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Protocol for disposition of tank farm equipment lists and tank farm drawings for year 2000 compliance (open access)

Protocol for disposition of tank farm equipment lists and tank farm drawings for year 2000 compliance

A program has been initiated to assess, renovate, document and certify tank farm field equipment for year 2000 compliance. The program is necessary to assure no adverse effects occur in tank farm operations as a result of equipment malfunction due to what is widely known as the ''millennium bug''. This document elaborates the protocols for reviewing field equipment lists and tank farm drawings for the purpose of identifying and resolving year 2000 compliance problems in tank farm equipment.
Date: February 23, 1999
Creator: Adams, M. R.
System: The UNT Digital Library
Simulating the Effect on Criticality of Simultaneous Matrix Degradation and Assembly Collapse for the 21 PWR Waste Package (open access)

Simulating the Effect on Criticality of Simultaneous Matrix Degradation and Assembly Collapse for the 21 PWR Waste Package

The purpose of this calculation is to evaluate the effects of fission products loss on the reactivity of commercial pressurized water reactor (PWR) spent nuclear fuel (SNF) in 21 PWR waste packages (WPs) in the event of simultaneous fuel matrix degradation and assembly collapse.
Date: September 23, 1999
Creator: Alsaed, A. A.
System: The UNT Digital Library
TRIGA FUEL PHASE I AND II CRITICALITY CALCULATION (open access)

TRIGA FUEL PHASE I AND II CRITICALITY CALCULATION

The purpose of this calculation is to characterize the criticality aspect of the codisposal of TRIGA (Training, Research, Isotopes, General Atomic) reactor spent nuclear fuel (SNF) with Savannah River Site (SRS) high-level waste (HLW). The TRIGA SNF is loaded into a Department of Energy (DOE) standardized SNF canister which is centrally positioned inside a five-canister defense SRS HLW waste package (WP). The objective of the calculation is to investigate the criticality issues for the WP containing the five SRS HLW and DOE SNF canisters in various stages of degradation. This calculation will support the analysis that will be performed to demonstrate the viability of the codisposal concept for the Monitored Geologic Repository (MGR).
Date: November 23, 1999
Creator: Angers, L.
System: The UNT Digital Library
Measuring parameters of large-aperture crystals used for generating optical harmonics (open access)

Measuring parameters of large-aperture crystals used for generating optical harmonics

The purpose of this project was to develop tools for understanding the influence of crystal quality and crystal mounting on harmonic-generation efficiency at high irradiance. Measuring the homogeneity of crystals interferometrically, making detailed physics calculations of conversion efficiency, performing finite- element modeling of mounted crystals, and designing a new optical metrology tool were key elements in obtaining that understanding. For this work, we used the following frequency-tripling scheme: type I second- harmonic generation followed by type II sum-frequency mixing of the residual fundamental and the second harmonic light. The doubler was potassium dihydrogen phosphate (KDP), and the tripler was deuterated KDP (KD*P). With this scheme, near-infrared light (1053 nm) can be frequency tripled (to 351 nm) at high efficiency (theoretically >90%) for high irradiance (>3 GW/cm²). Spatial variations in the birefringence of the large crystals studied here (37 to 41 cm square by about 1 cm thick) imply that the ideal phase-matching orientation of the crystal with respect to the incident laser beam varies across the crystal. We have shown that phase-measuring interferometry can be used to measure these spatial variations. We observed transmitted wavefront differences between orthogonally polarized interferograms of {lambda}/50 to {lambda}/100, which correspond to index variations of …
Date: February 23, 1999
Creator: Auerbach, J. M.; English, R. E., Jr.; Hibbard, R. L.; Michie, R. B.; Norton, M. A.; Perfect, S. A. et al.
System: The UNT Digital Library
Waste retrieval sluicing system campaign number 1 solids volume transferred calculation (open access)

Waste retrieval sluicing system campaign number 1 solids volume transferred calculation

This calculation has been prepared to document the volume of sludge removed from tank 241-C-106 during Waste Retrieval Sluicing System (WRSS) Sluicing Campaign No.1. This calculation will be updated, if necessary, to incorporate new data. This calculation supports the declaration of completion of WRSS Campaign No.1 and, as such, is also the documentation for completion of Performance Agreement TWR 1.2.1, C-106 Sluicing Performance Expectations. It documents the performance of all the appropriate tank 241-C-106 mass transfer verifications, evaluations, and appropriate adjustments discussed in HNF-SD-WM-PROC-021, Chapter 23, ''Process Engineering Calculations for Tank 241-C-106 Sluicing and Retrieval''.
Date: June 23, 1999
Creator: BAILEY, J.W.
System: The UNT Digital Library
WRSS jumper leak assessment (open access)

