Anion Exchange Recovery of Plutonium From the Hanford 234-5 Building Button Line. Task I Oxalate Filtrate (open access)

Anion Exchange Recovery of Plutonium From the Hanford 234-5 Building Button Line. Task I Oxalate Filtrate

Resulte of a laboratory investigation undertaken to adapt the Pu anion exchange process to the direct recovery of the Pu lost to the Task I oxalate filtrate are reported. It was found that the Button Line Task I Filtrate can be recovered by HNO/sub 3/ anion exchange process, thus isolating the Button Line from any solvent extraction process. (J.R.D.)
Date: November 13, 1962
Creator: Wheelwright, E. J.
Object Type: Report
System: The UNT Digital Library
Comparison of Experimental Data With Computer Calculated Values for Single Phase Flow and Transient Heat Transfer to Gaseous Hydrogen (open access)

Comparison of Experimental Data With Computer Calculated Values for Single Phase Flow and Transient Heat Transfer to Gaseous Hydrogen

Comparisons between experimental data obtained from single-phase gaseous hydrogen cool-down with those computed from a computer program have shown excellent agreements.
Date: December 13, 1962
Creator: Chi, J.W.H.
Object Type: Report
System: The UNT Digital Library
CORROSION OF NICKEL-BASE SPECIMENS EXPOSED IN THE VOLATILITY PILOT PLANT MARK III FLUORINATOR (open access)

CORROSION OF NICKEL-BASE SPECIMENS EXPOSED IN THE VOLATILITY PILOT PLANT MARK III FLUORINATOR

The combination of operating temperatures around 550 deg C with LiF present in the salt baths produces about the same bulk metal losses on Ni and Ni- base alloys as was found by operating at 650 deg C without Li in the salt baths. The presence of U accelerates corrosion of Ni and Ni-base alloys during the Volatility Process fluorination cycle. Prior F conditioning of L Ni decreases corrosion of the material during subsequent fluorination. Prior F conditioning of INCO-61 weld metal increases the attack on INCO 61 during subsequent fluorination. Bulk metal losses on L Ni and the Ni-binary alloys containing Al, Co, Fe, or Mn are about the same during fluorination at 550 deg C with Li present in the fluoride salt baths. The presence of the alloying elements, Al, Fe, or Mn, in Ni drastically reduces or lelements intergranular attack usually found in unalloyed Ni exposed to a fluorination environment. In fluorination environments, the effect of adding Co to Ni on subsequent corrosion by intergranular attack of the binary is unclear. These reported tests showed that serious intergranular attack of a 95% Ni --5% Co specimen occurred. On the other hand, this test series and previous series …
Date: November 13, 1962
Creator: Kegley, T. M., Jr. & Litman, A. P.
Object Type: Report
System: The UNT Digital Library
CRITICALITY EXCURSION OF NOVEMBER 10, 1961 (open access)

CRITICALITY EXCURSION OF NOVEMBER 10, 1961

A criticality excursion occurred at the Oak Ridge Critical Experiments Laboratory on November l0, l961 as enriched uranium metal, neutron reflected and moderated by hydrogen, was being assembled. It is estimated that the energy yield was between 10/sup 15/ and 10/sup 16/ fissions. There was no personnel exposure or property damage. Fission product contamination, both airborne and contained in the metal, decayed sufficiently overnight to allow unhindered continuation of the experiment. The excursion was caused by a too rapid approach of the two sections of uranium constituting the experiment. (auth)
Date: February 13, 1962
Creator: Callihan, D.
Object Type: Report
System: The UNT Digital Library
EFFECT OF NEUTRON IRRADIATION ON MATERIALS SUBJECTED TO MULTI-AXIAL STRESS DISTRIBUTIONS. Quarterly Report for the Period Ending June 30, 1962 (open access)

EFFECT OF NEUTRON IRRADIATION ON MATERIALS SUBJECTED TO MULTI-AXIAL STRESS DISTRIBUTIONS. Quarterly Report for the Period Ending June 30, 1962

