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D-0 South End Cap Calorimeter Cold Test Results

Description: The South endcap calorimeter vessel was moved into Lab A on Sept. 18, 1990. A cooldown of the pressure vessel with liquid nitrogen was performed on Sept. 26 to check the vessel's integrity. With the pressure vessel cold, the insulating vacuum was monitored for leaks. Through out the testing, the insulating vacuum remained good and the vessel passed the test. The cold test was carried out per the procedures of D-Zero engineering note 3740.220-EN-250. The test was very similar to the cold test pe… more
Date: November 26, 1990
Creator: Rucinski, R.
open access

1-1/2-Loop Semiscale Isothermal Test Program: Program and System Description in Support of Experiment Data Reports.

Description: The isothermal test series is part of the Semiscale Blowdown and Emergency Core Cooling (ECC) Project conducted by Aerojet Nuclear Company for the U. S. Atomic Energy Commission. The test series consisted of ten blowdown tests and five hot-wall tests with emphasis on emergency core coolant delivery. The blowdown tests were conducted to investigate the effects of lower plenum geometry, heat transfer configuration, ECC injection location, downcomer gap size, and break size.
Date: February 1, 1974
Creator: Aerojet Nuclear Company
open access

1/2/Sup +/. -->. 1/2/Sup -/ Beta Decay of /Sup 19/Ne and the Parity Nonconserving Nn Force

Description: A branching ratio of (1.20 +- 0.20) x 10/sup -4/ is obtained for the ..beta../sup +/ decay of /sup 19/Ne to the 110 keV 1/2/sup -/ level of /sup 19/F. This transition (presumably dominated by the ..delta..J/sup ..pi../ = 0/sup -/ axial charge operator) provides a crucial test of wavefunctions used in interpreting the parity mixing of the ground and 110 keV levels of /sup 19/F. These wavefunctions, which yield a parity mixing larger than that observed experimentally, also predict too large a ..b… more
Date: 1978~
Creator: Adelberger, E. G.; Hindi, M. M.; Hoyle, C. D.; Swanson, H. E. & Von Lintig, R. D.
open access

1,3,5-trichlorobenzene progress report, July--September 1976

Description: Research progress is reported on the following topics: (1) conversion of 2, 4, 6-trichloroaniline to 2, 4, 6-trichloronitrobenzene; (2) nitration of 1, 2, 4-trichlorobenzene; (3) exploration of the route to 1, 3, 5-trichlorobenzene via aniline; and (4) direct nitration of trichloroaniline. (TFD)
Date: September 1, 1976
Creator: Estes, Z. L.
open access

A 1. 5--4 Kelvin detachable cold-sample transfer system: Application to inertially confined fusion with spin-polarized hydrogens fuels

Description: A compact cold-transfer apparatus for engaging and retrieving samples at liquid helium temperatures (1.5--4K), maintaining the samples at such temperatures for periods of hours, and subsequently inserting them in diverse apparatuses followed by disengagement, is described. The properties of several thermal radiation-insulating shrouds, necessary for very low sample temperatures, are presented. The immediate intended application is transportable target-shells containing highly spin-polarized deu… more
Date: January 1, 1990
Creator: Alexander, N.; Barden, J.; Fan, Q. & Honig, A.
open access

1.5% boron, stainless steel

Description: A test report on the brittleness of borated steel to be used in the KIWI B-5 shield capsules.
Date: September 19, 1962
Creator: Schreiber, J.J.
open access

1.8.2.1.2 Site system engineering implementation Fiscal Year 1998 multi-year work plan

Description: Manage the Site Systems Engineering process to provide a traceable, integrated, requirements-driven, and technically defensible baseline., Through the Site Integration Group, Systems Engineering ensures integration of technical activities across all site projects. Systems Engineering`s primary interfaces are with the Project Direction Office and with the projects, as well as with the Planning organization.
Date: October 3, 1997
Creator: Ferguson, J. E.
open access

1.8.3 Site system engineering FY 1997 program plan

Description: The FY 1997 Multi-Year Work Plan (MYWP) technical baseline describes the functions to be accomplished and the technical standards that govern the work. The following information is provided in this FY 1997 MYWP: technical baseline, work breakdown structure, schedule baseline, cost baseline, and execution year.
Date: September 13, 1996
Creator: Grygiel, M. L.
open access

1/12-Scale mixing interface visualization and buoyant particle release tests in support of Tank 241-SY-101 hydrogen mitigation

Description: In support of tank waste safety programs, visualization tests were performed in the 1/12-scale tank facility, using a low-viscosity simulant. The primary objective of the tests was to obtain video records of the transient jet-sludge interaction. The intent is that these videos will provide useful qualitative data for comparison with model predictions. Two tests were initially planned: mixing interface visualization (MIV) and buoyant particle release (BPR). Completion of the buoyant particle rel… more
Date: October 1, 1993
Creator: Eschbach, E. J. & Enderlin, C. W.
open access

1/12-scale physical modeling experiments in support of tank 241-SY- 101 hydrogen mitigation