WRSS jumper leak assessment

The purpose of this assessment is: (1) to assemble and document the facts associated with three recently installed jumpers which have leaked either during actual process operation or during post installation testing; (2) to describe the corrective actions taken and to identify any process improvements which need to be implemented in the Hanford jumper design and installation activities; and (3) to document WRSS jumper leak lessons learned for use by future projects and other jumper design, fabrication, and installation activities.
Date: June 23, 1999
Creator: BAILEY, J.W.
System: The UNT Digital Library
Data quality objectives for TWRS privatization phase 1: tank waste transfer control (open access)

Data quality objectives for TWRS privatization phase 1: tank waste transfer control

The Phase 1 privatization contract (DOE-RL 1996) requires that the Project Hanford Management Contractors, on behalf of the U.S. Department of Energy, Richland Operations Office, deliver waste feed in appropriate quantities and composition on schedule. The Feed Process Management Team (FPMT) was created with responsibility for establishing requirements, identifying and recommending baseline change control, assuring configuration management of tank contents (e.g., feed pedigrees), and requiring understanding among the various TWRS elements so the right feed is produced on schedule (Boston 1996). The FPMT has charged the Double Shell Tank (DST) Waste Inventory Control (WIC) (LMHC 1997) group to develop and implement the waste configuration control needed to insure that our ability to deliver feed on schedule is not adversely impacted. The WIC group, which has representatives from engineering, environmental, operations, and waste feed delivery, reviews proposed waste transfers and technical issues affecting the TWRS waste inventory. The WIC group either approves proposed transfers or, if a unanimous decision is not obtained, elevates approval to the FPMT. A representative from the FPMT is present at the WIC group meetings where waste transfer approvals are decided, and WIC relays information to the FPMT as needed. The TWRS operations include waste inventory control, …
Date: June 23, 1999
Creator: BANNING, D.L.
System: The UNT Digital Library
Tank 241-Z-361 vapor sampling and analysis plan (open access)

Tank 241-Z-361 vapor sampling and analysis plan

Tank 241-Z-361 is identified in the Hanford Federal Facility Agreement and Consent Order (commonly referred to as the Tri-Party Agreement), Appendix C, (Ecology et al. 1994) as a unit to be remediated under the authority of the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). As such, the U.S. Environmental Protection Agency will serve as the lead regulatory agency for remediation of this tank under the CERCLA process. At the time this unit was identified as a CERCLA site under the Tri-Party Agreement, it was placed within the 200-ZP-2 Operable Unit. In 1997, The Tri-parties redefined 200 Area Operable Units into waste groupings (Waste Site Grouping for 200 Areas Soils Investigations [DOE-RL 1992 and 1997]). A waste group contains waste sites that share similarities in geological conditions, function, and types of waste received. Tank 241-Z-361 is identified within the CERCLA Plutonium/Organic-rich Process Condensate/Process Waste Group (DOE-RL 1992). The Plutonium/Organic-rich Process Condensate/Process Waste Group has been prioritized for remediation beginning in the year 2004. Results of Tank 216-Z-361 sampling and analysis described in this Sampling and Analysis Plan (SAP) and in the SAP for sludge sampling (to be developed) will determine whether expedited response actions are required before 2004 …
Date: February 23, 1999
Creator: BANNING, D.L.
System: The UNT Digital Library
Engineering safety evaluation for 22 ton steel disposal box lifting bail design (open access)

Engineering safety evaluation for 22 ton steel disposal box lifting bail design

The objective of this analysis is to design and analyze the lifting bail of the 22 Ton Steel Waste Disposal Box (SWDB). The new design takes the original lifting bail and adds a hinge allowing the top portion of the bail to fold over towards the lid.
Date: November 23, 1999
Creator: BOEHNKE, W.M.
System: The UNT Digital Library
29th Annual PolyMAC Meeting: Book of Abstracts (open access)