Activities in a program to determine the effects of neutron irradiation on A-302B steel are reported. Plans are discussed concerning performance tests on tensile, notched tensile, tube, and Charpy specimens. An irradiation capsule design was finalized. A theoretical analysis of the critical conditions arising in a tube subjected to both internal pressure and axial load is included. (J.R.D.)
Date: August 13, 1962
Creator: Trozera, T A
Object Type: Report
System: The UNT Digital Library
FORMATION CONSTANTS OF THE COMPLEX SPECIES FORMED BY INTERACTION OF RARE- EARTH NITRILOTRIACETATE COMPLEXES WITH AN EQUIVALENT AMOUNT OF BASE (open access)

FORMATION CONSTANTS OF THE COMPLEX SPECIES FORMED BY INTERACTION OF RARE- EARTH NITRILOTRIACETATE COMPLEXES WITH AN EQUIVALENT AMOUNT OF BASE

The formation constants of the RChOH/sup -/ species, formed by interaction of individual rare-earth nitrilotriacetate species and KOH at 25 deg C and an ionic strength of 0.1 were determined by the potentiometric method, i.e., computed from the pH values of equilibrium mixtures containing varying proportions of rare-earth complex and base. The relations of these constants to the ion-exchange separation of rare earths at high pH were discussed. (auth)
Date: April 13, 1962
Creator: Gupta, A.K. & Powell, J.E.
Object Type: Report
System: The UNT Digital Library
HIGH-TEMPERATURE VAPOR-FILLED THERMIONIC CONVERTER. Quarterly Technical Progress Report, March 15 through June 30, 1962 (open access)

HIGH-TEMPERATURE VAPOR-FILLED THERMIONIC CONVERTER. Quarterly Technical Progress Report, March 15 through June 30, 1962

Research covers the work done on a bench test of an unclad thermionic converter. The objective is to produce an efficient, high-power-density, long- life thermionic power converter using a uranium-zirconium-carbide emitter and a high-temperature nickel collector. (auth)
Date: July 13, 1962
Creator: Skoff, R.
Object Type: Report
System: The UNT Digital Library
Irradiation Processing Department monthly report, July 1962 (open access)

Irradiation Processing Department monthly report, July 1962

This document details activities of the Irradiation Processing Department during the month of July, 1962. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; and NPR Project.
Date: August 13, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Irradiation Processing Department monthly report, May 1962 (open access)

Irradiation Processing Department monthly report, May 1962

This document details activities of the Irradiation Processing Department during the month of May 1962.
Date: June 13, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Matrix Isolation Studies of High-Temperature Species Group II Chlorides (open access)

Matrix Isolation Studies of High-Temperature Species Group II Chlorides

A matrix isolation technique for the investigation of infrared absorption spectra of molecules of hightemperature species trapped in a pseudo- gas phase'' is described. The spectra of the dichlorides of zinc, cadmium, and mercury in argon, krypton, and xenon matrices are reported. Presence in the gas phase of dimers of zinc chloride and mercuric chloride is noted. An absorption band, previously reported as due to the degenerate bending motion of zinc chloride, is attributed to zinc dimer. (auth)
Date: September 13, 1962
Creator: McNamee, R. W., Jr.
Object Type: Thesis or Dissertation
System: The UNT Digital Library
Mobile energy depot feasibility study: summary report (open access)

Mobile energy depot feasibility study: summary report

Declassified 28 Aug 1973. Various methods of producing and using nuclear power for military land vehicles and other military equipment were investigated and evaluated. A nuclear-powered mobile energy depot (MED) would move with advancing armies and produce vehicle fuels from materials readily available in the field. This would make mechanized units independent of external fuel supplies for extended periods, and permit them to move quickly and easily to areas impossible for units that depend on the customary fuel supply lines. Many possible MED systems were evaluated on the basis of energy sources, fuel manufacturing (by both conventional and chemonuclear processes), fuel storage and transportation, and fuel utilization in both present-day internal-combustion engines and power units of the future (i.e., fuel cells). The applications of more than a dozen MED systems to vehicular propulsion were studied. (auth)
Date: July 13, 1962
Creator: Burwell, S. B.; Carlson, J. A.; Clark, R. G.; Donelan, L. E.; Erwin, A. F.; Grimes, P. G. et al.
Object Type: Report
System: The UNT Digital Library
Monte Carlo Calculations. III. A General Study of Bimolecular Exchange Reactions (open access)

Monte Carlo Calculations. III. A General Study of Bimolecular Exchange Reactions

None
Date: December 13, 1962
Creator: Blais, N. C. & Bunker, D. L.
Object Type: Report
System: The UNT Digital Library
Naval applications program (open access)

