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Forestry in the 2007 Farm Bill
This report briefly describes the Agriculture Committees' jurisdiction over forestry, with examples of legislation addressed by the committees. It discusses forestry issues likely to be debated in the upcoming farm bill. It then presents information on the forestry provisions in the Administration's proposal for the 2007 farm bill, followed by the forestry provisions in the House-passed 2007 farm bill (the Farm, Nutrition, and Bioenergy Act of 2007, H.R. 2419) and in the Senate Committee draft bill (the Food and Energy Security Act of 2007).
Date:
January 25, 2008
Creator:
Gorte, Ross W.
System:
The UNT Digital Library
Agricultural Exports and the 2007 Farm Bill
This report assesses 2007 farm bill trade title provisions for U.S. agricultural export programs.
Date:
January 25, 2008
Creator:
Hanrahan, Charles E.
System:
The UNT Digital Library
San Jacinto River Authority Annual Financial Report: 2009
Comprehensive annual financial report of the San Jacinto River Authority discussing the finances and statistics for the activities of the agency during fiscal year 2009.
Date:
January 25, 2010
Creator:
San Jacinto River Authority (Tex.)
System:
The Portal to Texas History
Engineering task plan for flammable gas atmosphere mobile color video camera systems
This Engineering Task Plan (ETP) describes the design, fabrication, assembly, and testing of the mobile video camera systems. The color video camera systems will be used to observe and record the activities within the vapor space of a tank on a limited exposure basis. The units will be fully mobile and designed for operation in the single-shell flammable gas producing tanks. The objective of this tank is to provide two mobile camera systems for use in flammable gas producing single-shell tanks (SSTs) for the Flammable Gas Tank Safety Program. The camera systems will provide observation, video recording, and monitoring of the activities that occur in the vapor space of applied tanks. The camera systems will be designed to be totally mobile, capable of deployment up to 6.1 meters into a 4 inch (minimum) riser.
Date:
January 25, 1995
Creator:
Kohlman, E. H.
System:
The UNT Digital Library
Elimination of the Cold Outgassing for the Casting Operation : Final Report-Production Test 235-1
Objective: "Production Test 235-1 and an amendment, were written to outline the procedures for reducing the outgassing time and evaluating the effects of these reductions."
Date:
January 25, 1952
Creator:
Carlson, R. A.
System:
The UNT Digital Library
Permitting plan for project W-236B, initial pretreatment module
The Tank Waste Remediation System pretreatment process mission is to separate high-level and low-level waste fractions. A comprehensive review of environmental regulations has indicated that several environmental reviews, permits, and approvals are required before construction and operation of the facility. This revised document provides a summary of permit application data requirements, alternative strategies for permit completion and approval, as well as the probability of success for each alternative for the Initial Pretreatment Module resulting from recent revisions to the Tri-Party Agreement.
Date:
January 25, 1995
Creator:
Tollefson, K. S.
System:
The UNT Digital Library
Draft of physics sections to 100-N technical manual
The information presented is a collection of most of the physics information available for the New Production Reactor. The details of some of the physics information, particularly those dealing with exposure and temperature effects, are by no means to be considered the final word since there has been no experimental verification of these effects. However, the gross physics characteristics described are felt to be reasonable representations of the expected physics behavior of N Reactor and should serve as useful guides throughout the startup planning and initial operation.
Date:
January 25, 1963
Creator:
Nilson, R.
System:
The UNT Digital Library
Hazard analysis for 300 Area N Reactor Fuel Fabrication and Storage Facilty
This hazard analysis (HA) has been prepared for the 300 Area N Reactor Fuel Fabrication and Storage Facility (Facility), in compliance with the requirements of Westinghouse Hanford Company (Westinghouse Hanford) controlled manual WHC-CM-4-46, Nonreactor Facility Safety Analysis Manual, and to the direction of WHC-IP-0690, Safety Analysis and Regulation Desk Instructions, (WHC 1992). An HA identifies potentially hazardous conditions in a facility and the associated potential accident scenarios. Unlike the Facility hazard classification documented in WHC-SD-NR-HC-004, Hazard Classification for 300 Area N Reactor Fuel Fabrication and Storage Facility, (Huang 1993), which is based on unmitigated consequences, credit is taken in an HA for administrative controls or engineered safety features planned or in place. The HA is the foundation for the accident analysis. The significant event scenarios identified by this HA will be further evaluated in a subsequent accident analysis.
Date:
January 25, 1994
Creator:
Johnson, D. J. & Brehm, J. R.
