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ABRAC--AN IBM-704 THREE DIMENSIONAL NUCLEAR-THERMAL DEPLETION PROGRAM WITH DISTRIBUTED VOID EFFECTS

Description: ABRAC is a three dimensional nuclear thermal depletion program to study the effects of water moderator density changes, resulting from flow variations and boiling, on neutron flux distribution and depletion. The program requires an IBM-704 with a memory of 32.768 words and ten tape units. (auth)
Date: March 1, 1960
Creator: Jacobi, W. M.; Lawton, T. J.; Meanor, S. H. & Parrette, J. R.
Partner: UNT Libraries Government Documents Department

[Actors slide]

Description: Photograph of two actors arguing on a slide, a man on the left and a woman on the right. The man is wearing a robe, the woman is in a dress. Labeling along the bottom of the slide says, "Cat on a Hot Tin Roof, an Avon production - an MGM release."
Date: March 30, 1960
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Partner: UNT Libraries Special Collections
open access

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 mills/kwh. In a similar plant with a net electrical output of 530 Mw, the estimated power generating cost is 5.4 mills/ kwh. Most of the components of the plant are within the capability of current technology. The major exception is the fuel material, uranium carbide. Preliminary results of the development work now in progress indicate that uranium carbide would be an excellent fuel for high-temperature reactors, but temperature and burnup limitation have yet to be firmly established. Additional development work is also required on the steam generators. These are the single-barrier type similar to those which will be used in the Enrico Fernri Fast Breeder Reactor plant but produce steam at higher pressure and temperature. Questions also remain regarding the use of nitrogen as a cover gas over sodium at 1200 deg F and compatibility of the materials used in the primary neutron shield. All of these questions are currently under investigation. (auth)
Date: March 15, 1960
Creator: Churchill, J. R. & Renard, J.
Partner: UNT Libraries Government Documents Department
open access

Alpha correlation

Description: This study was developed to provide a correlation for the evaluation of the pile C{sub RI}/Tube C{sub RI} ratio (alpha value) for each of the Hanford reactors.
Date: March 24, 1960
Creator: Cremer, B. R.
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 counters so that all charged secondaries from the antiproton--proion interactions could be detected. With the information obtained from these counters, the --p-bar--p total, elastic, inelastic, and charge-exchange cross sections and the angular distribution of the elastic scatterings were obtained at each energy. The total cross section was found to be 80, 89, and 100 mb at 2.0 1.25. and 0.98 Bev. respeclively. The inelastic cross section was about twothirds of ihe total cross section at each energy. It was found that each of the partial cross sections was dropping off slowly with energy. The results were fitted by an optic al-model c alculation. (auth)
Date: March 15, 1960
Creator: Coombes, C. A.
Partner: UNT Libraries Government Documents Department
open access

An assessment of the zirconium tube program -- C Reactor pilot demonstration installation

Description: Production Test IP-272-A-FP authorizes the installation of up to 100 smooth bore Zircaloy-2 process tubes in C Reactor to demonstrate the feasibility of self-supported fuel elements for production use. An additional 200 zirconium tubes are expected to be delivered by mid-year and con be used to expand the initial demonstration facility. It is the purpose of this document to assess the status of the pilot demonstration program from the B-C Reactor Operation viewpoint.
Date: March 18, 1960
Creator: Amy, G. O.
Partner: UNT Libraries Government Documents Department
open access

Automatic Recording Unit

Description: From abstract: The PT-750 is designed to be used in conjunction with a production tester which requires automatic recording of test data. This manual provides a source of procedures and reference material necessary in automatic recording and in use of the PT-750.
Date: March 29, 1960
Creator: Ross, Frank A.
Partner: UNT Libraries Government Documents Department

[A band on set with Curly Broyles]

Description: Photograph of Curly Broyles on set with a band. Broyles is wearing a dark colored suit with a bow tie while the band members are wearing lighter jackets with black pants. Broyles is holding a trumpet and the man to his right is playing a clarinet. The other men are playing the trombone, the banjo, the piano, the upright bass, and the drums. The drum set is on a raised platform on the right side of the set. The walls behind the set are striped and in the stripes are geometric shapes. The wall on the left has horizontal stripes while the wall on the right has vertical stripes.
Date: March 28, 1960
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Partner: UNT Libraries Special Collections
open access

THE BMI-16 RECIRCULATING GAS LOOP INSTALLED AT THE ETR

Description: A developmental program was conducted to provide and in-pile loop facility for use in evaluating gas-cooledreactor fuel asubassemblies. The program included the design, construction, and installation of a recirculating gas loop which is located in a 6 by 6-in. facility in the aluminum reflector of the ETR. The loop system was designed to recirculate the primary nitrogen coolant at flow rates up to 0.9 lb per sec and pressures up to 200 psia. It will accept fuel subassmeblies up to 36 in. in length and 2.26 ia. in diameter with specimen power generation up to 150 kw. The maximum coolant temperature at the specimen outlet is set at 1500 deg F. The loop system includes the in-reactor section, the machinery, the control system, and the specimen-handling apparatus. Salient features of the re-ertrant system include an aluminum pressure wall in the in-reactor section, static gas insulation between the reactor coolant and the circulating loop gas, and a controllable rate of heat exchange between the specimen inlet- and specimen outlet-gas channels in sections of concentric countedlow piping. The three blowers in the system feature grease-lubricated bearings and water cooling. The complete system was tested out of pile and is now installed in the ETR. (auth)
Date: March 18, 1960
Creator: Baum, J. V. & Francis, G. A.
Partner: UNT Libraries Government Documents Department

[Boedeker's slide]

Description: Photograph of a slide for Boedeker's store. It says, "H. Boedeker's, 117 Lancaster off Jefferson, Dallas." Dallas is in white writing, the rest is black.
Date: March 22, 1960
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Partner: UNT Libraries Special Collections
open access

Burst testing of irradiated Zircaloy tubing. Revision 1

Description: An extensive knowledge of the effect on the mechanical properties of metals of prolonged exposure to neutron radiation is considered necessary to properly establish design and operating criteria for in-reactor pressure tubes and test loops. An opportunity to obtain a limited amount of this information on Zircaloy-2 presented itself when, after two years of service, the pressure tubes were replaced in the RE reactor recirculating test facility. Three Zircaloy-2 tubes, with a two-inch inside diameter and 48 feet long, had operated intermittently with prototypical fuel elements at water temperatures up to 250 C (480 F) and pressures up to 1350 psi. During this period, the tubes received an estimated integrated neutron exposure of 1.9 {times} 10{sup 22} nvt. After the tubes were removed from the reactor, metallographic examinations, longitudinal-tensile tests, flattening tests, and burst tests were performed. In this report, the techniques for performing the burst tests are described and the results of the burst tests are compared with the results from tensile tests on coupons cut from corresponding locations along the tube.
Date: March 4, 1960
Creator: Kahle, V. E.
Partner: UNT Libraries Government Documents Department

[Cat on a Hot Tin Roof slide]

Description: Photograph of a slide advertising Cat on a Hot Tin Roof. A woman sits on a drawn bed on the left side of the slide. Large writing on the right says, "Cat on a Hot Tin Roof," and the letters are half black and white.
Date: March 30, 1960
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Partner: UNT Libraries Special Collections
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