192 Matching Results

Search Results

Results: 1 - 24 next
open access

ABWR: PL-2 Design Report

Description: From preface: This report satisfies the quarterly progress report requirements for PL-1 and PL-2 plant design work for the period ending September 30, 1960 At present time a SL-1 Core 2 is under construction. This is a replacement core for SL-1 (ALPR) and will be identical to a PL-2 core; a PL condenser is under test at the SL-1 facility; final construction plans for PL components and modules which are not site sensitive will be completed in March 1961.
Date: October 15, 1960
Creator: Combustion Engineering, inc. Nuclear Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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 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

An Algorithm for Construction Feasible Schedules and Computing Their Schedule Times

Description: "An algorithm for the generation of feasible schedules and the computation of the completion times of the job operations of feasible schedule is presented. Using this algorithm, the distribution of schedule times over the set of feasible schedule—or a subset of feasible schedules—was determined for technological orderings that could occur in a general machine shop. These distributions are found to be approximately normal. Biasing techniques corresponding to “first come first serve,” random choi… more
Date: November 15, 1960
Creator: Heller, Jack & Logemann, George
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

An appraisal of the Hanford high-level waste program

Description: As set forth in the CPD Waste Management Program (HW-63958), new and improved methods of waste processing are planned to be initiated at Hanford. A major part of this program is concerned with the high-level wastes from the Purex Plant, with major objectives being the control of long-term hazards, the insurance of production continuity, and the attainment of positive waste accountability at reasonable over-all costs. Specific plans for the disposal of Purex wastes are based on the use of high t… more
Date: September 15, 1960
Creator: Campbell, B. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Bounce III

Description: BOUNCE III is a program which was written for the IBM-704 as part of a study of the parameters of the neutron distribution in a large thermal column. The program calculates the eigenvalues and corresponding eigenvectors of the matrix resulting from a diffusion-theory, multigroup description of the thermal neutron spectrum.
Date: December 15, 1960
Creator: Kerr, B. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Cap-spire pulsing

Description: The cap-spire pulsing technique of preheating the cap-spire portion of the fuel assembly does significantly improve the brazing of the cap-spire assembly. The air pocket at the spire wafer junction is fully removed. The cap side wafer is essentially 100% wetted with brazing alloy. Destructive tests show that a 4 to 1 improvement in most quality measurements is achieved over present cap preheating techniques, without using additional cleaning step of spire etching. The pulsing is accomplished by… more
Date: June 15, 1960
Creator: Burgess, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design Study: Sodium Modular Reactor

Description: This study was undertaken for the USAEC under Contract AT(04-3)-189, Project Agreement No. 6, to investigate desirable features of a sodium cooled, graphite moderated uranium fueled power reactor using the modular concept, and, based on this investigation, evaluate the economic potential of this reactor type.
Date: January 15, 1960
Creator: General Electric Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Device for Continuous Detection of Hydrogen in Sodium

Description: Abstract: A device to detect the presence of hydrogen in sodium has been developed. Such a device, installed in a sodium heated steam generator, would signal the presence of water in the sodium resulting from a leak in the sodium-water barrier.
Date: December 15, 1960
Creator: Strahl, H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Equilibrium Configuration of a Plasma in the Guiding Center Limit

Description: "We compute the equilibrium configuration of a collision-free plasma contained in an axially symmetric magnetic field. The plasma is characterized by a non-scalar pressure tensor which is obtained from a microscopic distribution function in a form suggested b the guiding center approximation. The solution is calculated in the limit where the ratio of the width to the length of the plasma region and the ratio of the gas to the magnetic pressure are both small. Boundary values at the midplane … more
Date: September 15, 1960
Creator: Oppenheim, Alan
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Experimental and Research Work in Neutron Dosimetry. Final Summary Report for the Period May 15, 1959-June 15, 1960

Description: A practical, prototype silicon p-n junction fast-neutron dosimeter, sensitive in the same range as human tissue, was developed, together with sn associated read-out circuit to facilitate the accurate measurement of accumulated dose. From both theoretical and experimental considerations, it was demonstrated that the dosimeter is essentially insensitive to the gamma and thermal components of a uranium fission spectrum. It was shown that accumulated damage effects appear to be environmentally stab… more
Date: June 15, 1960
Creator: Gorton, H. C.; Mengali, O. J.; Zacaroli, A. R.; Crooks, R. K.; Swartz, J. M. & Peet, C. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A FAILURE ANALYSIS FOR THE LOW-TEMPERATURE PERFORMANCE OF DISPERSION FUEL ELEMENTS

Description: An analytical approach is proposed which allows the bunnup (by fission) of uranium required to cause failure in a uranium dioxide-stainicss steel dispersion fuel element to be calculated. The analysis is developed by assuming the matrix of the fuel eicment to be made up of a uniform, close-packed array of spherical UO/sub 2/ particles, each surrounded by and associated with a hollow stainless steel sphere. Equations are then written for the amount of fission gas released into the stainless stee… more
Date: June 15, 1960
Creator: Weir, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

FUEL BURNUP STUDIES FOR A 225 Mwe ADVANCED SODIUM GRAPHITE REACTOR

Description: Reactivity and fuel burnup studies were performed for a 255 Mw(e) sodium- graphite reactor of the advanced calandria core type. This reactor is briefly described. Initial criticality calculations and flux distributions were obtained, using two-group theory for enrichments between 2.0 at.% U/sup 325/ and 4.0 at.% U235. A four-group burnup study was performed for enrichments between 2.5 at.% Uisup nd 3.25 at.% U/sup 235/. Core lifetime, changes in isotopic fuel composition, variations in radial p… more
Date: June 15, 1960
Creator: Aronson, A. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fuel element study for Reactor Overbore Program

Description: Recent studies have confirmed that large incentives exist for overboring the reactor process channels approximately 500 mils in the C and five old reactors under the proposed Plant Improvement Program. Conservative estimates of the incentives for overboring indicate a payout period of about two years for the proposed work, an increase in plutonium production of 15--18%, derived from increased conversion ratio and a reduction in plant unit cost. Since sufficient progress has been made in the are… more
Date: December 15, 1960
Creator: Stringer, J. T. & Blanton, W. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Gamma activity of irradiated zircalloy samples

Description: Three small samples of zircalloy-2, obtained from a KER tube, were irradiated in the Quickie Facility in F Reactor for one, four, and nine months, respectively. Each sample weighed approximately two grams. One day after discharge from the reactor, the specific activity of each of the samples was essentially the same (about 150 mr/hr/gram at one foot in air). Attenuation measurements taken one day after discharge using lead plates yielded a ten-fold reduction in gamma intensity for each 0.95 inc… more
Date: June 15, 1960
Creator: Bunch, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Gas Diffusion Into a Bubble of Fixed Radius

Description: The problem of radiolytic gas diffusion into a bubble of fixed radius is solved. A constant source of radiolytic gas is assumed. The concentration of gas at the bubble surface is related to the pressure within the bubble by Henry's constant. (W. L.H.)
Date: July 15, 1960
Creator: Warner, C., III
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen