Resource Type
Collection
Serial/Series Title
Atomic Energy Commission Reports
3
Notes of Monthly Component Test Program Review Meeting Held with SNPO at WANL
2
TID
2
Chemical Processing Department Monthly Report
1
Fiscal Year 1966
1
ORNL (Series)
1
Oak Ridge National Laboratory Reports
1
Office of Saline Water Reports
1
Project Sulky
1
Report (U.S. Atomic Energy Commission)
1
4 More
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States
Year
Month
Language
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MULTI-NODE SIMULATION OF THE FFTF INTERMEDIATE HEAT EXCHANGER.
None
Date:
January 1, 1966
Creator:
Gerhardstein, L.H.
System:
The UNT Digital Library
DEEP SEA RADIOISOTOPE-FUELED THERMOELECTRIC GENERATOR POWER SUPPLY SYSTEM. SNAP-21B PROGRAM, PHASE I. Final Summary Report.
None
Date:
January 1, 1966
Creator:
Benson, D.; Panneman, R. & Yanisch, V. Jr.
System:
The UNT Digital Library
Preparation and Properties of Plutonium Carbonitride.
None
Date:
January 1, 1966
Creator:
Guyton, J. L. & Thompson, M. A.
System:
The UNT Digital Library
An Analog Computer Study of the Control Characteristics of the Medium Power Reactor Experiment System Including the Turbine-Generator.
None
Date:
January 1, 1966
Creator:
Burke, O. W.; Ditto, S. J. & Walker, C. S.
System:
The UNT Digital Library
THERMAL CONDUCTIVITY AND ELECTRICAL RESISTIVITY OF ZIRCALOY-4.
None
Date:
January 1, 1966
Creator:
Feith, A.D.
System:
The UNT Digital Library
FINAL REPORT OF OFF-SITE SURVEILLANCE FOR THE PHOEBUS 1-A EXPERIMENT.
None
Date:
January 1, 1966
Creator:
unknown
System:
The UNT Digital Library
Design Study and Economic Evaluation of Head-End Reprocessing Facility Integral With an HTGR Power Plant
Preliminary designs and costs have been developed for nuclear fuel head-end reprocessing facilities integral with a large High-Temperature Gas-Cooled Reactor (HTGR) power plant.
Date:
January 1, 1966
Creator:
Stelling, H. E. & Steyer, K. G.
System:
The UNT Digital Library
Pacific Northwest Laboratory Monthly Activities Report for November 1966.
None
Date:
January 1, 1966
Creator:
unknown
System:
The UNT Digital Library
SCTI: Pressure Reducing Valve Body Failure.
None
Date:
January 1, 1966
Creator:
Wagner, R. K.
System:
The UNT Digital Library
CONTROL CONCEPTS AND DIGITAL COMPUTER ANALYSIS OF THE MPRE FLUID SYSTEM.
None
Date:
January 1, 1966
Creator:
LaVerne, M.E.
System:
The UNT Digital Library
MPRE FUEL ELEMENTS: MANUFACTURE, INSPECTION, DRAWINGS, AND SPECIFICATIONS.
None
Date:
January 1, 1966
Creator:
Tolson, G.M.
System:
The UNT Digital Library
ALTERNATE REACTOR CONCEPT DESIGN STUDY FOR THE FAST FLUX TEST FACILITY. FIXED SHIELD PLUG, VERTICAL CORE REACTOR CONCEPT.
None
Date:
January 1, 1966
Creator:
Duffy, J.G.; Hess, J.W.; Matte, J.; Mueller, R.E. & White, J.R.
System:
The UNT Digital Library
Thermal diffusivity of MTR-ETR type fuel plates. Final report
Thermal diffusivity of Al-clad MTR-ETR type fuel plates was measured from room temperature to 600/sup 0/C. (DLC)
Date:
January 10, 1966
Creator:
Bates, J.L.
System:
The UNT Digital Library
Mechanism and kinetics of mineral absorption by plants. Annual progress report, October 1, 1965-September 30, 1966
Plant nutrition was studied as a relation between aerobic respiration and ion uptake in barley. Potassium, chlorine, lithium, sodium, calcium, sulfates, and bicarbonates were studied by root absorption in varying concentrations of carbon dioxide atmospheres. (PSB)
Date:
January 1, 1966
Creator:
Jacobson, L. & Overstreet, R.
System:
The UNT Digital Library
Chemical Processing Division monthly report, June 1966
This report for June 1966, from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance: Financial operations; facilities engineering; research; and employee relations.
Date:
January 1, 1966
Creator:
unknown
System:
The UNT Digital Library
Report to the FEDC working committee for the period September 1965--January 1966
This report to the FEDC Working Committee details activities in N-Reactor fuel element fabrication and materials testing for the time period of September 1965 to January 1966.
Date:
January 5, 1966
Creator:
Lewis, M. & Minor, J. E.
