25 Matching Results

This system will be undergoing maintenance April 18th between 9:00AM and 12:00PM CDT.

Search Results

Results: 1 - 24 next
open access

B-Plant fission product flowsheets. Part 1

Description: B-Plant is currently being evaluated for use as an integrated fission product plant operating in conjunction with the Purex Plant and a waste calcination system. If the forecasted demands for fission products should increase to rates exceeding present capabilities and if private enterprise continues to remain outside the recovery field, present budget plans are to develop the use of B-Plant in three phases. In Phase 1, the B-Plant canyon would be activated and provisions made for preparing and … more
Date: January 12, 1961
Creator: Beard, S. J. & Judson, B. F.
Partner: UNT Libraries Government Documents Department
open access

Comparative nuclear effects of biomedical interest. Civil effects study

Description: Selected physical and biological data bearing upon the environmental variations created by nuclear explosions are presented in simplified form. Emphasis is placed upon the ``early`` consequences of exposure to blast, thermal radiation, and ionizing radiation to elucidate the comparative ranges of the major effects as they vary with explosive yield and as they contribute to the total hazard to man. A section containing brief definitions of the terminology employed is followed by a section that u… more
Date: January 12, 1961
Creator: White, C.S.; Bowen, I.G.; Richmond, D.R. & Corsbie, R.L.
Partner: UNT Libraries Government Documents Department
open access

Governor Performance Tests. Core I, Seed 2. Test Results. Section 4

Description: An investigation was conducted to determine the load at which each of the governor valves open when the primary average temperature is at 500 deg F. Data compilations for the test are presented along with comparisons with past performances. (J.R.D.)
Date: January 12, 1961
Partner: UNT Libraries Government Documents Department
open access

Maritime Gas-Cooled Reactor Program. Reactor Materials Compatibility With Impurities in Helium

Description: Results are presented of an investigation to determine the maximum permissible partial pressure of carbon dioxide that could be tolerated in the Maritime Gas Cooled Reactor system without oxidizing and embrittling niobium and its alloys, and to screen the heat-resistant nickel- and iron-base alloys for resistance to oxidation and carburization by hydrogen, carbon dioxide, and carbon monoxide. The effect of hydrogen additions on carburization of heatresisting alloys and on the decomposition of c… more
Date: January 12, 1961
Creator: Bokros, J. C. & Shoemaker, H. E.
Partner: UNT Libraries Government Documents Department
open access

STRUCTURAL EVALUATION OF HNPF U-MO FUEL ELEMENTS

Description: A structural evaluation is presentsd of the Hallam Power Reactor fuel elements. The fuel rcd spacer examined is an interim design, but the final spacer is considered to be adequately represented by the analysis of the interim design. Loading of the spacer is considered at temperatures up to 600 deg F. The maximum stress in the hanger rod is found to be 4700 psi. Creep in the fuel rod cladding from internal pressure is predicted to be 5.2% after 48 months of operation, based on a predicted volum… more
Date: April 12, 1961
Creator: Waters, F.J.
Partner: UNT Libraries Government Documents Department
open access

Measurement of the Polarization of Photoneutrons From Deuterium

Description: The polarization of the neutrons produced by photodisintegration of deuterium by 2.75-Mev gamma rays was measured and the results compared to theoretical predictions. The photoneutrons were tsken at five gamma-ray-neutron angles between 45 and 135 deg in the laboratory and scattered from magnesium which has a broad resonance at these neutron energies. Tne polarization was determined from the asymmetry in the left-right scattering from magnesium. The neutrons are found to be negatively polarized… more
Date: May 12, 1961
Creator: Martin, F. V. & John, W., Jr.
Partner: UNT Libraries Government Documents Department
open access

Pneumatic Atomizing Nozzles in Fluidized Bed Calcining. I. Calibration Tests

Description: The results of test stand studies of a pneumatic atomizing nozzle to be used in the Demonstrational Waste Calcining Facility at the Idaho Chemical Processing Plant are presented. Atomization and performance characteristics are described. The liquid feed control system for the Demonstrational Waste Calciner is compared with results of bench scale tests, and recommendations are made for improving the system. (auth)
Date: May 12, 1961
Creator: Legler, B M & Stevens, J I
Partner: UNT Libraries Government Documents Department
open access

KER-3 operating report test K-3-13, PT-1P-363-A. Irradiation of ZR-2 jacketed enriched single tube fuel elements in the KER Loops

Description: The objective of the test was to evaluate the behavior during irradiation of nominally 1.739 inch OD, 1.074 inch ID, Zircaloy-2 jacketed single tube fuel elements with brazed end closures at operating conditions somewhat more severe than those expected for N Reactor fuel element outer tubes. The test elements were fabricated with the Be-Zr alloy brazed end closure planned for use on N Reactor fuel elements. Iron supports were used to minimize process tube scratching during charge-discharge.
Date: June 12, 1961
Partner: UNT Libraries Government Documents Department
open access

