Serial/Series Title
Country
Decade
Month
239 Matching Results
Results open in a new window/tab.
Zirconium Alloys for Steam Service: a Preliminary Study
The fabricability, elevated temperature strength, steam corrosion resistance, and hydrogen pickup of various binary, ternary, and quaternary alloys were studied experimentally.
Date:
June 24, 1960
Creator:
Klepfer, H. H.
System:
The UNT Digital Library
Fuel Cycle Program: A Boiling Water Reactor Research and Development Program - First Summary Report, March 1959-July 1960
The Fuel Cycle Development Program is a basic development program of boiling and other water reactor technology. This is the first report to the U.S. Atomic Energy Commission of activities carried out under this program. It constitutes a review of the progress from April 27, 1959 through July 31, 1960.
Date:
1960
Creator:
General Electric Company
System:
The UNT Digital Library
High Power Density Development Project (Contract Pending) Advance Requisition 474-49976 - Second Quarterly Progress Report, July-September, 1960
Development of nuclear reactor cores having high power density, long fuel life, and low fabrication costs is the objective of this program sponsored by the AEC. It will be achieved by extensive development and testing carried out in conjunction with the design, construction and operation of the Big Rock Point plant of the Consumers Power Company in Michigan. This second quarterly report describes the progress achieved from July through September 1960.
Date:
October 1, 1960
Creator:
Holland, L. K.
System:
The UNT Digital Library
Compact Control Rod Drive Study For a Boiling Water Reactor in a T7 Tanker
The reason for initiating the compact drive study for the T7 tanker was to investigate control rod drive size, location, and removal space requirement factors and select the control rod drive mechanism which would allow optimization of the over-all size of the containment vessel. Approximately twelve mechanical/hydraulic control rod drive arrangements were considered during this study.
Date:
August 8, 1960
Creator:
Biglieri, N. J.
System:
The UNT Digital Library
Prediction of Two-Phase Flow From Mixing Length Theory
It is proposed in this report to describe a new two-phase flow mixing length model. It consists of treating the two-phase system as a continuous medium and applying to it the methods and assumptions so widely accepted in single-phase turbulent flow. Because it reduces a two-phase problem to an equivalent one in single-phase flow, the proposed model can be readily used to predict the effects of flow rate, channel geometry, and channel direction in two-phase flow.
Date:
December 27, 1960
Creator:
Levy, S.
System:
The UNT Digital Library
Preliminary Hazards Summary Report For The Vallecitos Superheat Reactor
This Preliminary Hazards Summary Report has been prepared for submission to the United States Atomic Energy Commission in compliance with Part 50 of the regulations governing the licensing of production or utilization facilities, pursuant to the Atomic Energy Act of 1954, as amended, and contains the general information required by 10 CFR 50.34.
Date:
February 1, 1961
Creator:
General Electric Company
System:
The UNT Digital Library
Swaging Over Unground Pellets
This study was designed to determine how swaging stainless steel over unground pellets will affect the integrity of fuel rods, and to find maximum pellet diameter variation that can be tolerated.
Date:
January 25, 1961
Creator:
Brown, R. L.
System:
The UNT Digital Library
Some Control Rod Applications and Operating Experience in Power Reactor Environments
Information obtained in a survey of control rod applications and operating experience is reported. This survey covered the Army Nuclear Power Program, the Organic Moderated Reactor Experiment, the Yankee Atomic Power Plant, the Shippingport Pressurized Water Reactor and the Argonne Experimental Boiling Water Reactor.
Date:
December 14, 1960
Creator:
Williamson, H.E.
System:
The UNT Digital Library
Bounce III
BOUNCE III is a program which was written for the IBM-704 as part of a study of the parameters of the neutron distribution in a large thermal column. The program calculates the eigenvalues and corresponding eigenvectors of the matrix resulting from a diffusion-theory, multigroup description of the thermal neutron spectrum.
Date:
December 15, 1960
Creator:
Kerr, B. A.
System:
The UNT Digital Library
Final Report: 300 KWe Capsule Nuclear Power Plant Study
This document presents the results of investigations concerned with the conceptual design of a 300 KWe "Capsule" nuclear power plant.
Date:
December 15, 1960
Creator:
General Electric Company
System:
The UNT Digital Library
Preliminary Report: 300 KWe Capsule Nuclear Power Plant Study
This report describes progress made in the study of the feasibility of the concept, plant arrangement studies, and considerations pertaining to partial plant attendance. It is concluded that both the indirect and direct boiling cycles are feasible. The recommended reference design is the direct cycle, in a single capsule, with the turbine, generator and pumps on a single shaft.