System:
The UNT Digital Library
K Reactor uncooled HCR: Equilibrium temperature study
Temperature calculations were made on a proposed design of an uncooled horizonal control rod (HCR) for the K Reactors. The calculations were performed with the aid of a FORTRAN coded heat transfer program for the UNIVAC 1107. The results of the calculations indicate that such a control rod is feasible for.4400 Mw and 5000 Mw operation provided certain precautions are taken. These precautions include assuring good contact between the rod and the graphite in the high flux regions and Providing reasonable contact between the graphite stack and the graphite slider plates that will be placed in the bottom of the rod channels prior to rod insertion and use.
Date:
January 24, 1966
Creator:
Agar, J. D.
System:
The UNT Digital Library
Douglas United Nuclear, Inc. production inventory and manufacturing statement December 31, 1965 and FY to date
None
Date:
January 24, 1966
Creator:
Bombino, J. J.
System:
The UNT Digital Library
Minutes of meetings to discuss extraction test studies of ceramic coproduct targets
The meetings were held on December 6 and 7, 1965 in the 325 Building conference room at PNL. The objectives of the meetings were: (1) To review the status of the ceramic coproduct target element fabrication technology and the subsequent extraction processing technology of irradiated elements as developed at PNL. (2) To discuss the feasibility of performing extraction studies of irradiated coproduct target elements at the SRL pilot plant facilities in demonstrating the capability of coproduct production in N-Reactor. (3) To identify potential problem areas that could arise when the laboratory scale extraction process would be performed on a pilot plant scale in the existing SRL facility.
Date:
January 3, 1966
Creator:
Cooperstein, R.
System:
The UNT Digital Library
Technical requirements and criteria for the coproduct target element
The technical basis and criteria for five requirements are presented. Requirement 1 is that the coproduct target element shall be compatible with the driver element in the environment of the N-Reactor primary loop. Requirement 2 is that the target element shall be compatible with nuclear safety requirements under all credible accident conditions. Requirement 3 is that the coproduct element shall be unmistakable from other fuel element models in use or expected to be in use during the period 1966-68. Requirement 4 is that the target element shall have a degree of reliability that is compatible with reactor performance objectives. Requirement 5 is that the target element shall be compatible with procedures for post-irradiation processing.
Date:
January 7, 1966
Creator:
Evans, T. W.
System:
The UNT Digital Library
Analyses of Crude Oils From 546 Important Oilfields in the United States
This report analyses the crude oils from many oilfields within the U.S.
Date:
January 1, 1966
Creator:
McKinney, C. M.; Ferrero, E. P. & Wenger, W. J.
System:
The UNT Digital Library
Theoretical density of lithium aluminate updated
The ''handbook'' density for LiAlO/sub 2/ is 2.55 g/cc. Recent data show that it should be revised to 2.62 g/cc. In the future densities reported as percent of theoretical should be based on 2.62 g/cc as being 100 percent. Values quoted on this basis will be more realistic. In order to avoid confusion it will be necessary to state which number percent of theoretical density are based upon--that is, ''2.62 g/cc = 100 percent,'' or ''2.55 g/cc = 100 percent.'' For the convenience of those working directly with the material, a conversion chart is included along with a table which gives density (g/cc) versus percent density based on 2.62 g/cc.
Date:
January 12, 1966
Creator:
Gurwell, W. E.
System:
The UNT Digital Library
FORMATION OF TRANSURANIUM ISOTOPES IN POWER REACTORS
In recent years there has been an increased interest in the use of transuranium isctopes for special power applications. Moreover, as the civilian power reactor economy expands, a large quantity of such isotopes will be formed in reactors using slightly enriched uranium fuel and, more particularly, in reactors which recycle the higher isotopes they form. This report, consisting mainly of computer printouts, indicates the yields of transuranium isotopes from different fueling methods. Since water reactors will be the predominate type of power reactor for at least a decade, most of the values presented here are derived from simulated water reactors.
Date:
January 1, 1966
Creator:
Deonigi, D.E.
System:
The UNT Digital Library
Research and Engineering Operation, N-Reactor Department monthly record report
The reactor was manually scrammed from 3870 Mw on January 4 due to a rupture suspect. The failure was subsequently identified as a fretting type on the inner surface of a single tube test fuel element. The evidence indicates that a buggy spring support vibrating against the inner spring of the fuel caused the clad perforation. The remaining column of single tube fuel was discharged. The reactor operated at 3730 Mw until January 7, when the loss of instrument air supply caused the reactor to scram. Upon reinstatement of the instrument air supply the reactor was started up on January 8 and achieved 4000 Mw operation on January 10. After the startup on January 8, the plant operated at essentially full power until January 13. At this time a scram occurred due to loss of header pressure on the steam supply to the drive turbines. The scram was found to have been due to energizing an improperly wired control panel which was a part of the tie-in of the sixth cell work. While the reactor was down, heat exchanger 3B was hydrostatically tested and repaired. A leak in the auxiliary plant boiler was also repaired and an inspection of the …
Date:
January 31, 1966
Creator:
Leverett, M. C.
System:
The UNT Digital Library