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1- and 2-D computer analysis of an HDL stress wave switch, 1974, June 25
None
Date:
June 25, 1974
Creator:
Mahler, J.
Object Type:
Report
System:
The UNT Digital Library
10-MWe pilot-plant-receiver panel test requirements document solar thermal test facility
Testing plans for a full-scale test receiver panel and supporting hardware which essentially duplicate both physically and functionally, the design planned for the Barstow Solar Pilot Plant are presented. Testing is to include operation during normal start and shutdown, intermittent cloud conditions, and emergencies to determine the panel's transient and steady state operating characteristics and performance under conditions equal to or exceeding those expected in the pilot plant. The effects of variations of input and output conditions on receiver operation are also to be investigated. Test hardware are described, including the pilot plant receiver, the test receiver assembly, receiver panel, flow control, electrical control and instrumentation, and structural assembly. Requirements for the Solar Thermal Test Facility for the tests are given. The safety of the system is briefly discussed, and procedures are described for assembly, installation, checkout, normal and abnormal operations, maintenance, removal and disposition. Also briefly discussed are quality assurance, contract responsibilities, and test documentation. (LEW)
Date:
August 25, 1978
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
15.4% CuIn1-XGaXSe2-Based Photovoltaic Cells from Solution-Based Precursor Films
We have fabricated 15.4%- and 12.4%-efficient CuIn1-XGaXSe2 (CIGS)-based photovoltaic devices from solution-based electrodeposition (ED) and electroless-deposition (EL) precursors. As-deposited precursors are Cu-rich CIGS. Additional In, Ga, and Se are added to the ED and EL precursor films by physical vapor deposition (PVD) to adjust the final film composition to CuIn1-XGaXSe2. The ED and EL device parameters are compared with those of a recent world record, an 18.8%-efficient PVD device. The tools used for comparison are current voltage, capacitance voltage, and spectral response characteristics.
Date:
May 25, 1999
Creator:
Bhattacharya, R. N.; Batchelor, W.; Contreras, M. A.; Noufi, R. N. (National Renewable Energy Laboratory); Hiltner, J. F. & Sites, J. R. (Department of Physics, Colorado State University)
Object Type:
Article
System:
The UNT Digital Library
The 25-Inch Liquid Hydrogen Bubble Chamber
None
Date:
May 25, 1964
Creator:
Barrera, F.; Byrns, R. A.; Eckman, G. J.; Hernandez, H. P.; Norgren, D. U.; Shand, A. J. et al.
Object Type:
Report
System:
The UNT Digital Library
30 years of high-intensity negative ion sources for accelerators
Thirty years ago, July 1, 1971, significant enhancement of negative ion emission from a gas discharge following an admixture of cesium was observed for the first time. This observation became the basis for the development of Surface Plasma Sources (SPS) for efficient production of negative ions from the interaction of plasma particles with electrodes on which adsorbed cesium reduced the surface work-function. The emission current density of negative ions increased rapidly from j {approximately} 10 mA/cm{sup 2} to 3.7 A/cm{sup 2} with a flat cathode and up to 8 A/cm{sup 2} with an optimized geometrical focusing in the long pulse SPS, and to 0.3 A/cm{sup 2} for DC SPS, recently increased up to 0.7 A/cm{sup 2}. Discovery of charge-exchange cooling helped decrease the negative ion temperature T below 1 eV, and increase brightness by many orders to a level compatible with the best proton sources, B = j/T> 1 A/cm{sup 2} eV. The combination of the SPS with charge-exchange injection improved large accelerators operation and has permitted beam accumulation up to space-charge limit and overcome this limit several times. The early SPS for accelerators have been in operation without modification for {approximately} 25 years. Advanced version of the SPS for …
Date:
July 25, 2001
Creator:
Dudnikov, Vadim
Object Type:
Article
System:
The UNT Digital Library
44-BWR WASTE PACKAGE LOADING CURVE EVALUATION
The objective of this calculation is to evaluate the required minimum burnup as a function of initial boiling water reactor (BWR) assembly enrichment that would permit loading of spent nuclear fuel into the 44 BWR waste package configuration as provided in Attachment IV. This calculation is an application of the methodology presented in ''Disposal Criticality Analysis Methodology Topical Report'' (YMP 2003). The scope of this calculation covers a range of enrichments from 0 through 5.0 weight percent (wt%) U-235, and a burnup range of 0 through 40 GWd/MTU. This activity supports the validation of the use of burnup credit for commercial spent nuclear fuel applications. The intended use of these results will be in establishing BWR waste package configuration loading specifications. Limitations of this evaluation are as follows: (1) The results are based on burnup credit for actinides and selected fission products as proposed in YMP (2003, Table 3-1) and referred to as the ''Principal Isotopes''. Any change to the isotope listing will have a direct impact on the results of this report. (2) The results of 100 percent of the current BWR projected waste stream being able to be disposed of in the 44-BWR waste package with Ni-Gd Alloy …
Date:
August 25, 2004
Creator:
Scaglione, J.M.
Object Type:
Report
System:
The UNT Digital Library
100 Area D4 Project Building Completion Report May 2006 - June 2007
This report documents the decontamination and decommissioning (D&D) and the demolition of the 153-N, 1515-N, 1516-N, 1517-N, 1518-N, 1519-N, 1331-N, 1332-N, and 181-NC facilities in the 100 Area of the Hanford Site. The D&D and demolition of these facilities included characterization, engineering, removal of hazardous and radiologically contaminated materials, equipment removal, utility disconnection, deactivation, decontamination, demolition of the structure, and removal of the remaining slabs.
Date:
July 25, 2007
Creator:
Ison, E. G.
Object Type:
Report
System:
The UNT Digital Library
100 Areas, January 15 through January 21
This report gives the weekly progress for the B, D, and F piles. The report also gives a brief discussion of the following activities: process water control and pressure drop studies; purging of D, B, and F piles; slug corrosion studies; tube corrosion studies; thimble corrosion studies; and graphite expansion studies.
Date:
January 25, 1946
Creator:
Jordan, W. E.
Object Type:
Report
System:
The UNT Digital Library
100 Areas technical activities report: Engineering, June 1947
There were no cases of unusual blistering of slugs being followed under Production Tests. Two normal production tubes were borescoped following trouble with discharge. In Tube 3188-D a distorted slug became stuck in the region of sharp curvature near the inner end of the rear gun barrel; this is the first time this phenomenon has occurred. Examination of irradiated slugs of rolled metal after normal exposure indicates that rolled material has no particular advantages over extruded material from the standpoint of blistering. However, no extensively blistered pieces were found in either the rolled metal are being held for more extended exposure. Inspection of a large number of Van Stone flanges in the D and F Piles has confirmed that the inlet flanges are in generally good condition but that the rear Van Stone flanges of tubes in the 0.140-inch orifice sone of both piles were badly corroded and generally contained deep pits that extended about half-way through the flange. The Van Stone test units are to be installed unshielded in the risor room at the rear of the D Pile, since the shielding required in the X Sample Room exceeded the allowable floor loading. Recent experimental observations indicate that solid …
Date:
June 25, 1947
Creator:
Woods, W. K.
Object Type:
Report
System:
The UNT Digital Library
101-SY waste sample speed of sound/rheology testing for sonic probe program
One problem faced in the clean-up operation at Hanford is that a number of radioactive waste storage tanks are experiencing a periodic buildup and release of potentially explosive gases. The best known example is Tank 241-SY-101 (commonly referred to as 101-SY) in which hydrogen gas periodically built up within the waste to the point that increased buoyancy caused a roll-over event, in which the gas was suddenly released in potentially explosive concentrations (if an ignition source were present). The sonic probe concept is to generate acoustic vibrations in the 101-SY tank waste at nominally 100 Hz, with sufficient amplitude to cause the controlled release of hydrogen bubbles trapped in the waste. The sonic probe may provide a potentially cost-effective alternative to large mixer pumps now used for hydrogen mitigation purposes. Two important parameters needed to determine sonic probe effectiveness and design are the speed of sound and yield stress of the tank waste. Tests to determine these parameters in a 240 ml sample of 101-SY waste (obtained near the tank bottom) were performed, and the results are reported.