Description: Hanford tank 241-SY-101 is a 75-ft-dia double-shell tank that contains approximately 1.1 M gal of radioactive fuel reprocessing waste. Core samples have shown that the tank contents are separated into two main layers, a article laden supernatant liquid at the top of the tank and a more dense slurry on the bottom. Two additional layers may be present, one being a potentially thick sludge lying beneath the slurry at the bottom of the tank and the other being the crust that has formed on the surfa… more
Date: January 1, 1993
Creator: Fort, J. A.; Bamberger, J. A.; Bates, J. M.; Enderlin, C. W. & Elmore, M. R.
open access

1/12-scale physical modeling experiments in support of tank 241-SY- 101 hydrogen mitigation. Final report

Description: Hanford tank 241-SY-101 is a 75-ft-dia double-shell tank that contains approximately 1.1 M gal of radioactive fuel reprocessing waste. Core samples have shown that the tank contents are separated into two main layers, a article laden supernatant liquid at the top of the tank and a more dense slurry on the bottom. Two additional layers may be present, one being a potentially thick sludge lying beneath the slurry at the bottom of the tank and the other being the crust that has formed on the surfa… more
Date: January 1993
Creator: Fort, J. A.; Bamberger, J. A.; Bates, J. M.; Enderlin, C. W. & Elmore, M. R.
open access

1/12-Scale scoping experiments to characterize double-shell tank slurry uniformity: Test plan

Description: Million gallon double-shell tanks (DSTs) at Hanford are used to store transuranic, high-level, and low-level wastes. These wastes generally consist of a large volume of salt-laden solution covering a smaller volume of settled sludge primarily containing metal hydroxides. These wastes will be retrieved and processed into immobile waste forms suitable for permanent disposal. The current retrieval concept is to use submerged dual-nozzle pumps to mobilize the settled solids by creating jets of flui… more
Date: October 1994
Creator: Bamberger, J. A. & Liljegren, L. M.
open access

1.5D Quasilinear Model for Alpha Particle-TAE Interaction in ARIES ACT-I

Description: We study the TAE interaction with alpha particle fusion products in ARIES ACT-I using the 1.5D quasilinear model. 1.5D uses linear analytic expressions for growth and damping rates of TAE modes evaluated using TRANSP pro les to calculates the relaxation of pressure pro les. NOVA- K simulations are conducted to validate the analytic dependancies of the rates, and to normalize their absolute value. The low dimensionality of the model permits calculating loss diagrams in large parameter spaces.
Date: January 30, 2013
Creator: Ghantous, K.; Gorelenkov, N. N.; Kessel, C. & Poli, F.
open access

1/6TH SCALE STRIP EFFLUENT FEED TANK-MIXING RESULTS USING MCU SOLVENT

Description: The purpose of this task was to determine if mixing was an issue for the entrainment and dispersion of the Modular Caustic Side Solvent Extraction (CSSX) Unit (MCU) solvent in the Defense Waste Processing Facility (DWPF) Strip Effluent Feed Tank (SEFT). The MCU strip effluent stream containing the Cs removed during salt processing will be transferred to the DWPF for immobilization in HLW glass. In lab-scale DWPF chemical process cell testing, mixing of the solvent in the dilute nitric acid solu… more
Date: February 1, 2006
Creator: Hansen, E.
open access

E-1 CAM Revision 4

Description: this report is a descriptive journey of the E-1 CAM Revision 4
Date: April 30, 1970
open access

1-Dimensional simulation of thermal annealing in a commercial nuclear power plant reactor pressure vessel wall section

Description: The objective of this work was to provide experimental heat transfer boundary condition and reactor pressure vessel (RPV) section thermal response data that can be used to benchmark computer codes that simulate thermal annealing of RPVS. This specific protect was designed to provide the Electric Power Research Institute (EPRI) with experimental data that could be used to support the development of a thermal annealing model. A secondary benefit is to provide additional experimental data (e.g., t… more
Date: November 1, 1994
Creator: Nakos, J. T.; Rosinski, S. T. & Acton, R. U.
open access

01-ERD-111 - The Development of Synthetic High Affinity Ligands

Description: The aim of this project was to develop Synthetic High-Affinity Ligands (SHALs), which bind with high affinity and specificity to proteins of interest for national security and cancer therapy applications. The aim of producing synthetic ligands for sensory devices as an alternative to antibody-based detection assays and therapeutic agents is to overcome the drawbacks associated with antibody-based in next-generation sensors and systems. The focus area of the project was the chemical synthesis of… more
Date: February 5, 2004
Creator: Perkins, J; Balhorn, R; Cosman, M; Lightstone, F & Zeller, L
open access

1 - FFTF-LMFBR seal test program, July-September 1974

Description: The objectives of the general seal test program are to: (1) conduct static and dynamic tests to demonstrate or determine the mechanical performance of full-size (cross-section) FFTF fuel transfer machine and reactor vessel head seals intended for use in a sodium vapor - inert gas environment, (2) demonstrate that these FFTF seals or new seal configurations provide acceptable fission product and cover gas retention capabilities at Clinch River Breeder Reactor Plant (CRBRP) operating environmenta… more
Date: January 1, 1974
Creator: Kurzeka, W. & Oliva, R.
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