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A 5 mechanical test of core support block. Preliminary report
Description:
This report contains seven different configurations of support blocks.
Date:
September 30, 1963
Creator:
Lee, D. Y.
A 23-Group Neutron Thermalization Cross Section Library
Description:
A set of 23-group neutron cross sections for use in the calculation of neutron thermalization and thermal neutron spectral effects in SNAP reactors is compiled. The sources and methods used to obtain the cross sections are described. (auth)
Date:
July 15, 1963
Creator:
Doctor, R. D. & Boling, M. A.
40-MW(e) Prototype High-Temperature Gas-Cooled Reactor Research and Development Program. Quarterly Progress Report for the Period Ending June 30, 1962
Description:
Research and development progress specifically directed toward the construction of a 40-Mw(e) prototype power plant employing a high-temperature, gas-cooled, graphitemoderated reactor known as the HTGR is reported. Irradiation of element III-B in the in-pile loop continued satisfactorily. The element has generated a total of l36.3 Mw-hr of fission heat. The gross activity in the purge stream increased slightly to about 350 mu C/cm/sup 3/. By taking larger gas samples than were previously taken,…
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Date:
October 31, 1963
100-N technical manual. Volume 2A: Systems descriptions
Description:
This report contains engineering drawings for the control room, reactor monitoring systems, and reactor control systems for the N reactor. Each console in the control room is detailed. Other systems discussed are: stack air monitoring system, charging machine control systems, and heating and ventilation control systems. A N reactor plant glossary is included.
Date:
December 31, 1963
190-H drawdown test
Description:
A discrepancy of about 1000 gpm has existed between the full-flow recorded 190, 105 and ROL flows. While past operating practices have not used the 190 or ROL flow rates for official purposes, the disquieting, though not theoretically unexplicable, differences require some quantitative resolution. On November 24, 1962, a drawdown test of the 190-H storage tanks was performed to establish the accuracy of the various flowmeters. The drawdown test of the 190 storage tanks was run at the beginning …
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Date:
January 17, 1963
Creator:
Cremer, B. R. & Bokish, K. P.
A 200-Watt Conduction-Cooled Reactor Power Supply for Space Application
Description:
The limited supply of relatively long-half-life isotopes having a reasonably high power density and the low conversion efficiencies obtainable with thermoelectric devices have so far limited the power output of isotope-fueled sources of electric power to several tens of watts. In addition, the high cost of the available isotopes results in a very large expense for isotope-fueled generators producing several hundred watts. It appears that a small, minimumweight, conduction-cooled reactor is an a…
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Date:
March 1, 1963
Creator:
MacFarlane, D. R.
250-Watt(e) Isotope-Fueled Thermionic Generator Study. Final Report.
Description:
No Description Available.
Date:
January 1, 1963
Creator:
Kortier, W. E. & Lyon, W. C.
1000 Mwe Closed Cycle Water Reactor Study
Description:
This report has two volumes, volume 1 contains the summary and detailed description of plant design, volume 2 contains a comprehensive nuclear evaluation of the reactor core.
Date:
March 1, 1963
Creator:
Westinghouse Electric Corp., Pittsburgh, Pa. Atomic Power Div.
1000 MWE Closed Cycle Water Reactor Study Volume II
Description:
This report includes the nuclear evaluation that has been conducted for the purpse of studying those problem areas which are expected to increase in severity as the core size is increased to produce 1000 MWE.
Date:
March 1, 1963
1000-Mwe Sgr and Prototype Evaluation Study. Volume 2. 200-Mwe Sgr Prototype Preliminary Design
Description:
No Description Available.
Date:
December 1, 1963
1000-Mwe Sgr and Prototype Evaluation Study. Volume I. Large Sgr Design Bases, Economics, and Development Program
Description:
No Description Available.
Date:
December 1, 1963
1000 MWe SGR Parameter Study--Core Thermal and Hydraulic Analysis
Description:
No Description Available.
Date:
November 19, 1963
Creator:
Imig, J. K.
1559/RE: A CODE TO COMPUTE RESONANCE INTEGRALS IN MIXTURES
Description:
The computer program 1559/RE is an experimental IBM-704 code in FORTRAN language for computing the resonance integrals of isotopes in mixtures in the presence of hydrogenic moderation. There may be up to four isotopes, each with no more than 75 resolved resonance levels. Doppler broadening and interference scattering are included No estimate is made of contributions from unresolved resonances. Typical running times are 30 min (with no Doppler broadening) to 90 min (with Doppler broadening) for …
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Date:
May 1, 1963
Creator:
Kelber, C.N.
A 1620 FORTRAN Programme for the Calculation of Bragg Angles for use in Powder X-Ray Diffraction Investigations
Description:
An IBM 1620 program is described that calculates the Bragg angles for cubic, hexagonal, and tetragonal crystal systems for use with powder x-ray diffraction techniques. Allowance is made for absent reflections in the case of face- and body-centered cubic and close-packed hexagonal materials.
Date:
April 1963
Creator:
Walker, D. G.
A 1620 FORTRAN Programme for the Refinement of Lattice Parameters by a Modified Least Squares Method
Description:
An I.B.M. 1620 programme is described which calculates refined lattice parameters from X-ray diffraction data according to Hess' Method. The programme may be used for cubic, hexagonal, and tetragonal systems and three systematic error functions are included. The output includes the refined parameters their stand errors, and the misfit of the data at each experimental point.
Date:
April 1963
Creator:
Walker, D. G.
630A Maritime Nuclear Steam Generator: Status Report Number 1
Description:
From foreword: The primary purpose of this document is to set forth the current status of the 630A Nuclear Steam Generator, under development for the U.S. AEC.
Date:
September 12, 1963
Creator:
General Electric Company. Nuclear Materials and Propulsion Operation.
Abscopal Effects of Localized Irradiation by Accelerator Beams
Description:
The aim of this series of experiments was to evaluate the existence of abscopal effects of irradiation. No attempt was made towards the elucidation of mechanisms. Very early in the history of radiological research it was noticed radiation produces both local and general effects involving the entire body. Gauss and Lembcke introduced the term "Roentgenkater" (radiation sickness). They ascribed these "General Effects" to the circulation of toxic substances released from cells that disintegrated f…
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Date:
February 1, 1963
Creator:
Jansen, C. R.; Bond, V. P.; Rai, K. R. & Lippincott, S. W.
Absorption-Multistage Flash Distillation Process
Description:
"The major factors which influence the cost of water production from sea water by distillation methods are (1) the cost of fuel or energy required by the distilling plant, and (2) the required capital investment. Preliminary studies on the application of absorption or solution cycles to distillation methods for saline water conversion indicated that the fuel cost or thermal economy of a distillation plant could be improved by combining the distillation process with an absorption or solution cyc…
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Date:
September 1963
Creator:
Fluor-Singmaster & Breyer, Inc.
Acceptance Test Facility Safeguards Report.
Description:
The purpose of this report is to describe the operation of the Acceptance Test Facility (ATF) and testing of SNAP 10A Auxiliary Power Units (APU) in the facility.
Date:
January 1, 1963
Creator:
Soske, P. L.; Ostenso, A. S.; Kamensky, F. J. & Berger, S.
Accurate Nuclear Fuel Burnup Analyses; Eighth Quarterly Progress Report, (September - November 1963)
Description:
The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date:
December 1, 1963
Creator:
Rider, B. F.; Ruiz, C. P.; Luke, P. S., Jr.; Peterson, J. P., Jr. & Smith, F. R.
Accurate Nuclear Fuel Burnup Analyses: Fifth Quarterly Progress Report December 1962-February 1963
Description:
Work has continued on the development of Accurate Fuel Burnup Analysis. Work performed during the fifth quarter is summarized here.
Date:
March 1, 1963
Creator:
Rider, B. F.; Ruiz, C. P. & Peterson, J. P.
Accurate Nuclear Fuel Burnup Analysis Quarterly Progress Report: Seventh Quarter, June 1963 - August 1963
Description:
Quarterly progress report on Accurate Nuclear Fuel Burnup Analysis project.
Date:
September 1, 1963
Creator:
Rider, B. F.; Ruiz, C. P.; Peterson, J. P., Jr.; Luke, P. S., Jr. & Smith, F. R.
Accurate Nuclear Fuel Burnup Analysis Quarterly Progress Report: Sixth Quarter, March 1963 - May 1963
Description:
Quarterly progress report on Accurate Nuclear Fuel Burnup Analysis project.
Date:
June 1, 1963
Creator:
Rider, B. F.; Ruiz, C. P.; Peterson, J. P., Jr. & Luke, P. S., Jr.
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Feed Materials Production Center Summary Technical Report
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Two-Phase Pressure Losses Quarterly Progress Report
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3
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ACRH Semiannual Report on Medical Research
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Accurate Nuclear Fuel Burnup Analysis Quarterly Progress Report
2
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2
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Contribution (University of Washington. College of Fisheries)
2
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Fiscal Year 1963
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IDO
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Molten-Salt Reactor Program Semiannual Progress Report
2
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Program of Two-Phase Flow Investigation Quarterly Report
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Shorter contributions to general geology
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Special scientific report--fisheries
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Specific Zirconium Alloy Design Program Quarterly Progress Report
2
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Transition Boiling Heat Transfer Program...Second Quarterly Progress Report
2
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Two-Mile Accelerator Project Quarterly Status Report
2
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Accurate Nuclear Fuel Burnup Analyses Quarterly Report
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1
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Hanford Atomic Products Operation Plutonium Recycle Test Reactor Mechanical Seal Pump Operating Experience
1
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In-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes
1
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Information circular (United States. Bureau of Mines)
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Maritime Gas-Cooled Reactor Program Quarterly Progress Report
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Mineral resources of Alaska
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1
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Radiolysis of Organic Fluids Annual Progress Report
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1
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Saline Water Conversion Demonstration Plant Number 1
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The Flora of Healthy Dogs
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Thermodynamic Properties of 65 Elements
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Thermonuclear Project Semiannual Report
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Transition Boiling Heat Transfer Program...First Quarterly Progress Report
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