Date:
July 25, 1994
Creator:
Cannon, N. S.
Object Type:
Report
System:
The UNT Digital Library
105-K east sandfilter backwash line sample analysis report. Second campaign
This project seeks to produce uranium (U) and plutonium (Pu) analyses of samples taken from the KE basin filter backwash line each time the sand filter is backwashed. K Basin operations will use the analytical results to determine additions of fissile materials to the backwash sludge pit and thereby maintain a running inventory of fissile elements in the pit. K Basin Operations must not exceed a certain total inventory in order to be within a criticality specification. The second campaign of this project consisted of three samples, numbered by the customer 208KEB, 209KEB, and 210KEB.
Date:
January 25, 1996
Creator:
Miller, George L.
Object Type:
Report
System:
The UNT Digital Library
105-K east sandfilter backwash line sample analysis report: Third campaign
This project seeks to produce uranium (U) and plutonium (Pu) analyses of samples taken from the KE basin filter backwash line each time the sand filter is backwashed. K Basin operations will use the analytical results to determine additions of fissile materials to the backwash sludge pit and thereby maintain a running inventory of fissile elements in the pit. K Basin operations must not exceed a certain total inventory in order to be within a criticality specification. The third campaign of this project consisted of three samples, numbered by the customer 245KEB, 246KEB, and 247KEB. A revised letter of instruction controlled their processing.
Date:
January 25, 1996
Creator:
Miller, George L. & Bechtold, D. B.
Object Type:
Report
System:
The UNT Digital Library
200 area effluent treatment facility basic support systems operational test specification
This document identifies the test requirements for the 200 Area Effluent Treatment Facility Basic Support Systems
Date:
February 25, 1997
Creator:
Crane, A.F., Fluor Daniel Hanford
Object Type:
Report
System:
The UNT Digital Library
241-AN-A pit leak detection ANA-WT-LDSTA-331 acceptance test procedure
This document describes the method used to test design criteria for Safety Class, Intrinsically Safe leak detector system installed in 241-AN-A Valve Pit located at 200E Tank Farms. The purpose of this Procedure is to demonstrate that the pit leak detection relay cabinet and intrinsically safe probe circuit is fully operable.
Date:
August 25, 1999
Creator:
VANDYKE, D.W.
Object Type:
Report
System:
The UNT Digital Library
241-AN-A valve pit manifold valves and position indication acceptance test procedure
This document describes the method used to test design criteria for gear actuated ball valves installed in 241-AN-A Valve Pit located at 200E Tank Farms. The purpose of this procedure is to demonstrate the following: Equipment is properly installed, labeled, and documented on As-Built drawings; New Manifold Valves in the 241-AN-A Valve Pit are fully operable using the handwheel of the valve operators; New valve position indicators on the valve operators will show correct valve positions; New valve position switches will function properly; and New valve locking devices function properly.
Date:
August 25, 1999
Creator:
VANDYKE, D.W.
Object Type:
Report
System:
The UNT Digital Library
241-AN-B pit leak detection ANA-WT-LDSTA-231 acceptance test procedure
This document describes the method used to test design criteria for Safety Class, Intrinsically Safe leak detector system installed in 241-AN-B Valve Pit located at 200E Tank Farms. The purpose of this Procedure is to demonstrate that the pit leak detection relay cabinet and intrinsically safe probe circuit is fully operable.
Date:
August 25, 1999
Creator:
VANDYKE, D.W.
Object Type:
Report
System:
The UNT Digital Library
241-AN-B valve pit manifold valves and position indication acceptance test procedure
This document describes the method used to test design criteria for gear actuated ball valves installed in 241-AN-B Valve Pit located at 200E Tank Farms. The purpose of this procedure is to demonstrate the following: Equipment is properly installed, labeled, and documented on As-Built drawings; New Manifold Valves in the 241-AN-B Valve Pit are fully operable using the handwheel of the valve operators; New valve position indicators on the valve operators will show correct valve positions; New valve position switches will function properly; and New valve locking devices function properly.
Date:
August 25, 1999
Creator:
VANDYKE, D.W.