System:
The UNT Digital Library
Dynamic analysis of the 7-GeV APS experiment hall foundation based on equivalent lumped parameter modeling
In this technical note, mass-spring-dashpot, also referred to as equivalent lumped parameter, models are employed to model the soil-foundation interaction of two typical floor segments from the 7-GeV APS experiment hall. Equivalent lumped parameter models have the advantage of being easy to apply and of readily allowing for parameter studies. Analysis requires knowledge of certain properties of the soil including density, shear wave velocity, and Poisson`s ratio, as well as knowledge of the degree of homogeneity of the underlying soil stratum. These data for the APS site were determined by a geotechnical investigation. A soil profile and pertinent data, obtained from crosshole seismic testing, are given. Natural frequencies and damping are calculated for the vertical, sliding, rocking, and coupled rocking/sliding modes of vibration. Subsequently, various corrections to account for modeling ``deficiencies`` are considered and their influences evaluated. The equivalent lumped parameter models were developed for machine foundations which, compared with the APS foundation, are smaller in plan dimension. Therefore, the applicability of these models in the analysis of the dynamic characteristics of the APS foundation must be established. The modeling is evaluated by applying the equivalent lumped parameter models in the analysis of large foundations for which test data exists. …
Date:
January 25, 1989
Creator:
Wambsganss, M. W.
System:
The UNT Digital Library
Magnetic field effects on endcap EM calorimetry in SDC
The SDC calorimeter will be immersed in a strong magnetic field in the endcap region because of the solenoid which supplies the SDC tracking field. This flux must be returned through the endcap region of the electromagnetic (EM) and hadronic (HAD) calorimeters. Since magnetic fields are known to induce changes in the light output of plastic scintillator, the endcap will need to be recalibrated once the solenoid is energized. In addition, gradients in the field will create nonuniformities in the calorimetric response. The ``induced constant term`` in the EM and HAD calorimeters due to the inhomogeneities induced by the magnetic field are here evaluated in order to see that SDC performance specifications are not compromised.
Date:
January 25, 1993
Creator:
Green, D.
System:
The UNT Digital Library
Hanford Atomic Products Operation monthly report, December 1954
This document presents a summary of work and progress at the Hanford Engineer Works for December 1954. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The Manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and Separation sections. The Engineering Department`s section summarizes work for the Technical, Design, and Project Sections. Costs for the various departments are presented in the Financial Department`s summary. The Medical, Radiological Sciences, Utilities and General Services, Employee and Public Relations, and Community Real Estate and Services departments have sections presenting their monthly statistics, work, progress, and summaries.
Date:
January 25, 1955
Creator:
unknown
System:
The UNT Digital Library
Effect of pretreating of host oil on coprocessing. Quarterly progress report, July 1, 1992--September 30, 1992
The principal objective of this research is to determine the role host petroleum-derived oils (1000{degrees}F+), as well as that of catalytically treated host oils, play when used as liquefaction solvents in coprocessing with coal. The host oils will be extensively characterized and then pretreated in a number of ways which involve catalytic reactions such as hydrogenation, hydrocracking, isomerization, and dehydrogenation. The pretreated oils will then be characterized. The effects of the host oil on coprocessing with coal will be compared to those obtained using catalytically modified heavy oils. When appropriate, model compounds will be used to study specific reactions brought about by the pretreatments. Highly dispersed iron catalysts modified by the addition of small amounts of other metals will be used to modify the chemical composition of the host oils. To date, five different pretreatment reactions have been carried out on the Amoco oil. Table 1 list some properties of this oil. Details of the reaction conditions used are given in Table 2. An objective of the pretreatment reactions is to increase hydrogen content without too significant a breakdown (cracking) of the hydrocarbon structures. Severe cracking could produce a light hydrocarbon solvent which may not be suitable for coprocessing because …
Date:
January 25, 1993
Creator:
Wender, I. & Tierney, J. W.
System:
The UNT Digital Library
[Cladding of uranium tubes]
None
Date:
January 25, 1956
Creator:
McBride, C. C.
System:
The UNT Digital Library
Proposal for charging the sixth rupture fuel element experiment: GEH-10, 46, 47
The objective of the test discussed in this report is to verify further the corrosion rate of irradiated tubular fuel elements under conditions of high specific power and central core temperatures. The fuel will be the inner component of an NPR fuel element assembly. A proposal to charge two tubular fuel elements into the GEH-P7 Loop has been made. The upper fuel element of the two has been irradiated to 1660 MWD/T in a Hanford reactor. A hydraulic cylinder will be attached to the upper fuel element. The hydraulic cylinder will be used to move a chisel along the outer surface of the upper fuel element and shear off a cap which has been welded over a hole through the cladding. The lower fuel element of the two will be used to add heat to the loop so that the desired loop water temperatures can be maintained.
Date:
January 25, 1961
Creator:
Call, R. L. & Kaulitz, D. C.