Naval applications program

This memorandum provides an discussion as to the possible application of nuclear ramjet propulsion in a submarine-based missile system. Questions are raised as to modifications required, compatibility with present submarine launch facilities, and missile and booster volume.
Date: June 13, 1962
Creator: Hadley, J. W.
Object Type: Report
System: The UNT Digital Library
Periodic Characterization of Radioactive Waste Disposal Effluents. Core I Seed 3. Test Evaluation (open access)

Periodic Characterization of Radioactive Waste Disposal Effluents. Core I Seed 3. Test Evaluation

Data are given on the radioactive nuclides present in waste disposal effluents during Nov. 1961. The concentrations of all activities was well within established limits for discharge to the environment. (C.H.)
Date: June 13, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Process Improvement Transition Authorization IP-20-I: Increased graphite temperature limits and use of nitrogen in the K reactors (open access)

Process Improvement Transition Authorization IP-20-I: Increased graphite temperature limits and use of nitrogen in the K reactors

The objectives of this Process Improvement Transition Authorization (PITA) for KE and KW reactors are to authorize a flat 700 C graphite temperature limit in the bulk of the graphite, with a conditional 850 C limit in the 0.130 coring zone only, and in conjunction therewith to provide for routine use of nitrogen instead of carbon dioxide in the reactor atmosphere. These temperatures as quoted apply to filler blocks in the vicinity of normal channels, and are maximum limits.
Date: June 13, 1962
Creator: Baars, R. E.
Object Type: Report
System: The UNT Digital Library
Radiation Effects in Borides, Part I - Helium Release and Swelling in Irradiated Borides (open access)

Radiation Effects in Borides, Part I - Helium Release and Swelling in Irradiated Borides

The principal objective of the work being reported was to irradiate a variety of borides in order to assess the relationship of crystal structure to helium retention and structural changes. A secondary objective was to compare the irradiation behavior of powders and dense solids. Another objective was to compare the behavior of borides with similar crystal structures but having metal atoms with vastly different absorption cross-sections, for example, zirconium and hafnium diborides.
Date: February 13, 1962
Creator: Hoyt, E. W. & Zimmerman, D. L.
Object Type: Report
System: The UNT Digital Library
Reactor statistics: Section 3, April 1961--May 15, 1962 (open access)

Reactor statistics: Section 3, April 1961--May 15, 1962

The following discussion and attached summary report is sent to you to illustrate the type of information that is currently in data processing machine language and available to those who require it. The reports are comprised of three major sections. The first is a map indicating the number of recordings of data in the category defined by the function number code. The second is a summary of the data, in terms of hours, for each of the functions performed during an outage, except secondary function code number 21 which is the number of tubes associated with the basic function performed. The third is a summary of the secondary functions performed within a basic function class, the associated delay total, and the number of tubes involved for those functions where a delineation by tube count may be of interest. The function code numbers relate directly to the definitions of the hours expended for charge-discharge, rupture removal, tube leak repair, tube replacement, and so forth. These definitive classes are taken from the distribution records supplied by the various reactor analysts and summarized by the Reports and Statistics group in the IPD Production Operation.
Date: June 13, 1962
Creator: Burke, R. C.
Object Type: Report
System: The UNT Digital Library
Reactor statistics Section 3, April 1961--May 15, 1962 (open access)

Reactor statistics Section 3, April 1961--May 15, 1962

None
Date: June 13, 1962
Creator: Burke, R. C.
Object Type: Report
System: The UNT Digital Library
Reactor statistics: Section 3, April 1961--May 15, 1962. Reactor Simulation Study, Reactor 4 (open access)

Reactor statistics: Section 3, April 1961--May 15, 1962. Reactor Simulation Study, Reactor 4

This discussion and attached summary report illustrate the type of information that was in data processing machine language and available to those who require it. The reports are comprised of three major sections. The first is a map indicating the number of recordings of data in the cateogry defined by the function number code. The second is a summary of the data, in terms of hours, for each of the functions performed during an outage, except secondary function code number 21 which is the number of tubes associated with the basic function performed. The third is a summary of the secondary functions performed within a basic function class, the associated delay total, and the number of tubes involved for those functions where a delineation by tube count may be of interest. The function code numbers relate directly to the definitions of the hours expended for charge-discharge, rupture removal, tube leak repair, tube replacement, and so forth. These definitive classes are taken from the distribution records supplied by the various reactor analysts and summarized by the Reports and Statistics group in the IPD Production Operation.
Date: June 13, 1962
Creator: Burke, R. C.
Object Type: Report
System: The UNT Digital Library
Reactor statistics - Section III, April 1961 - May 15, 1962 (open access)