SNAP 2 PRIMARY SYSTEM TEST-OBJECTIVES, SYSTEM DESCRIPTION, AND PROCEDURES

Description: The SNAP-2 Primary System Test loop fabrication was completed with associated flight prototype components including reactor core and boiler mockups for volume and DELTA P simulation, CRU-IIII NaK pump, compact heater, and expansion compensator. A mobile loading system was designed and fabricated with the capability of cleaning the NaK prior to final loop sealing. Loop descriptions, test objectives, and operating procedures are presented. (auth)
Date: June 12, 1961
Creator: Kikin, G.M.
Partner: UNT Libraries Government Documents Department
open access

Residual Radiation of the LRL 184-Inch Cyclotron

Description: Residual radioactivity at the Lawrence Radiation Laboratory 184-Inch Cyclotron was measured during November 1960. The study was conducted along three principal lines: (1) general survey of radiation levels in the cyclotron vault, (2) activation of foils placed near the cyclotron, and (3) gamma-ray spectra of the cyclotron gap region, including dee structure. Initial radiation levels were less than 8 r/hr which dropped to abcut 10 mr/hr after 48 hr. The observed activities induced in copper foil… more
Date: July 12, 1961
Creator: Boom, R. W.; Toth, K. S. & Zucker, A.
Partner: UNT Libraries Government Documents Department
open access

System of Automatic Processing and Indexing of Reports

Description: The rapidly increasing volume ot new data in scientific and technical fields demands faster and better ways to communicate the new information to those concerned. A working system. System of Automatic Processing and Indexing of Reports (SAPIR), for doing this is described. SAPIR makes use of the Keyword-in- Context Index principle, by which certain keywords, together with surrounding words that act as modifiers, are selected from the titles of the technical publications. These keywords with the… more
Date: July 12, 1961
Creator: Turner, L. D. & Kennedy, J. H.
Partner: UNT Libraries Government Documents Department
open access

Comparison of Radiation-Induced Graft Copolymerization Untilizing Electron Accelerators and Isotope Sources as Radiation Initiators

Description: "A comparison of grafting to two thicknesses of polypropylene film is made using isotope and electron accelerator initiation. The results indicate that the grafting of methacrylic acid: styrene to polypropylene is mainly a surface reaction."
Date: September 12, 1961
Creator: Odian, George; Oliver, William F. & Pierre, Karl
Partner: UNT Libraries Government Documents Department
open access

Electromagnetic Properties Of A Charged Vector Meson

Description: A systematic study is made of the electromagnetic properties of charged vector mesons. The various formalisms used to describe charged particles of spin 1 are compared, and a new first-order formulation of the Stuckelberg theory is developed.
Date: October 12, 1961
Creator: Young, James A. & Bludmen, Sidney A.
Partner: UNT Libraries Government Documents Department
open access

ANTIPROTON-NUCLEON CROSS SECTIONS FROM 0.5 TO 1.0 Bev

Description: Antiproton-production and nucleon-interaction cross sections were investigated for antiprotons in the energy range 0.5 to 1.0 Bev. The antiprotons were distinguished from other particles produced at the Bevatron by a system of scintillation- and velocity-selecting Cherenkov counters. The excitation function and momentum distribution were recorded for antiproton production in carbon and compared with statistical model expectations. The antiprotons were directed by a system of bending and focusin… more
Date: December 12, 1961
Creator: Elioff, T.; Agnew, L.; Chamberlain, O.; Steiner, H.M.; Wiegand, C. & Ypsilantis, T.
Partner: UNT Libraries Government Documents Department
open access

Antiproton-Nucleon Cross Sections From 0.5 To 1.0 Bev

Description: Antiproton-production and nucleon-interaction cross sections were investigated for antiprotons in the energy range 0.5 to 1.0 Bev. The antiprotons were distinguished from other particles produced at the Bevatron by a system of scintillation- and velocity-selecting Cerenkov counters. The excitation function and momentum distribution were recorded for antiproton production in carbon and compared with statistical model expectations.
Date: December 12, 1961
Creator: Elioff, Tommy; Agnaw, Louis; Chamberlain, O. (Owen); Steiner, Herbert M.; Wiegand, Clyde (Clyde Edward), 1915-1996 & Ypsilantis, Tom
Partner: UNT Libraries Government Documents Department
open access

COOLING OF THE HFIR BERYLLIUM REFLECTOR FOLLOWING A REACTOR SCRAM OR AN ELECTRICAL POWER OUTAGE

Description: Thermal stresses in the HFIR beryllium reflector were computed for the unlikely case where the reactor is scrammed with a simultaneous loss of coolant flow and for the case following an electrical power outage where the reactor power level and the coolant flow rate are reduced simultaneously. For the case where the reactor is scrammed with a sudden loss of the coolant flow, the resulting maximum tensile thermal stress following the scram is 22,500 psi. In case of an electrical power outage, the… more
Date: December 12, 1961
Creator: McLain, H. A.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen