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AEC Policy and Action Paper on Controlled Thermonuclear Research
None
Date:
June 1, 1966
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
ANNUAL REPORT OF DIVISION ANALYTICAL BRANCH FOR 1965
None
Date:
June 1, 1966
Creator:
Shank, Ralph C.
Object Type:
Report
System:
The UNT Digital Library
ATR FUEL MATERIALS DEVELOPMENT IRRADIATION RESULTS. PART II
None
Date:
June 1, 1966
Creator:
Walker, V. A.; Graber, M. J. & Gibson, G. W.
Object Type:
Report
System:
The UNT Digital Library
Boiling Nuclear Superheater (Bonus) Power Station: Punta Higuera Site Near Rincon, Puerto Rico. Project Completion Report
None
Date:
June 1, 1966
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Calculations of hard sphere packings in large cylinders.
This report is about the Calculations of hard-sphere packings in large cylinders.
Date:
June 1, 1966
Creator:
Clancy, B.E.
Object Type:
Report
System:
The UNT Digital Library
CATALOG OF NUCLEAR REACTOR CONCEPTS. PART I. HOMOGENEOUS AND QUASI- HOMOGENEOUS REACTORS. SECTION VI. SOLID HOMOGENEOUS (SEMIHOMOGENEOUS) REACTORS
None
Date:
June 1, 1966
Creator:
Teeter, C.E.; Lecky, J.A. & Martens, J.H.
Object Type:
Report
System:
The UNT Digital Library
Cfdts Data Analysis Final Report
This is a data analysis report of the 25 tests conducted with the Cold Flow Development Test System during October and November of 1965.
Date:
June 1, 1966
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
CHARACTERISTICS OF THE AEROSOL PRODUCED FROM BURNING PLUTONIUM
None
Date:
June 1, 1966
Creator:
Ettinger, H.J.; Moss, W.D. & Busey, H.
Object Type:
Report
System:
The UNT Digital Library
CHARGE COLLECTION AND CHARGE-COLLECTION TIME IN SEMICONDUCTOR PARTICLE DETECTORS
None
Date:
June 1, 1966
Creator:
Hansen, N.J.
Object Type:
Report
System:
The UNT Digital Library
Compatibility of strontium space fuel forms
None
Date:
June 1, 1966
Creator:
Miraglia, F. J., Jr.
Object Type:
Report
System:
The UNT Digital Library
Conjugacy to Unitary Groups Within the Infinite-Dimensional Symplectic Group
None
Date:
June 1, 1966
Creator:
Segal, I. E.
Object Type:
Report
System:
The UNT Digital Library
Crevice-Galvanic Corrosion of Aluminum
None
Date:
June 1, 1966
Creator:
Mori, S.; Draley, J. E. & Loess, R. E.
Object Type:
Report
System:
The UNT Digital Library
La Crosse boiling water reactor radio and water chemistry manual
None
Date:
June 1, 1966
Creator:
Mueller, J. J.
Object Type:
Report
System:
The UNT Digital Library
Design Equation Analysis for Heat Transfer to Cryogenic Hydrogen at Pressures From 600 to 1500 Psia and Wall-to-Bulk Temperature Ratios to 20
This report compares experimental forced convection heat transfer data for cryogenic hydrogen with a number of equations that have been proposed for predicting liquid-side heat transfer coefficients for convectively-cooled rocket nozzles. Experimental data have been taken from tests in both straight and curved electrically-heated tubes at pressures ranging from 600 to 1500 psi and at coolant temperatures less than 200°R. The problem of extrapolating these equations to test conditions not explicity achieved in experiments is also described.
Date:
June 1, 1966
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
The Determination of Axial Flux and Axial Exposure Distributions in the HWCTR
Methods were developed to calculate axial flux distributions from a knowledge of control rod position and fuel exposure during full-power nuclear operation of the HWCTR. The maximum specific power, heat flux, and core temperature of each fuel assembly were determined from the flux distributions to ensure safe operation of the reactor. Also, methods were developed to compute the axial exposure distribution of fuel assemblies as required for evaluation of the irradiation performance of each test fuel design.
Date:
June 1, 1966
Creator:
Gorrell, T. C.
Object Type:
Report
System:
The UNT Digital Library
ELECTROCHEMICAL CORROSION STUDIES OF SNAP CONTAINER MATERIALS
None
Date:
June 1, 1966
Creator:
Kubose, D. A. & Cordova, H. I.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of the thermal response of three proposed reactor designs to post-operational heating conditions
None
Date:
June 1, 1966
Creator:
Trammell, M.R. & McCune, W.C.
Object Type:
Report
System:
The UNT Digital Library
FACILITIES, CAPABILITIES, AND EXPERIENCE IN LIQUID METALS AND FAST REACTOR RESEARCH AND DEVELOPMENT
None
Date:
June 1, 1966
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
FAST FLUX TEST FACILITY DRIVER FUEL MEETING
The Pacific Northwest Laboratory has convened this meeting to enlist the best talents of our laboratories and industry in soliciting factual, technical information pertinent to the Pacific Northwest's Laboratory's evaluation of the potential fuel systems for the Fast Flux Test Facility. The particular factors emphasized for these fuel systems are those associated with safety, ability to meet testing objectives, and economics. The proceedings includes twenty-three presentations, along with a transcript of the discussion following each, as well as a summary discussion.
Date:
June 1, 1966
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Fuels and materials development program quarterly progress report for period ending March 31, 1966
None
Date:
June 1, 1966
Creator:
Patriarca, P.
Object Type:
Report
System:
The UNT Digital Library
HHT-7 filler strip corrosion test model: test report No. 3, hot buffer type peripheral core design
None
Date:
June 1, 1966
Creator:
Cherish, P.
Object Type:
Report
System:
The UNT Digital Library
HIGH-TEMPERATURE LIQUID-METAL TECHNOLOGY REVIEW. A Bimonthly Technical Progress Review. Volume 4, Number 3
None
Date:
June 1, 1966
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Hypervelocity particle breakup: analysis and experiment. Feasibility report
During the reentry destruction of an isotopic generator, the mechanisms of fuel form ablation must be predictable to properly assess the nuclear hazard associated with the event. Ultimate land deposition patterns and contaminant densities are directly a function of the final ablative particle size. One mechanism of fuel form ablation is the mechanical breakup of molten material by aerodynamic forces created during hypervelocity reentry. The object of this study was to determine the feasibility of describing the breakup phenomenon by statistical mechanical analytic techniques, and to determine the applicability of employing a light gas gun and a controlled environmental range to experimentally observe the breakup phenomenon. (auth)
Date:
June 1, 1966
Creator:
Osmeyer, W. E.; Olsen, T. M. & Braun, W.
Object Type:
Report
System:
The UNT Digital Library
AN IMPROVED AQUEOUS PROCESS FOR ZIRCONIUM ALLOY NUCLEAR REACTOR FUELS. PART III. CONTINUOUS DISSOLUTION IN HYDROGLUORIC ACID WITH SOLUBLE POISON
None
Date:
June 1, 1966
Creator:
Newby, B.J. & Rohde, K.L. (eds.)
Object Type:
Report
System:
The UNT Digital Library