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1,655
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442
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302
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169
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126
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55
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9
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9
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208
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197
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122
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88
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78
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48
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2,657 Matching Results
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An 8-Matrix Theory of the Vertex p - NN Based on the Strip Approximation
The present study was motivated by an attempt to understand low energy [formula] scattering within the framework of the bootstrap principle and the un-Reggeized version of the strip approximation. This work attempts to generate low energy [formula] scattering in the p(1,1) and p(3,3) states assuming the potential operating in these states is generated by the exchange of low mass meson states in the crossed t-channel and low mass baryon states in the crossed u channel. In particular, the p-meson is kept in channel t; the p mass and the coupling of [formula] and [formula] appear as parameters. The parameters of the nucleon and (3,3) poles are taken as the elements to be determined by self-consistency.
Date:
May 1964
Creator:
Sarkissian, M. Der
Object Type:
Report
System:
The UNT Digital Library
10-30 Bev/c ELASTIC SCATTERING OF $pi$$sup +-$+ p, p + p, /anti p/ + p AND K$sup +-$ + p OVER THE /t/ RANGE 0.0005 TO 1 (Bev/c)$sup 2$
None
Date:
July 28, 1964
Creator:
Foley, K. J.; Gilmore, R. S.; Jones, R. S.; Lindenbaum, S. J.; Love, W. A.; Ozaki, S. et al.
Object Type:
Report
System:
The UNT Digital Library
A-11 seven cluster model: FFL-10 solid core tests
This report summarizes the results of the seventh and last of a series of tests completed in the A-11 test program during the Contract Year 1964
Date:
December 18, 1964
Creator:
Cherish, P. & Leff, G.J.
Object Type:
Report
System:
The UNT Digital Library
A-11 seven cluster model: Phase V, flow induced vibration tests
This report summarizes the results of the fifth of a series of tests completed in the A-11 test program.
Date:
September 29, 1964
Creator:
Cherish, P. & Leff, G.J.
Object Type:
Report
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
40-Mw(e) Prototype High-Temperature Gas-Cooled Reactor Postconstruction Research and Development Program. Summary Progress Report for the Period Ending, October 1964
None
Date:
December 15, 1964
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
40-Mw(E) Prototype High-Temperature Gas-Cooled Reactor. Research and Development Program. Quarterly Progress Report for the Period Ending March 31, 1963
None
Date:
October 31, 1964
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
80" Bubble Chamber Expansion System Preliminary Operating Procedures
These procedures are intended to be used for the initial operation of the expansion system and serve as a basis for a more complete and revised form to be written once operating experience has been gained. An attempt has been made to offer a logical and systematic presentation to facilitate operation and maintenance of the system by the operating personnel. Thus, the sequence of valve actuations has been presented in matrix and check list form to minimize errors; this also has the advantage of making it easier to adapt certain expansion system procedures to programmed control by a process control computer.
Date:
January 7, 1964
Creator:
Goodzeit, C. L.
Object Type:
Report
System:
The UNT Digital Library
80" Bubble Chamber Expansion System Summary of Piston Motion Studies
Prior to assembly into the 80" bubble chamber, the expansion system was subjected to a series of tests to check piston dynamics and gain information on the reliability of the various components. Furthermore, the rest provided operating personnel with the opportunity to become familiar with the operation and maintenance of the expansion system. Two separate tests were performed with the apparatus that was located at the north end of the AGS experimental area; one during the week of Oct. 15 and the other during the week of Nov. 12. The system was run with helium gas supplied from AGS compressor room and the piston was operated at room temperature.
Date:
January 7, 1964
Creator:
Goodzeit, C. L.
Object Type:
Report
System:
The UNT Digital Library
80" Chamber - Low Energy Beams
One of the major, as well as first, decisions which must be taken on a large chamber is to decide on the direction of the magnetic field, i.e., vertical or horizontal. Either alternative has advantages and disadvantages ad it is the intention of this note to discuss these features.
Date:
January 3, 1964
Creator:
Rau, R. R.
Object Type:
Report
System:
The UNT Digital Library
100-KEW coolant backup adequacy
None
Date:
April 29, 1964
Creator:
Heacock, H. W.
Object Type:
Report
System:
The UNT Digital Library
105-F intermediate range test hole parameters
This report discusses 105 intermediate range test hole which was bored in 105-F to demonstrate reactor hole boring techniques. This test hole was then utilized to determine the performance of neutron sensitive gamma compensated ion chambers (CIC), the effectiveness of epoxy reactor shield plug designs, the compatability of the prototype.components intermediate range instrumentation, and demonstrate the performance of an intermediate range monitor system on a typical Hanford reactor application. In the process of determining the above information physical, nuclear, gamma, and temperature data was recorded as related to the 105-F intermediate range monitor test hole and is provided in this report.
Date:
November 16, 1964
Creator:
Erickson, G. L.