29th Annual PolyMAC Meeting: Book of Abstracts

A sixteen-run, Resolution IV, fractional factorial screening design has been used to evaluate the relative significance of seven independent material and process variables for an electrically deposited commercial acrylic paint. A Resolution IV design was chosen so that variable interactions could be detected without any interference from the effects of the variables themselves. Because resource limitations did not permit use of a Resolution V design, the two-way interactions were confounded with one another in groups of three, which unfortunately made interpretation of the results more complicated. Each design point was replicated once and a pair of centerpoints were run at the beginning, in the middle and at the end of the design points. A total of 38 test panels were prepared. Independent variables used in this experiment were total charge, current density, mixer speed, silica content, crossover point, temperature and solids fraction. The magnitude of each independent variable's effect on the dependent response variables was estimated by fitting a first-order model with two-way interaction terms. Three-way interactions were assumed to be insignificant. Interaction confounding was eliminated by using the significance of the independent variables to determine which of the three possible interactions was significant. Data analysis was performed using the …
Date: July 23, 1999
Creator: Balazs, B.
System: The UNT Digital Library
Toward Net Energy Buildings: Design, Construction, and Performance of the Grand Canyon House (open access)

Toward Net Energy Buildings: Design, Construction, and Performance of the Grand Canyon House

The Grand Canyon house is a joint project of the DOE's National Renewable Energy Laboratory and the U.S. National Park Service and is part of the International Energy Agency Solar Heating and Cooling Programme Task 13 (Advanced Solar Low-Energy Buildings). Energy consumption of the house, designed using a whole-building low-energy approach, was reduced by 75% compared to an equivalent house built in accordance with American Building Officials Model Energy Code and the Home Energy Rating System criteria.
Date: June 23, 1999
Creator: Balcomb, J. D.; Hancock, C. E. & Barker, G.
System: The UNT Digital Library
Evaluation of the Hydrologic Source Term From Underground Nuclear Tests in Frenchman Flat at the Nevada Test Site: The Cambric Test (open access)

Evaluation of the Hydrologic Source Term From Underground Nuclear Tests in Frenchman Flat at the Nevada Test Site: The Cambric Test

The objectives of this project are to develop and apply a modeling frame- work to quantitatively evaluate the nature and extent of radionuclide migration within the immediate, near field environment about an underground nuclear test. Specifically, it will involve evaluation of ² The speciation and abundance of radionuclides that are introduced into groundwater as aqueous species or colloids, and ² The rate and extent of radionuclide movement, dilution, and reaction in groundwater surrounding the working point of a test. To be clear, interest will only be focused on processes that have occurred well after the nuclear test, as opposed to the more dynamic processes that take place during or immediately after detonation. The meaning of "near field" in this case will loosely refer to a volume of diameter 4-8 R<sub>c</sub>, centered on the working point and chimney of the test, where Rc is the radius of the blast cavity. For a given nuclear test, this information will collectively comprise the test's "hydrologic source term". This work relies on and is being supported by existing data, analyses, and interpretations that have been made at the Nevada Test Site (NTS) during the American nuclear test program and previous and ongoing studies related …
Date: March 23, 1999
Creator: Bourcier, W. L.; Bruton, C. J.; Carle, S. F.; Kersting, A. B.; Pawloski, G. A.; Rard, J. A. et al.
System: The UNT Digital Library
Existing Data Format for Two-Parameter Beta-Gamma Histograms for Radioxenon (open access)

Existing Data Format for Two-Parameter Beta-Gamma Histograms for Radioxenon

There is a need to establish a commonly acceptable format for storing beta-gated coincidence data for stations in the International Monitoring System (IMS) for the Comprehensive Nuclear-Test-Ban Treaty (CTBT). The current aerosol RMS type data format is not applicable for radioxenon in that the current format contains implicit assumptions specific to conventional gamma-ray spectrometry. Some assumptions in the current RMS format are not acceptable for the beta-gated spectra expected from the U.S. Department of Energy PNNL Automated Radioxenon Sampler-Analyzer (ARSA) and other similar systems under use or development from various countries. The RMS data format is not generally applicable for radioxenon measurements in the CTBT for one or more of the following main reasons: 1) The RMS format does not currently support 2-dimensional data. That is, the RMS data format is setup for a simple l-dimensional gamma-ray energy histogram. Current data available from the ARSA system and planned for other radioxenon monitors includes spectral information from gamma-rays and betas/conversion electrons. It is worth noting that the beta/conversion electron energy information will be used to separate the contributions from the different radioxenons. 2) The RMS data format assumes that the conversion between counts and activity can be calculated based (in part) …
Date: March 23, 1999
Creator: Bowyer, TW; Heimbigner, TR; McIntyre, JI; McKinnon, AD; Reeder, PL & Wittinger, E
System: The UNT Digital Library
Appropriations for FY2000: District of Columbia (open access)