Object Type:
Report
System:
The UNT Digital Library
241-SY Tank Farm Construction Extent of Condition Review for Tank Integrity
This report provides the results of an extent of condition construction history review for tanks 241-SY-101, 241-SY-102, and 241-SY-103. The construction history of the 241-SY tank farm has been reviewed to identify issues similar to those experienced during tank 241-AY-102 construction. Those issues and others impacting integrity are discussed based on information found in available construction records, using tank 241-AY-102 as the comparison benchmark. In the 241-SY tank farm, the third DST farm constructed, refractory quality and stress relief were improved, while similar tank and liner fabrication issues remained.
Date:
July 25, 2013
Creator:
Barnes, Travis J.; Boomer, Kayle D.; Gunter, Jason R. & Venetz, Theodore J.
Object Type:
Report
System:
The UNT Digital Library
241-U-701 new compressor building and instrument air piping analyses
Building anchorage analysis is performed to qualify the design of the new compressor building foundation given in the ECN ``241-U-701 New Compressor Building.`` Recommendations for some changes in the ECN are made accordingly. Calculations show that the 6-in.-slab is capable of supporting the pipe supports, and that the building foundation, air compressor and dryer anchorage, and electric rack are adequate structurally. Analysis also shows that the instrument air piping and pipe supports for the compressed air system meet the applicable code requirements and are acceptable. The building is for the U-Farm instrument air systems.
Date:
August 25, 1994
Creator:
Huang, F. H.
Object Type:
Report
System:
The UNT Digital Library
242-A Campaign 99-1 process control plan
242-A Evaporator 99-1 will process approximately one million gallons of waste from tank 102-AW in June 1999. The process control Plan provides a general description of activities, which will occur during 242-A Evaporator Campaign 99-1 and to document analyses conducted to demonstrate that 102-AW waste is acceptable for processing. Predict is a registered trademark of Risk Decisions England Corporation, United Kingdom.
Date:
August 25, 1999
Creator:
Le, E. Q.
Object Type:
Report
System:
The UNT Digital Library
244-CR Vault Interim Stabilization Project Plan
The 244-CR Vault is a two-level, multi-cell structure of reinforced concrete constructed below grade. The lower cell contains four individual compartments, each containing a steel process storage tank and equipped with a concrete sump. The upper cell contains the piping and support equipment, and has two compartments for each of the tanks. The ''pump pit'' is accessed by the removal of concrete cover blocks, while the smaller ''riser pit'' is accessed by steel cover plates. The facility most recently was used as a double-contained receiver tank (DCRT). A DCRT is a type of waste transfer tank that together with its related equipment constitutes a short-term storage area for liquid waste and has a pump pit for waste transfer operations. This vault most recently was used for short-term storage and waste routing for saltwell liquid pumped from the 241-C Tank Farm in the 200 East Area. Waste transfer lines are connected inside the pump pit by a jumper installed between connecting nozzles. An active ventilation system is in operation at the 244-CR vault. Ventilation supply air enters the upper vault section through an inlet header with some leakage through the spaces between the cell cover blocks. The upper and lower vaults …
Date:
April 25, 2000
Creator:
PARKMAN, D.B.
Object Type:
Report
System:
The UNT Digital Library
300 Area D4 Project 3rd Quarter Fiscal Year 2006 Building Completion Report
This report documents the deactivation, decontamination, decommissioning, and demolition of five buildings in the 300 Area of the Hanford Site. The D4 of these facilities included characterization, engineering, removal of hazardous and radiologically contaminated materials, equipment removal, utility disconnection, deactivation, decontamination, demolition of the structure, and stabilization or removal of the remaining slab and foundation as appropriate.
Date:
September 25, 2006
Creator:
Smith, D. S.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
309 Building fire protection analysis and justification for deactivation of sprinkler system. Revision 1
Provide a `graded approach` fire evaluation in preparation for turnover to Environmental Restoration Contractor for D&D. Scope includes revising 309 Building book value and evaluating fire hazards, radiological and toxicological releases, and life safety issues.
Date:
June 25, 1997
Creator:
Conner, R. P.
Object Type:
Report
System:
The UNT Digital Library