Object Type:
Report
System:
The UNT Digital Library
241-SX tank farm waste storage
Salt wastes from the Redox solvent extraction process have been routed to the 241-SX tank farm for storage since May 21, 1954. Tanks in this farm contain wastes from three types of irradiated uranium processing: (1) low (approximately 250 MWD/T) and (2) high (approximately 600 MWD/T) natural uranium; and (3) E-metal. It is estimated that approximately 1.6 Kgs of Am-Cm, 17 Kgs of Np-237, 20 Kgs of Pu and 8 tons of uranium are present in the sludges from wastes generated through 4-30-64. A total of 12.1 Kgs of the 29.1 Kgs of Np-237 estimated has been recovered or is present in the Redox Np-237 accumulation cycle as of 4-30-64. Because of the potential for unmeasured losses (such as Pu or U precipitates) the total plutonium and uranium may exceed the quantities stated herein. A breakdown of the estimates by tanks is provided.
Date:
September 3, 1964
Creator:
Hanson, G. L.
Object Type:
Report
System:
The UNT Digital Library
500-Thgc--a 500 Node Transient Heat Transfer Code
This document is a user manual for those who are familiar with problems 500 Node Transient Heat Transfer Code.
Date:
March 27, 1964
Creator:
Blaine, R. A. & Berland, R. F.
Object Type:
Report
System:
The UNT Digital Library
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 1
From introduction: "Summary report of the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company."
Date:
February 14, 1964
Creator:
General Electric Company
Object Type:
Report
System:
The UNT Digital Library
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 2
From introduction: "Presents the detailed description of a 1000 MW Electric Power Plant employing one or two Boiling Water Reactors as the steam source."
Date:
February 14, 1964
Creator:
General Electric Company
Object Type:
Report
System:
The UNT Digital Library
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 3
From introduction: "Contains the appendices and a complete set of drawings related to the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company for the United States Atomic Energy Commission."
Date:
February 14, 1964
Creator:
General Electric Company
Object Type:
Report
System:
The UNT Digital Library
1000-Mwe SGR. 90% ThO₂, 10% UO₂ Alternate Fuel Core Thermal and Hydraulic Analysis
The thermal and hydraulic core parameters were determined using the SORTD I code for 90% ThO/sub 2/, 10% UO/sub 2/ fuel both for (1) a core containing 592 fuel elements corresponding to the UC reference core with a maximum UC temperature of 2000 deg F and (2) a core containing 784 fuel elements corresponding to a UC core with a maximum UC temperature of 1750 deg F. Eighteen rod elements with 2.5 in./sup 2/ and 3.5 in./sup 2/ fuel areas, and 30 rod elements with 4.5 in./sup 2/ and 5.5 in./sup 2/ fuel areas are analyzed for 8 cases. (auth)
Date:
February 19, 1964
Creator:
Imig, J. K.
Object Type:
Report
System:
The UNT Digital Library
1000-Mwe Sgr and Prototype Evaluation Study. Supplement
None
Date:
July 1, 1964
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
1965 State legislative program of the Advisory Commission on Intergovernmental Relations
The ACIR Library is composed of publications that study the interactions between different levels of government. This document addresses the ACIR state legislative program.
Date:
October 1964
Creator:
United States. Advisory Commission on Intergovernmental Relations.
Object Type:
Book
System:
The UNT Digital Library
5th Annual Report
The ACIR Library is composed of publications that study the interactions between different levels of government. This document is an annual report.
Date:
January 1964
Creator:
United States. Advisory Commission on Intergovernmental Relations.
Object Type:
Book
System:
The UNT Digital Library
6144-Channel Time-of-Flight Analyzer
Report describing a 6144-channel analyzer designed and built for the purpose of analyzing time-of-flight during studies of slow neutron scattering at Hanford Laboratories. This includes descriptions of the analyzer, its logic and circuits, and its test mode.
Date:
September 1964
Creator:
Walker, R. A. & Russell, J. T.
Object Type:
Report
System:
The UNT Digital Library
630A MARITIME NUCLEAR STEAM GENERATOR. Progress Report No. 7
This progress report covers the period from November 15, 1963 to February 15, 1964. A study indicated that the most desirable type of blower drive turbine is one using main turbine throttie steam conditions and exhausting to the main turbine cross-over line. Preliminary planning for the initiation of a dynamic structural analyses of the overall steam generator was completed. External pressure loading and thermal stress calculations show that the calandria has a suitable design margin. A revised fuel latch operable from the rear face of the core was designed. A study was initiated to determine the feasibility of substituting Zircaloy for the stainless steel tubing within the active core. Preliminary sizing of control rod extensions and gang plates was completed. Initial loading of the second configuration of the 630A critical experiment reactor was completed. Detailed power distributions were measured in the 11 typical positions. Subcritical and critical rod worth curves were obtained in the critical experiment with up to 132 shim rods in the core. Moderator temperature coefficient measurements were made and agreed well with analytical data. Critical experiment correlation of fine radial power calculations in the revised mock-up showed good agreement. Performance specifications were prepared for a 1-Mw(e) power …
Date:
March 16, 1964
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
630A MARITIME NUCLEAR STEAM GENERATOR. Progress Report No. 8
None
Date:
May 1, 1964
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library