Reactor statistics - Section III, April 1961 - May 15, 1962

This report is a summary of the way information is stored on the maintenance histories of the Hanford Production Reactors. Twenty two different categories are considered as primary reasons for maintenance down times. The data is stored in terms of hours spent on different tasks, and is also grouped by the controlling cause of the outage.
Date: June 13, 1962
Creator: Burke, R. C.
Object Type: Report
System: The UNT Digital Library
Reactor statistics, Section III, April 1961--May 15, 1962. Reactor 2 (open access)

Reactor statistics, Section III, April 1961--May 15, 1962. Reactor 2

The discussion and summary report presented here illustrate the type of information that is currently in data processing machine language and available to those who require it. During the progress meetings at which these reports were discussed, several persons indicated a desire to have a documented explanation of the report and a personal copy to scan. This is the answer to these requests. The reports are comprised of three major sections. The first is a map indicating the number of recordings of data in the category defined by the function number code. The second is a summary of the data, in terms of hours, for each of the functions performed during an outage, except secondary function code number 21 which is the number of tubes associated with the basic function performed. The third is a summary of the secondary functions performed within a basic function class, the associated delay total, and the number of tubes involved for those functions where a delineation by tube count may be of interest.
Date: June 13, 1962
Creator: Burke, R.C.
Object Type: Report
System: The UNT Digital Library
Reactor statistics, Section III, April 1961--May 15, 1962. Reactor 3 (open access)

Reactor statistics, Section III, April 1961--May 15, 1962. Reactor 3

The discussion and summary report presented here illustrate the type of information that is currently in data processing machine language and available to those who require it. During the progress meetings at which these reports were discussed, several persons indicated a desire to have a documented explanation of the report and a personal copy to scan. This is the answer to these requests. The reports are comprised of three major sections. The first is a map indicating the number of recordings of data in the category defined by the function number code. The second is a summary of the data, in terms of hours, for each of the functions performed during an outage, except secondary function code number 21 which is the number of tubes associated with the basic function performed. The third is a summary of the secondary functions performed within a basic function class, the associated delay total, and the number of tubes involved for those functions where a delineation by tube count may be of interest.
Date: June 13, 1962
Creator: Burke, R.C.
Object Type: Report
System: The UNT Digital Library
Reactor statistics, Section III, April 1961--May 15, 1962. Reactor Simulation Study, Reactor 5 (open access)

Reactor statistics, Section III, April 1961--May 15, 1962. Reactor Simulation Study, Reactor 5

The discussion and summary report presented here illustrate the type of information that is currently in data processing machine language and available to those who require it. During the progress meetings at which these reports were discussed, several persons indicated a desire to have a documented explanation of the report and a personal copy to scan. This is the answer to these requests. The reports are comprised of three major sections. The first is a map indicating the number of recordings of data in the category defined by the function number code. The second is a summary of the data, in terms of hours, for each of the functions performed during an outage, except secondary function code number 21 which is the number of tubes associated with the basic function performed. The third is a summary of the secondary functions performed within a basic function class, the associated delay total, and the number of tubes involved for those functions where a delineation by tube count may be of interest.
Date: June 13, 1962
Creator: Burke, R.C.
Object Type: Report
System: The UNT Digital Library
Section 3 reactor statistics: April 1961--May 15, 1962 (open access)

Section 3 reactor statistics: April 1961--May 15, 1962

This discussion and summary report illustrate the type of information that is in data processing machine language and available to those who require it. The reports are comprised of three major sections. The first is a map indicating the number of recordings of data in the category defined by the function number code. The second is a summary of the data, in term of hours, for each of the functions performed during an outage, except secondary function code number 21 which is the number of tubes associated with the basic function performed. The third is a summary of the secondary functions performed with a basic function class, the associated delay total and the number of tubes involved for those functions where a delineation by tube count may be of interest.
Date: June 13, 1962
Creator: Burke, R. C.
Object Type: Report
System: The UNT Digital Library