System:
The UNT Digital Library
A novel process for methanol synthesis. Final report
The use of methanol (MeOH) as a fuel additive and in MTBE production has renewed interest in the search for improved MeOH processes. Commercial processes are characterized by high pressures and temperatures with low per pass conversion (10--12%). Efforts are underway to find improved MeOH synthesis processes. A slurry phase ``concurrent`` synthesis of MeOH/methyl formate (MeF) which operates under relatively mild conditions (100{degrees}C lower than present commercial processes) was the subject of investigation in this work. Evidence for a reaction scheme involving the carbonylation of MeOH to MeF followed by the hydrogenolysis of MeF to two molecules of MeOH -- the net result being the reaction of H{sub 2} with CO to give MeOH via MeF, is presented. Up to 90% per pass conversion and 98% selectivity to methanol at rates comparable to commercial processes have been obtained in spite of the presence of as much as 10,000 ppM CO{sub 2} and 3000 ppM H{sub 2}O in the gas and liquid respectively. The effect of process parameters such as temperature, pressure, H{sub 2}/CO ratio in the reactor, flow rate and catalyst loading were also investigated. The use of temperatures above 170{degrees}C at a pressure of 50 atm results in MeF …
Date:
January 25, 1994
Creator:
Tierney, J. W. & Wender, I.
System:
The UNT Digital Library
300 Area, January 15--January 21
This report from the reactor fuel manufacturing facilities at Hanford highlights extrusion, canning, and welding operations. Processing of thorium and bismuth is discussed. Radiography of fuels revealed voids that conformed underweight reject measurements.
Date:
January 25, 1946
Creator:
Kidder, C. P.
System:
The UNT Digital Library
Aerodynamic Design of Heavy Vehicles Reporting Period September 2001 through January 15, 2002
Activities for this first quarter include continued effort in simulating the experiments performed in the NASA 7-ft x 10-ft wind tunnel with the GTS geometry using both LLNL's advanced computational tools and NASA's Overflow code. Along with this analysis effort, we continue to implement advanced algorithms in LLNL's models to improve simulation speed and accuracy and to verify and validate these advanced simulation tools.
Date:
January 25, 2002
Creator:
McCallen, R.; Salari, K.; Ortega, J.; Yen-Nakafuji, D.; Dunn, T.; Browand, F. et al.
System:
The UNT Digital Library
TRU Waste Cyclone Drum Incinerator and Treatment System: April--June 1977.
None
Date:
January 25, 1978
Creator:
Luthy, Don F.; Elswick, Toby C. & Doty, Jay W.
System:
The UNT Digital Library
Warp failure of a thirty-six inch long uranium 2 wt % zirconium alloy tubular fuel element, PT-IP-250-A (RM-568). Final report
The N-Reactor will be charged with tubular fuel elements consisting of two components. Both components, an outer tube with a concentric inner tube, have a uranium core, coextruded with a Zircaloy-2 cladding. The testing in support of N-Reactor fuels has been conducted in the experimental loops in the K-East Reactor. Although the process tubes in the KER loops are smaller than the proposed N-Reactor process tubes, the test loops operate at the water temperatures and pressures that will exist in the N-Reactor. To obtain the desired heat fluxes and core temperatures in KER loop test elements, enriched uranium fuel was used. The cladding surface temperatures and fuel temperatures were near anticipated N-Reactor values. Test conditions, results, and conclusions are presented.
Date:
January 25, 1963
Creator:
Kuhlken, L. E.
System:
The UNT Digital Library
Government Access to Phone Calling Activity and Related Records: Legal Authorities
This report summarizes statutory authorities regarding access by the government, for wither foreign intelligence or law enforcement purposes, to information related to telephone calling patterns or practices. Where pertinent, it also discusses statutory prohibitions against accessing or disclosing such information, along with relevant exceptions to those prohibitions.
Date:
January 25, 2007
Creator:
Bazan, Elizabeth B.; Stevens, Gina Marie & Yeh, Brian T.
System:
The UNT Digital Library
Farm Credit System
This report provides information about the farm credit system which provides financial cooperative lending to agricultural and aquatic producers, rural homeowners etc.
Date:
January 25, 2007
Creator:
Monke, Jim
System:
The UNT Digital Library
The Federal Government Debt: Its Size and Economic Significance
None
Date:
January 25, 2007
Creator:
Cashell, Brian W.
System:
The UNT Digital Library
A Separate Consumer Price Index for the Elderly?
None
Date:
January 25, 2008
Creator:
unknown
System:
The UNT Digital Library
Emergency Management Preparedness Standards: Overview and Options for Congress
This report presents background information on the commission's findings, on emergency response standards, and on options Congress might consider to address issues related to emergency preparedness standards.
Date:
January 25, 2006
Creator:
Bea, Keith
System:
The UNT Digital Library