8 Matching Results

Search Results

Results: 1 - 8
open access

Decomposition of Nitrous Oxide Final Report. Period Covered: February 19, 1959-August 18, 1959

Description: The decomposition of N/sub 2/O in a reactor tube containing various fixed-bed catalysts was investigated at 200 to 700 deg C, space velocities of 250, 1250, and 2500 vol. of gas per vol. of catalyst per hr, and various gas mixture compositions. As catalysts, En at 500 deg C and Pd at 650 deg C both gave satisfactory results. NO/sub 2/ was formed with all these catalysts, the amount increasing as the residual N/sub 2/O decreased. (C.J.G.)
Date: August 31, 1959
Creator: Zufall, J. H. & Miller, H. S.
Partner: UNT Libraries Government Documents Department
open access

CALCULATION OF RADIAL NEUTRON-FLUX DISTRIBUTION IN EGCR LATTICE CELL

Description: The neutron flux distributions in an EGCR cell containing seven and clusters of 2.0 and 2.6a enriched uranium odde were obtained by using a one- velocity, one-dimensional P-3 solution to the neutron transport equation and adjusting fluxes in the fuel cluster in a manner which is consistent with previous comparisons of experiments and calculated distributions. Flux traverses in the outer rod perpendicular to diameter of the cluster are also presented. (auth)
Date: August 31, 1959
Creator: DeBoer, T. K.
Partner: UNT Libraries Government Documents Department
open access

VARIABLE MODERATOR REACTOR DEVELOPMENT PROGRAM. Quarterly Progress Report No. 1

Description: Development of the boiling water UO/sub 2/ fueled Variable Moderator Reactor (VMR) is conducted under contract for the USAEC. The initiation and progress of work under Phase I of the contract, Physics and Kinetic Analysis and Initial Evaluation,'' and the preparation for Phase II, Critical Experiment and Analysis of Results,'' are reported. A hydrodynamic flow sheet representing the sequence of calculations for the BOCH program was prepared. A preliminary block diagram of the kinetics model of … more
Date: August 31, 1959
Partner: UNT Libraries Government Documents Department
open access

Pathfinder Atomic Power Plant Measurements of Nuclear Parameters of Boiler and Superheater Lattices

Description: Experiments are described which were designed to yield information pertinent to the evaluation of the nuclear parameters of various fuel-moderator lattices in the environment of the Sioux Falls Power Reactor (Controlled Recirculation Boiling Reactor) core. The test lattice section was enclosed in an element which replaced one of the fuel elements of the Penn State Reactor. Parameters measured were U/sup 236/ neutron capture cadmium ratio, space-averaged thermal neutron flux ratios, and reactivi… more
Date: August 31, 1959
Creator: Jacobs, A. & Vollmer, R.H.
Partner: UNT Libraries Government Documents Department
open access

Dissolution of aluminium oxide as a regulating factor in aqueous aluminum corrosion

Description: The solubility of aluminum corrosion product in contact with metallic aluminum in deionized water has been determined over the range 80 to 350/sup 0/C. Evidence is presented to show that oxide dissolution results in the formation of a porous oxide on aluminum exposed in refreshed dynamic systems. Dynamic corrosion rate data have been analyzed on the basis of parabolic film growth and a linear oxide degradation process acting simultaneously on the system. The degradation process has been shown t… more
Date: August 31, 1959
Creator: Dillon, R.L.
Partner: UNT Libraries Government Documents Department
open access

Production test authorization IP-217-A-supplement, uranium sample irradiation (HAPO-218)

Description: The object of this production test is to authorize the irradiation of samples of natural uranium for use in the fission product volatilization program. Any empty central zone PCCF and/or process tube at B, D, DR, or H Reactors will meet the requirements of this authorization.
Date: August 31, 1959
Creator: Zima, G. E.
Partner: UNT Libraries Government Documents Department
open access

New Production Reactor Thermal Shielded Studies

Description: The relative neutron capture gamma production in several prospective iron thermal shielding materials for the New Production Reactor was measured to determine the merit of adding boron to the metal. It was found that for the beam geometry the used addition of 1 1/2 percent boron to the iron before casting reduced the soft gamma production by a factor of 6.5 and the hard gamma production by a factor of 10. No attempt was made to measure gamma or neutron transmissions.
Date: August 31, 1959
Creator: Friesenhahn, S. J.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen