25 Matching Results

Search Results

Results: 1 - 24 next
open access

NEUTRON CROSS SECTIONS FOR ALUMINUM

Description: No Description Available.
Date: November 13, 1964
Creator: Joanou, G. D. & Stevens, C. A.
Partner: UNT Libraries Government Documents Department
open access

Analysis of the Combustion of Graphite-Uranium Fuels in a Fixed Bed or Moving Bed

Description: The first step in a proposed processing method for recovery of uranium from graphite-uranium fuels consists of oxidation of the fuel by oxygen to volatilize the carbon. Residue ash from the combustion step can be treated in a variety of ways to recover and purify the uranium. The combustion step may be caried out by contacting the solid fuel in a fixed or moving bed with a stream of oxygen-bearing gas in a tubular or annular reactor. Oxidizing gas may be introduced to the reactor at several poi… more
Date: August 13, 1964
Creator: Scott, Charles D.
Partner: UNT Libraries Government Documents Department
open access

Graduate Programs for the Health Physicist in the United States

Description: The first man-made nuclear reactor -- or "pile" as it was then called -- was rather hurriedly improvised and operated in a crowded space under the athletic bleachers of Stagg Field at the University of Chicago on December 2, 1942. Just prior to this time, there began the assembly of a group of physicists with an unusual assignment. They were determined that radiation hazards of unprecedented proportions must be coped with successfully in the conduct of reactor programs as planned. Since these p… more
Date: August 13, 1964
Creator: Morgan, K. Z. (Karl Ziegler), 1908-
Partner: UNT Libraries Government Documents Department
open access

An evaluation of the experimental determination of the effects of burnout and corrosion on spline worth

Description: Efforts have been made to experimentally evaluate and to calculate the effect of reactor environment on splines. This report follows some of these efforts and relates them to operational experience. The use of splines in the Hanford Reactors has improved the efficiency and ease of operating the reactors. With the widespread use of splines, it is important to know the effect of reactor exposure to safely and efficiently use the splines in reactor operation.
Date: July 13, 1964
Creator: Blyckert, W. A.
Partner: UNT Libraries Government Documents Department
open access

Hazards review: N-Reactor 1.25% co-producer fuel element test

Description: The N-Reactor Hazard Summary Report examines the hazard from operating the N-Reactor with a uniform fuel loading enriched to 0.947% U{sup 235}. Incentives have been developed for reactor testing of a block of 49 tubes loaded with co-producer elements, i.e. elements capable of producing both weapons grade plutonium and tritium. The element utilizes an outer fuel tube enriched to 1.25% U{sup 235} with an inner target lithium-aluminum rod. Criteria have been developed to guide the evaluation of sa… more
Date: July 13, 1964
Creator: Miller, N. R. & Nechodom, W. S.
Partner: UNT Libraries Government Documents Department
open access

Irradiation Processing Department Monthly Report: February 1964

Description: This report details activities of the Irradiation Processing Department during the month of February 1964.
Date: March 13, 1964
Creator: Hanford Atomic Products Operation. Irradiation Processing Department.
Partner: UNT Libraries Government Documents Department
open access

February 1963 Production Studies Addendum

Description: This report provides an addendum to the February 1963 production studies and details Neptunium 237 production yields.
Date: February 13, 1964
Creator: Lang, L. W. & McCurry, J. W.
Partner: UNT Libraries Government Documents Department
open access

Progress report on NASA cermet studies identification SNC-12, January 1964

Description: This report details progress in an intensive investigation which was launched to determine the basic mechanisms leading to gross loss of UO{sub 2} fuel upon thermal cycling of UO{sub 2}-W cermets and to suggest means of overcoming this serious operational problem. (This problem was recently uncovered at both Lewis Research Center and at Hanford). More than 40 separate experiments were conducted in four high temperature furnaces, at temperatures to 2600 C, pressures from 10{sup {minus}5} mm vacu… more
Date: February 13, 1964
Creator: Cadwell, J. J.
Partner: UNT Libraries Government Documents Department
open access

Biological Effects of Thermal Neutrons and the B10 (n,c) Li7 Reaction

Description: Boron-10 has a high thermal neutron capture cross section (3880 barns). Following neutron capture, the subsequent nuclear disintegration produces an alpha particle and a lithium-7 nucleus with the release of an average of 2.34 MeV for the particle irradiation, and in 93% of the reactions there is also the emission of an 0.48 MeV gamma ray: [equation not transcribed]. The kinetic energy is divided between the lithium-7 nucleus and the alpha particle giving the equal and opposite momentums with a… more
Date: January 13, 1964
Creator: Archambeau, J. O.; Alcober, V; Calvo, W. & Brenneis, H.
Partner: UNT Libraries Government Documents Department
open access

Core Band Tensile Test

Description: This test was conducted to determine the adequancy of the Core Band to withstand the forces imposed upon it during Reactor Operation.
Date: January 13, 1964
Creator: Allison, H. & Zibritosky, G.
Partner: UNT Libraries Government Documents Department
open access

Dose-survival Curves for HeLa Cell Cultures Using Thermal Neutrons and the B10 (n,α)Li7 Reaction

Description: The biological evaluation of the thermal neutron capture reaction of boron-10, B10 (n,α)Li7 + 2.786 MeV, has previously been studied, using different particles from the boron-10 thermal neutron capture reaction compared with 250 kvp x-rays has been reported as 1.05 for spleen-thymic weight reduction (1), as 1.5 to 2.0 for skin lesions in pigs (2), and 1.87 for skin lesions of the rabbit's ear (3). The significance of such a calculation is felt to be unreliable for the boron-10 reaction in anima… more
Date: January 13, 1964
Creator: Archambeau, J. O.; Drew, R. M. & Robertson, J. S.
Partner: UNT Libraries Government Documents Department
open access

A Single Stage Axial Compressor Blade Test Facility

Description: Abstract: This report gives a general description of the single stage axial compressor blade test facility located at the Oak Ridge Gaseous Diffusion Plant, Oak Ridge, Tennessee.
Date: January 13, 1964
Creator: Fee, G. G.
Partner: UNT Libraries Government Documents Department
open access

Two Lectures on the Magnetic Scattering of Neutrons

Description: In these lectures we will discuss some examples of information about magnetic properties of solids which can be obtained by neutron scattering. We consider a scattering process in which a neutron with wave vector k and spin σ is incident upon a solid in state q>. (Here q stands for all of the quantum numbers which describe the state of the solid, such as spin and orbital electronic states, phonon numbers, etc.) After interacting with the solid, the neutron goes off with wave-vector k' and spin … more
Date: January 13, 1964
Creator: Blume, M.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen