53 Matching Results

Search Results

Results: 1 - 24 next
open access

The Laboratory Director's Review Committees at ORNL

Description: The basic reasons for establishing the Laboratory Director's Review Committees are discussed together with a short description of the field of activity of each committee.
Date: May 10, 1961
Creator: Kertész, François, 1911-
Partner: UNT Libraries Government Documents Department
open access

Examinations of Pump Impellers From Sodium and Fused Salt Pump Endurance Tests

Description: Examinations of three Inconel pump impellers were made to establish the extent of cavitation damage and degree of carburization sustained during pump endurance tests. The pumps, two of which circulated fluoride salt and one sodium, had operated for the bulk of the test programs in the temperature range 1000-1250 deg F. Cavitation damage was manifested in each of the impellers by the formation of deep pits (in excess of 1/4-inch), the location of damaged areas varying with impeller geometry.
Date: April 10, 1961
Creator: DeVan, J.H.
Partner: UNT Libraries Government Documents Department
open access

Neutron Multiplication Experiments with Enriched Uranium Metal in Slab Geometry

Description: The determination of critical dimensions of both individual units and arrays of units of fissionable material, in simple shapes and with minimal interference from supports, etc., has been a continuing program at Oak Ridge National Laboratory. In the experiments presently reported, uranium metal slabs were assembled, and although not made critical, produced sufficient source neutron multiplication to allow quite precise estimation of the critical thickness.
Date: April 10, 1961
Creator: Mihalczo, J.T. & Lynn, J.J.
Partner: UNT Libraries Government Documents Department
open access

Plutonium Release Incident at Oak Ridge National Laboratory

Description: A nonnuclear explosion involving an evaporator occurred in a shielded cell in the Radiochemical Processing Pilot plant at Oak Ridge National Laboratory. Plutonium released from the processing cell contaminated areas in the pilot plant building and nearby streets and building surfaces. The explosion is considered the result of rapid reaction of nitrated organic compounds formed by the inadvertent nitration of about 14 liters of a proprietary decontaminating reagent.
Date: January 10, 1961
Creator: King, L. J. & Bresee. J. C.
Partner: UNT Libraries Government Documents Department
open access

VARI-II

Description: Writing the VARI-II Program was motivated by the need for a method of analyzing the results for the Absorber Burn-Up Experiment in progress at the Vallecitos Atomic Laboratory.
Date: March 10, 1961
Creator: Russell, J. L. (John L.), Jr.
Partner: UNT Libraries Government Documents Department
open access

The Recovery of Fission Product Rare Earth Sulfates from Purex LWW

Description: A research and development program aimed at devising processes for the economical recovery of the potentially valuable long-lived fission products from Purex waste has been under wat at Hanford for several years. When this work has begun, the concentrated waste was primarily a nitric acid solution (6 to 10 M HNO3) containing the fission products and relatively small concentrations of iron, sulfate, and other corrosion products. Flowsheets based on classical separation schemes and rather similar… more
Date: May 10, 1961
Creator: Wheelwright, E. J. & Swift, W. H.
Partner: UNT Libraries Government Documents Department
open access

Experiments On Alfven-Wave Propagation

Description: This paper reports an extension of previous experimental work with Alfven waves. We consider hydromagnetic waves propagating in a cylindrical plasma in a uniform axial magnetic field. The copper tube is filled with highly ionized plasma by an electrically driven switch-on ionizing wave. After the tube is filled with plasma, a hydromagnetic wave is induced by a radial current flow from the small molybdenum electrode to the copper tube. The force produced by this radial current together with the … more
Date: May 10, 1961
Creator: Wilcox, John M.; DeSilva, Alan W. & Cooper, William S., III
Partner: UNT Libraries Government Documents Department
open access

Diffusion of Krypton Through Uranium Carbide - Final Report

Description: This program was established to develop new information concerning the mechanism of diffusion of fission gases (krypton and xenon) through UO2 and UC. The work was to concentrated on measurements of diffusion rates in unirradiated materials in the temperature range of 1000°C to above 2000°C, these determinations being important to the projected use of refractory fuel materials in high-temperature, high-burnup reactors.
Date: January 10, 1961
Creator: Weinstock, J. J.; Pinkerton, A. P. & Ziegel, K. D.
Partner: UNT Libraries Government Documents Department
open access

Supplement A to PT-IP-263-A-FP evaluation of chemically nickel plated fuel elements

Description: Irradiation of the initial test in this program involving ten tubes of alternately charged nickel-plated C-64 alloy clad test elements and X-8001 alloy control elements has been successfully completed. The test indicated that the nickel-plate spalling problem has been resolved as no significant spalling or flaking was observed during the post-irradiation examination. The second test in this program will be to verify the performance of nickel-plate with a pilot loading (up to 100 charges) of fue… more
Date: July 10, 1961
Creator: Clinton, M. A.
Partner: UNT Libraries Government Documents Department
open access

Neptunium-237 content of E-metal

Description: An analytical program was carried out to obtain an accurate single point measurement of neptunium-37 content versus exposure for E-metal. Two large volume dissolver solution samples representing E-metal from the KW, KE, C, and DR reactors were obtained from the Redox Plant for the basis of analysis. The neptunium-237/U ratio was determined by direct analysis, and the exposure was estimated from the measured Pu/U ratio and the uranium-235 burn-out.
Date: October 10, 1961
Creator: Schneider, R. A.
Partner: UNT Libraries Government Documents Department
open access

Summary of the Operational Status of Reactor Control Instrumentation, Report No. 2

Description: The purpose of this review is to report the operability status of the reactor control instrumentation. The status of the instruments was determined twice during the first six months of this year, April 1 and June 1. The information contained in this report is not intended to be a complete description of the control instruments, but only as they apply to reactor control. The assigned Pile Physicist at each reactor reported the status of instrumentation at his reactor. Chart I summarizes the oper… more
Date: July 10, 1961
Creator: Stewart, S. L.
Partner: UNT Libraries Government Documents Department
open access

D-Reactor Graphite Burnout Interim Report: IP-25A(PT-105-532-E)

Description: The oxidation rate of the moderator in D-Reactor has been monitored from samples placed along the length of process tube channel 3478. During the interval from August 8, 1960, to August 10, 1961 were very high, up to 40%/KOD (1000 operating days). From the shape of the front-to-rear burnout profile, the oxidant appears to be oxygen and/or water.
Date: November 10, 1961
Creator: Ryan, B. A.
Partner: UNT Libraries Government Documents Department
open access

Supplement A to PT-IP-183-A-98-FP: Evaluation of projection fuel elements for use in K process tubes

Description: The objective of this supplement is to authorize charging of ten tubes of ``bumper`` fuel elements and controls into each K Reactor. The test is designed to reevaluate the reduction in hot-spot incidence associated with fuel alignment within K Reactor ribbed process tubes for both natural and enriched uranium I&E fuel elements of the KIV geometry.
Date: April 10, 1961
Creator: Clinton, M. A.
Partner: UNT Libraries Government Documents Department
open access

Results of Laboratory Heat Transfer Experiments for C-Reactor Overbore Fuel Channels

Description: The purpose of this report is to present experimental data concerning the heat transfer and fluid flow conditions within a C-overbore geometry process channel for the cases of steady state operation, flow plugging incidents, and inlet piping failure incidents.
Date: November 10, 1961
Creator: Waters, E. D. & Kreiter, M. R.
Partner: UNT Libraries Government Documents Department
open access

Final report on production test IP-289-I, Supplement 1, H reactor export flow test

Description: The raw water export system forms the last ditch water supply system to the ``O`` and ``C`` type reactors; in the event of electrical and steam power failure, the export system is designed to supply enough raw water coolant. After the original export orifice was modified twice, the export system was retested.
Date: July 10, 1961
Creator: Cremer, B. R.
Partner: UNT Libraries Government Documents Department
open access

E-N and blanket conversions from analysis of tubes irradiated at H

Description: A block-loading of striped columns and tubes simulating a blanket loading were analyzed for product (Pu, tritium, E-metal) after irradiation in IP-255-A-9-FP. Results are rationalized to full-pile values; pile conversion ratios and pile gains are given.
Date: February 10, 1961
Creator: Lang, L. W. & Nechodom, W. S.
Partner: UNT Libraries Government Documents Department
open access

PT-IP-344-A-FP, Evaluation of Al-Si bond characteristics

Description: Tests in which aluminum-jacketed, Al-Si bonded uranium fuel elements were baked at various temperatures have shown there is a time-temperature relationship for Al-Si layer decomposition. For heat transfer and secondary coolant barrier considerations, the extent of bonding layer deterioration during fuel element irradiation is important. Currently, Al-Si bonded fuel elements show evidence of spire bond separation, and to a lesser degree, can-bond separation following irradiation. Such evidence h… more
Date: November 10, 1961
Creator: Clinton, M. A.
Partner: UNT Libraries Government Documents Department
open access

Proposal for charging heat treatment test elements GEH-10-44 & 45

Description: The objective of this irradiation is to determine the differences in irradiation behavior; typified by dimensional changes, surface roughness, and overall distortion; resulting from elements of similar fabrication history but different beta heat treating schedule. The fuel will be the inner tube only of an NPR fuel assembly. Both elements were heated in chloride salt at 730C; one was rapidly quenched and the other air cooled to obtain a wide variation in grain size and structure and residual st… more
Date: January 10, 1961
Creator: Kemper, R. S. & Young, F. E.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen