator:
Edwards, C.
Object Type:
Report
System:
The UNT Digital Library
Hanford Site technical baseline database
This document includes a cassette tape that contains the Hanford specific files that make up the Hanford Site Technical Baseline Database as of September 30, 1996. The cassette tape also includes the delta files that dellinate the differences between this revision and revision 4 (May 10, 1996) of the Hanford Site Technical Baseline Database.
Date:
September 30, 1996
Creator:
Porter, P.E.
Object Type:
Report
System:
The UNT Digital Library