Appropriations for FY2000: District of Columbia

Appropriations are one part of a complex federal budget process that includes budget resolutions, appropriations (regular, supplemental, and continuing) bills, rescissions, and budget reconciliation bills. This report is a guide to one of the 13 regular appropriations bills that Congress passes each year. It is designed to supplement the information provided by the House and Senate Appropriations Subcommittees on the District of Columbia.
Date: December 23, 1999
Creator: Boyd, Eugene
System: The UNT Digital Library
An Overview of Stationary Fuel Cell Technology (open access)

An Overview of Stationary Fuel Cell Technology

Technology developments occurring in the past few years have resulted in the initial commercialization of phosphoric acid (PA) fuel cells. Ongoing research and development (R and D) promises further improvement in PA fuel cell technology, as well as the development of proton exchange membrane (PEM), molten carbonate (MC), and solid oxide (SO) fuel cell technologies. In the long run, this collection of fuel cell options will be able to serve a wide range of electric power and cogeneration applications. A fuel cell converts the chemical energy of a fuel into electrical energy without the use of a thermal cycle or rotating equipment. In contrast, most electrical generating devices (e.g., steam and gas turbine cycles, reciprocating engines) first convert chemical energy into thermal energy and then mechanical energy before finally generating electricity. Like a battery, a fuel cell is an electrochemical device, but there are important differences. Batteries store chemical energy and convert it into electrical energy on demand, until the chemical energy has been depleted. Depleted secondary batteries may be recharged by applying an external power source, while depleted primary batteries must be replaced. Fuel cells, on the other hand, will operate continuously, as long as they are externally supplied …
Date: March 23, 1999
Creator: Brown, DR & Jones, R
System: The UNT Digital Library
Engineering task plan for determining the interstitial liquid level in tank 241-SY-101 utilizing a neutron probe in the multifunction instrument tree (open access)

Engineering task plan for determining the interstitial liquid level in tank 241-SY-101 utilizing a neutron probe in the multifunction instrument tree

This plan outlines the steps to be taken to modify existing neutron/gamma probe designs to allow insertion of these probes into the multifunction instrument trees (MITs) at tank 241-SY-101. The objective is to locate and track this tank's Interstitial Liquid Level (ILL). This plan provides scope, schedule, and cost estimates to achieve this objective, and assigns individual organizational responsibilities to carry out this task.
Date: February 23, 1999
Creator: CANNON, N.S.
System: The UNT Digital Library
Below Grade Assessment of Spent Nuclear Fuel (SNF) Cask Transport Route (open access)

Below Grade Assessment of Spent Nuclear Fuel (SNF) Cask Transport Route

The report provides an assessment of the route for the SNF Fuel transport system from the K Basins to the CVDF and to the CSB. Results include the identification of any underground structures or utilities traveled over by the transport, the overburden depths for all locations identified, evaluation of the loading conditions, and determination of the effects of the loads on the structures and utilities.
Date: November 23, 1999
Creator: CHENAULT, D.M.
System: The UNT Digital Library
CALDERON COKEMAKING PROCESS/DEMONSTRATION PROJECT (open access)

CALDERON COKEMAKING PROCESS/DEMONSTRATION PROJECT

This project deals with the demonstration of a coking process using proprietary technology of Calderon, with the following objectives geared to facilitate commercialization: (1) making coke of such quality as to be suitable for use in hard-driving, large blast furnaces; (2) providing proof that such process is continuous and environmentally closed to prevent emissions; (3) demonstrating that high-coking-pressure (non-traditional) coal blends which cannot be safely charged into conventional by-product coke ovens can be used in the Calderon process; (4) conducting a blast furnace test to demonstrate the compatibility of the coke produced; and (5) demonstrating that coke can be produced economically, at a level competitive with coke imports. The activities of the past quarter were focused on the following: Detailed studies of LTV's site for the installation of the commercial Demonstration Unit with site specific layouts; Environmental Work; Firm commitments for funding from the private sector; and Federal funding to complement the private contribution.
Date: June 23, 1999
Creator: Calderon, Albert
System: The UNT Digital Library
ROCK FALL CALCULATIONS FOR SINGLE CORROSION RESISTANT MATERIAL WASTE PACKAGES (open access)

