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AN ADVANCED SODIUM-GRAPHITE REACTOR NUCLEAR POWER PLANT

Description: An advanced sodium-cooled, graphite-moderated nuclear power plant is described which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency. Steam is generated at 2400 psig, superheated to 1050 deg F and, after partial expansion in the turbine, reheated to 1000 deg F. Net thermal efficiency of the plant is 42.3%. In a plant sized to produce a net electrical output of 256 Mw, the estimated cost is 8232/kw. Estimated cost of power generation is 6.7 mil… more
Date: March 15, 1960
Creator: Churchill, J. R. & Renard, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Antiproton-Proton Cross Sections at 1.0, 1.25, and 2.0 BeV

Description: The antiproton--proton interaction was studied at three energies, 2.0, 1.25, and 0.98 Bev. Antiprotons produced internally in the Revatron and channeled externally by a system of bending magnets and quadrupoles were selected from background particles by using a gas Cherenkov counter and scintillation counters. At the two lower energies, an electrostatic-magnetic velocity spectrometer was used to reject background particles. A liquidhydrogen target was completely surrounded by scintillation coun… more
Date: March 15, 1960
Creator: Coombes, C. A.
Item Type: Refine your search to only Thesis or Dissertation
Partner: UNT Libraries Government Documents Department
open access

Graphite burnout, interim report on IP-25-A (PT-105-532-E)

Description: Graphite reacts with such gases as CO{sub 2}, O{sub 2}, or water vapor to form gaseous oxides of carbon. In the case of CO{sub 2}-graphite interaction, the reaction rate is not significant until about 550 C. Water oxidizes graphite, very roughly, three times faster than CO{sub 2}. Air will oxidize graphite appreciably at temperatures below 500 C. Graphite removal from Hanford reactors is very important, since graphite is used both as a structural support and a moderator for neutrons. Griggs has… more
Date: March 15, 1960
Creator: Ryan, B. A. & de Halas, D. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hanford Laboratories Operation monthly activities report, February 1960

Description: This is the monthly report for the Hanford Laboratories Operation, February, 1960. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: March 15, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

An IBM-704 Code for a Harmonics Method Applied to Two-Region Spherical Reactors

Description: An IBM-704 computer code for the harmonics method of criticality calculation for two-region spherical reactors is described. In the harmonics method, the criticality condition corresponds to the vanishing of a certain infiniteorder determinant; in practice, this condition is replaced by equating a finite-order approximating determinant to zero. By hand, the calculations can be performed conveniently only for second-order approximating determinants. The approximating determinant with the describ… more
Date: March 15, 1960
Creator: Chalkley, R.; Nestor, C. W. Jr. & Tobias, M. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Interim Report on Safety Procedures for the Task 2 Thermoelectric Generator

Description: Operational hazards associated with the use of a radioisotope-fueled auxiliary power unit for a satellite mission are evaluated. The entire fabrication-to-flight and/or retrieval and disposal sequence is examined and safe handling procedures suggested. The design and operation of the Task 2 thermoelectric generator is discussed. (C.J.G.)
Date: March 15, 1960
Creator: Klein, L. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

[News Script: Carswell bomb wing]

Description: Script from the WBAP-TV/NBC station in Fort Worth, Texas, covering a news story about Carswell Air Force Base activating the 43rd Bomb Wing.
Date: March 15, 1960
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Item Type: Refine your search to only Script
Partner: UNT Libraries Special Collections
open access

[News Script: French cop]

Description: Script from the WBAP-TV/NBC station in Fort Worth, Texas, covering a news story about a French policeman in Fort Worth.
Date: March 15, 1960
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Item Type: Refine your search to only Script
Partner: UNT Libraries Special Collections
open access

[News Script: Lost money]

Description: Script from the WBAP-TV/NBC station in Fort Worth, Texas, covering a news story about W.M. Biggs, who was struck by a hit and run driver as he was walking to the courthouse. Fortunately, Biggs is in good condition and he was able to get his money back that the wind took.
Date: March 15, 1960
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Item Type: Refine your search to only Script
Partner: UNT Libraries Special Collections
open access

[News Script: Loud ties]

Description: Script from the WBAP-TV/NBC station in Fort Worth, Texas, covering a news story about the 8th annual Loud Tie contest of the Downtown Civitan Club in Fort Worth.
Date: March 15, 1960
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Item Type: Refine your search to only Script
Partner: UNT Libraries Special Collections
open access

PATHFINDER ATOMIC POWER PLANT TECHNICAL PROGRESS REPORT FOR OCTOBER 1959- DECEMBER 1959

Description: >Technical progress on the research and development program being performed in connection with the design of the Sioux Falls Power Reactor is reported. Areas covered in detail include fuel element research and development, reactor mechanical studies, nuclear analysis, chemistry, instrumentation and control, plant safety analysis, feasibility studies, and steam plant and reactor auxiliary systems design. (For preceding period see ACNP-5924.) (W.D.M.)
Date: March 15, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Problems of a Small Leak Between the Flow Monitor and Heated Section of a PRTR Process Tube

Description: The result of a leak in a PRTR process tube between the flow monitor and the heated section would be to increase the flow through the monitor, but to decrease the flow through the heated section. The concern for the case of small leaks is whether the increase in flow through the flow monitor is sufficient to cause a high flow tip and a reactor scram for the condition where the flow through the heated section is reduced to the point to cause excessive fuel element temperatures.
Date: March 15, 1960
Creator: Hesson, G. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PURIFICATION OF Pm$sup 147$ FROM FISSION-PRODUCED RARE EARTHS

Description: Promethium is purified from inactive and radioactive long-lived fission- produced rare earths by the use of Dowex 50 or Nalcite HCR cation exchangers and organic eluants. Americium and promethium, having hydrated ionic radii of the same size, are contained in the same fraction of the eluate. Promethium is purified from americium by adsorbing both elements on Dowex 1 (thiocyanate form) and eluting promethium from the resin with ammonium thiocyanate solution. Equllibrium studies were made in orde… more
Date: March 15, 1960
Creator: Pressly, R.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SELECTION OF THE PIQUA OMR FUEL ELEMENT

Description: Two types of aluminum-clad uranium alloy fuel elements, a square (parallel flat plate) and a circular (concentric cylindrical shell) were investigated to determine their relative suitability for use in the Piqua Reactor. Nuclear, thermal, and mechanical data are given, and considerations leading to selection of the circular element are presented. Design dimensions are listed and reactor thermal design and operating conditions are given for the proposed element. (auth)
Date: March 15, 1960
Creator: Baumeister, E.B. & Wilde, J.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

STUDY OF FUEL TEMPERATURE AND FLOW EFFECTS OF PLUGGING IN SRE FUEL CHANNELS

Description: The fuel surface temperatures and flow rate effects which might be produced by plugs in SRE fuel channels were investigated. It was found that plugs which locally insulate more than 20 to 30% of the surface of a fuel rod are dangerous. Heat transfer through the mcderator would not significantly affect the sensitivity of the outlet thermocouple to change in mass flow through a fuel channel, provided the reactor power is above 2 Mw and the channel is not completely plugged. If a 5% or greater inc… more
Date: March 15, 1960
Creator: Noyes, R.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Thermal Cycling Tests of Porous Uranium

Description: Abstract: It has been proposed that a fuel element containing porous uranium be used for moderately high temperature applications. In an effort to determine the structural integrity of this type of fuel body, thermal cycling tests have been conducted on porous uranium.
Date: March 15, 1960
Creator: Wilkinson, L. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Unique Fabrication Processes Applied to Fuel Cladding Materials

Description: The fabrication processes applied to nuclear fuels are subject to severe limitations because of the conditions imposed by the reactor environment. The combined problems of neutrons fluxes, high heat fluxes, corrosion by the coolant , and embrittlement by hydriding or similar reactions may be minimized through establishing rigorous materials and fabrication specifications for fuel and cladding.
Date: March 15, 1960
Creator: Bush, S. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

VARI Solution of Simultaneous, First-Order, Ordinary, Differential Equations

Description: VARI solves on the IBM-650 a system of simultaneous, first-order, ordinary, differential equations. The program was written so that a large number of calculations could be done in a reasonable length of time. The program permits the consideration of the production of the isotope by absorption and/or decay of one or more of any of the other isotopes in the chain.
Date: March 15, 1960
Creator: Kerr, B. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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