Reactor and Materials Technology Monthly Report, May 1965 (open access)

Reactor and Materials Technology Monthly Report, May 1965

This report discusses research at the Hanford production reactors on reactor materials and reactor technology.
Date: June 15, 1965
Creator: Albaugh, F. W.
Object Type: Report
System: The UNT Digital Library
Irradiation Processing Department semiannual research and development report (open access)

Irradiation Processing Department semiannual research and development report

This report discusses research and development programs of the Irradiation Processing Department in FY-1965.
Date: June 1, 1965
Creator: Ambrose, T. W.
Object Type: Report
System: The UNT Digital Library
Research and Engineering Operation, Irradiation Processing Department monthly record report, May 1965 (open access)

Research and Engineering Operation, Irradiation Processing Department monthly record report, May 1965

Process and development activities reported include: depleted uranium irradiations, thoria irradiation, and hot die sizing. Reactor engineering activities include: brittle fracture of 190-C tanks, increased graphite temperature limits for the F reactor, VSR channel caulking, K reactor downcomer flow, zircaloy hydriding, and ribbed zircaloy process tubes. Reactor physics activities include: thoria irradiations, E-D irradiations, boiling protection with the high speed scanner, and in-core flux monitoring. Radiological engineering activities include: radiation control, classification, radiation occurrences, effluent activity data, and well car shielding. Process standards are listed, along with audits, and fuel failure experience. Operational physics and process physics studies are presented. Lastly, testing activities are detailed.
Date: June 4, 1965
Creator: Ambrose, T. W.
Object Type: Report
System: The UNT Digital Library
Comparison of Heatflux Sensors Using Thermal Radiation Sources (open access)

Comparison of Heatflux Sensors Using Thermal Radiation Sources

None
Date: June 1, 1965
Creator: Barber, J. A.
Object Type: Report
System: The UNT Digital Library
IRRADIATION EFFECTS IN THE EGCR FUEL (open access)

IRRADIATION EFFECTS IN THE EGCR FUEL

None
Date: June 1, 1965
Creator: Baumann, C. D.
Object Type: Report
System: The UNT Digital Library
Irradiation Effects in the EGCR Fuel (open access)

Irradiation Effects in the EGCR Fuel

From foreword: "This is a documentation of the experiments performed and the data accumulated during the early period of the Experimental Gas-Cooled Reactor (EGCR) fuel element design."
Date: June 1965
Creator: Baumann, C. D.
Object Type: Report
System: The UNT Digital Library
Evaluation of macroreticular anion exchange resin - RTA-893-R (open access)

Evaluation of macroreticular anion exchange resin - RTA-893-R

The macroreticular anion exchange resin, Amberlite IRA-900-OH, and an experimental resin from Ionac Chemical Company were irradiated by a /sup 60/Co source to doses of 5 x 10/sup 7/ rad and 10/sup 8/ rad. These doses approximate or exceed the dose encountered by the deionizer resins in 100-Area service. The loss in exchange capacity and the volume changes of Amberlite IRA-900 on irradiation were similar to those found previously for Amberlite IRA-400. The Ionac experimental resin, which had a considerably lower initial exchange capacity, likewise was not stable to radiation. It is concluded that Amberlite IRA-900 offers no advantage over Amberlite IRA-400 for 100-Area purification service. Since there is little justification for further evaluation of macroreticular resin for 100-Area use, the present work completes RTA-893-R.
Date: June 7, 1965
Creator: Baumann, E. W.
Object Type: Report
System: The UNT Digital Library
Radiation Damage in Hexagonal Close-Packed Metals and Alloys (open access)

Radiation Damage in Hexagonal Close-Packed Metals and Alloys

None
Date: June 1, 1965
Creator: Bement, A. L.
Object Type: Report
System: The UNT Digital Library
PAX nine group element library (open access)

PAX nine group element library

None
Date: June 14, 1965
Creator: Bevard, D. G.
Object Type: Report
System: The UNT Digital Library
Plan for test cell A narrow band data acquisition accuracy test (open access)

Plan for test cell A narrow band data acquisition accuracy test

None
Date: June 25, 1965
Creator: Blau, P.
Object Type: Report
System: The UNT Digital Library
HIGH-TEMPERATURE CHEMICAL STABILITY OF REFRACTORY-BASE ALLOYS IN HIGH VACUUM (open access)

HIGH-TEMPERATURE CHEMICAL STABILITY OF REFRACTORY-BASE ALLOYS IN HIGH VACUUM

None
Date: June 1, 1965
Creator: Bourgette, D T
Object Type: Article
System: The UNT Digital Library
Status of special reactor process tube loadings, June 1, 1965 (open access)

Status of special reactor process tube loadings, June 1, 1965

This report shows the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials.
Date: June 8, 1965
Creator: Bown, R. W.
Object Type: Report
System: The UNT Digital Library
Special yield data analyses for core analysis material key No. 6706-C-N (open access)

Special yield data analyses for core analysis material key No. 6706-C-N

This document contains one table on the 95% confidence levels for the concentration of Plutonium, Uranium, Americium 241, Curium 242, and Neptunium 237 in an undisclosed material.
Date: June 16, 1965
Creator: Braymen, W.H. & Smith, H.E.
Object Type: Report
System: The UNT Digital Library
Special yield data analyses for core analysis material key {number_sign} 6887-KW-E (open access)

Special yield data analyses for core analysis material key {number_sign} 6887-KW-E

The report consists of three tables listing the chemical and isotopic composition of samples named KW-C-2, KW-C-3, and pig. Plutonium 238, 239, 240, 241, and 242, and uranium 234, 235, 236, and 238 are given in weight percent. Samples vary from 1.8--3.2 lbs U/gal and 0.5--0.85 gms Pu/gal. Concentrations of Am-241, Cm-242, and Np-237 are also reported.
Date: June 16, 1965
Creator: Braymen, W.H. & Smith, H.E.
Object Type: Report
System: The UNT Digital Library
Molten-Salt Reactor Program Semiannual Progress Report for Period Ending February 28, 1965 (open access)

Molten-Salt Reactor Program Semiannual Progress Report for Period Ending February 28, 1965

Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Progress of operations, construction, engineering analysis, and development is presented. This report includes tables, illustrations, and photographs.
Date: June 1965
Creator: Briggs, R. B.
Object Type: Report
System: The UNT Digital Library
NIMBUS DYNAMICS ANALYSIS FOR EJECTION MECHANISM (open access)

NIMBUS DYNAMICS ANALYSIS FOR EJECTION MECHANISM

None
Date: June 1, 1965
Creator: Burgio, R. G. & Miller, M. C.
Object Type: Report
System: The UNT Digital Library
CHEMICAL EVOLUTION (open access)

CHEMICAL EVOLUTION

How did life come to be on the surface of the earth? Darwin himself recognized that his basic idea of evolution by variation and natural selection must be a continuous process extending backward in time through that period in which the first living things arose and into the period of 'Chemical Evolution' which preceded it. We are approaching the examination of these events by two routes. One is to seek for evidence in the ancient rocks of the earth which were laid down prior to that time in which organisms capable of leaving their skeletons in the rocks to be fossilized were in existence. This period is sometime prior to approximately 600 million years ago. The earth is believed to have taken its present form approximately 4700 million years ago. We have found in rocks whose age is about 1000 million years certain organic molecules which are closely related to the green pigment of plants, chlorophyll. This seems to establish that green plants were already fluorishing prior to that time. We have now found in rocks of still greater age, namely, 2500 million years, the same kinds of molecules mentioned above which can be attributed to the presence of living …
Date: June 1, 1965
Creator: Calvin, Melvin
Object Type: Report
System: The UNT Digital Library
Neutron and fission yields from high-energy deuterons in infinite /sup 238/U targets (open access)

Neutron and fission yields from high-energy deuterons in infinite /sup 238/U targets

Early work on the interaction of high energy deuterons with large /sup 238/U targets is reexamined and current theoretical study is discussed. Results of fission and neutron yield calculations are compared with experiment. (SDF)
Date: June 28, 1965
Creator: Canfield, E.
Object Type: Report
System: The UNT Digital Library
Determination of Minimum Insulation Resistance Requirements for Outer Reflector Gas Temperature Thermocouples (open access)

Determination of Minimum Insulation Resistance Requirements for Outer Reflector Gas Temperature Thermocouples

This report describes the analysis performed in determining the lowest pemissable insulation resistance for the exposed junction copper/constantan thermocouples to measure outer reflector drum annulius, drum vane and beryllium exit gas temperature.
Date: June 11, 1965
Creator: Chambers, G.M.
Object Type: Report
System: The UNT Digital Library
Internal instrumentation cable transitioning (open access)

Internal instrumentation cable transitioning

None
Date: June 29, 1965
Creator: Chambers, G.M.
Object Type: Report
System: The UNT Digital Library
PRELIMINARY DESIGN REPORT-PROTOTYPE STEAM GENERATOR. VOL. 1. GENERAL. SODIUM-HEATED STEAM GENERATOR DEVELOPMENT (open access)

PRELIMINARY DESIGN REPORT-PROTOTYPE STEAM GENERATOR. VOL. 1. GENERAL. SODIUM-HEATED STEAM GENERATOR DEVELOPMENT

None
Date: June 1, 1965
Creator: Clark, J.G.
Object Type: Report
System: The UNT Digital Library
PHYSICAL PROPERTIES OF FUSED SALT MIXTURES. Data from Open Literature, 1907-1962 (open access)

PHYSICAL PROPERTIES OF FUSED SALT MIXTURES. Data from Open Literature, 1907-1962

None
Date: June 15, 1965
Creator: Clark, P.V.
Object Type: Report
System: The UNT Digital Library
Physical Properties of Fused Salt Mixtures (open access)

Physical Properties of Fused Salt Mixtures

Foreword: The purpose of the present work was to collect and tabulate data on fused salt mixtures.
Date: June 15, 1965
Creator: Clark, Paul V.
Object Type: Report
System: The UNT Digital Library
Laboratory Development of Processes for Fixation of High-Level Radioactive Waste in Glassy Solids. [Part] 3, Wastes from the Purex Solvent Extraction Process (open access)

Laboratory Development of Processes for Fixation of High-Level Radioactive Waste in Glassy Solids. [Part] 3, Wastes from the Purex Solvent Extraction Process

Report concerning the fixation and disposal of toxic waste derived from the Purex solvent extraction process.
Date: June 1965
Creator: Clark, W. E.; Godbee, H. W. & Fitzgerald, C. L.
Object Type: Report
System: The UNT Digital Library