ROCK FALL CALCULATIONS FOR SINGLE CORROSION RESISTANT MATERIAL WASTE PACKAGES

The purpose of this activity is to determine the structural performance of waste packages (WP) subject to rock fall design basis event (DBE) dynamic loads and document the calculation results that describe the threshold rock sizes for crack-initiation and through cracks in waste package shells. This activity is associated with the waste package design. AP-3.12Q, Revision 0, ICN 0, Calculations, is used to develop the calculation.
Date: March 23, 1999
Creator: Ceylan, Z.
System: The UNT Digital Library
K Basin Hazard Analysis (open access)

K Basin Hazard Analysis

None
Date: September 23, 1999
Creator: Chaffee, G. A.
System: The UNT Digital Library
Application of the Pegasus II Pulsed-Power Facility to the Study of Inertial Instability and Fracture of Cylindrical Tubes of Solid Aluminum (open access)

Application of the Pegasus II Pulsed-Power Facility to the Study of Inertial Instability and Fracture of Cylindrical Tubes of Solid Aluminum

Understanding the surface stability of metals undergoing dynamic fracture at shock breakout is important to several applications in metals processing. The advantages of using the Pegasus II facility to investigate the phenomena occurring at shock break out are described. As an example of the data collected, we concentrate on brief descriptions of two experiments that compared the tensile failure, i.e. ''spall'', patterns in the presence of sinusoidal perturbations seeded on the free inner surface of cylindrical samples of 3 types of Al. These samples were composed variously of soft Al 1100-O, structural grade Al 6061-T6, and ultra-pure 99.99% Al and were subjected to Taylor waves with shock pressures of 14 GPa. We show that the material behind the exiting surface undergoes a type of failure termed here ''microspall'', resulting in the production of a significant volume of low-density, probably granular, material. The failure mechanism, combined with the forces that cause inertial instability, leads to rapid pattern growth in the failed material and subsequent pattern growth on the surface. Pattern growth was studied as a function of perturbation wavelength and amplitude. The different Al samples vary by an order of magnitude in yield strength, and some increase in pattern instability was …
Date: June 23, 1999
Creator: Chandler, E. A.; Stokes, J.; Fulton, R. D.; Morgan, D. V.; Obst, A. W.; Oro, D. M. et al.
System: The UNT Digital Library
F-Area Hazardous Waste Management Facility Correction Action Report, Third and Fourth Quarter 1998, Volumes I and II (open access)

F-Area Hazardous Waste Management Facility Correction Action Report, Third and Fourth Quarter 1998, Volumes I and II

The groundwater in the uppermost aquifer beneath the F-Area Hazardous Waste Management Facility (HWMF), also known as the F-Area Seepage Basins, at the Savannah Site (SRS) is monitored periodically for selected hazardous and radioactive constituents. This report presents the results of the required groundwater monitoring program.
Date: April 23, 1999
Creator: Chase, J.
System: The UNT Digital Library
H-Area Hazardous Waste Management Facility Corrective Action Report, Third and Fourth Quarter 1998, Volumes I and II (open access)

H-Area Hazardous Waste Management Facility Corrective Action Report, Third and Fourth Quarter 1998, Volumes I and II

The groundwater in the uppermost aquifer beneath the H-Area Hazardous Waste Management Facility (HWMF), also known as the H-Area Seepage Basins, at the Savannah Site (SRS) is monitored periodically for selected hazardous and radioactive constituents. This report presents the results of the required groundwater monitoring program.
Date: April 23, 1999
Creator: Chase, J.
System: The UNT Digital Library
Laser science and technology update - 1999 (open access)

Laser science and technology update - 1999

The Laser Science and Technology (LS and T) Program's mission is to provide advanced solid-state laser and optics technologies for the Laboratory, government, and industry. The primary activities of LS and T in 1998 have been threefold--to complete the laser technology development and laser component testing for the ICF/NIF Program, to develop advanced solid-state laser systems and optical components for the Department of Defense (DoD) and DOE, and to address the needs of other government agencies and U.S. industry. After a four-year campaign, the LS and T Program achieved timely completion of the laser development effort for the NIF in 1998. This effort includes the special laser and component development, integrated performance testing on Beamlet, and detailed design and cost optimization using computation codes. Upon completing the Title II design review, the focus of the LS and T support effort has been shifted toward NIF laser hardware acquisition and deployment. The LS and T team also continued to develop advanced high-power solid-state laser technology for both the U.S. government and industrial partners. Progress was also made in several new areas: (a) diode-pumped solid-state laser drivers for high-energy-density physics and inertial fusion energy; (b) high-average-power femtosecond and nanosecond lasers for materials …
Date: September 23, 1999
Creator: Chen, H L & Powell, H T
System: The UNT Digital Library