Date:
June 30, 1960
Creator:
General Electric Company
System:
The UNT Digital Library
Calculated Scattering Kernels For Light Water at 23C, 42C, 61C, and 82C
This report contains a listing of the bound-proton kernels for neutron scattering which were calculated in conjunction with the USAEC Control Rod Materials Program.
Date:
May 27, 1962
Creator:
Kerr, B. A.
System:
The UNT Digital Library
Maritime Loop Irradiation Program Savannah I Fuel Irradiation Quarterly Progress Report: July 1, 1961-September 30, 1961
This report covers the S-I-5-B-M fuel irradiation in the GETR Maritime Loop during the first quarter of fiscal year 1962. The data are summarized in Section II.
Date:
December 21, 1961
Creator:
Danielson, D. W. & Gilbert, R. S.
System:
The UNT Digital Library
Subcooled burnout at high flows
Task II-B of the High Performance UO2 Program calls for testing a series of UO2 fuel rods in the PW loop of the GETR. The purpose of the tests is to obtain a relationship between the extent of central melting and the length of time before the fuel rod fails as a result of interaction between the fuel and the cladding.
Date:
unknown
Creator:
Janssen, E. (Engineer) & Kervinen, J. A.
System:
The UNT Digital Library
High Power Density Development Project Sixth Quarterly Progress Report: July-September 1961
During the quarter the development program was continued as scheduled. Milestones that were reached included the successful irradiation of prototype Big Rock fuel bundles in VBWR to a level above 2500 MWD/T with power densities as high as 88 kw/1. Also completed was the scheduling computer specification followed by a formal solicitation of bids through the AEC. A summary of progress by task is presented here.
Date:
1961
Creator:
Holland, L. K.
System:
The UNT Digital Library
The Half-Life and Gamma Ray Abundance of Cs-137
The nuclide Cs-137 is a fission product commonly used for measurement of uranium burnup in irradiated uranium fuel by the fission product to uranium ratio method. In the application of this method, the largest single error introduced in the measurement of burnup is the uncertainty in the half-life of Cs-137. Because of the uncertainty in this value and its importance in nuclear fuel burnup analysis, a reinvestigation was undertaken to obtain a more accurate value using the mass spectrometric method.
Date:
June 2, 1962
Creator:
Rider, B. F.; Peterson, J. P. & Ruiz, C. P.
System:
The UNT Digital Library
Economic Evaluation of Control Rod Materials and Fabrication Processes
Control rod materials, designs, and fabrication processes are compared for their relative economies. Control rod lifetime data are calculated with a simple approximation of nuclear worth depreciation. These data are used in conjunction with the estimated fabrication costs to determine the cost of using several absorber materials in a typical power reactor on a cost-per-year basis. The effect the control system has on core power density and fuel lifetime is included.
Date:
May 1962
Creator:
Williamson, H. E. & Megerth, F. H.
System:
The UNT Digital Library
Fuel Cycle Program, A Boiling Water Reactor Research and Development Program Eighth Quarterly Progress Report April 1962 - June 1962
The Fuel Cycle Program is an integrated program of investigation in the Vallecitos Boiling Water Reactor (VBWR) and other facilities to improve the technological limits of boiling water reactors in several areas. This report presents updates on tasks related to those areas.
Date:
July 10, 1962
Creator:
Hodde, J. A.
System:
The UNT Digital Library
High Power Density Development Project Ninth Quarterly Progress Report April-June 1962
Progress is reported on several tasks related to nuclear fuel development at the Consumers Power Company Big Rock Point Plant.
Date:
1962
Creator:
Holladay, R. L.
System:
The UNT Digital Library
Program For The Development of Plutonium Recycle For Use In Light Water Moderated Reactors Quarterly Report For Period April 1 - June 30, 1962
The Program fuel element has continued under irradiation in the Vallecitos Boiling Water Reactor, thermal energy group transfer cross sections for UO2 have been computed, and data have been reduced from the resonance wire activations performed last quarter. Future plans are included.
Date:
July 15, 1962
Creator:
Carver, J. G.; Morgan, W. R. & Robkin, M. A.
System:
The UNT Digital Library
Summary Safeguards Report For The Critical Experiment Facility Vallecitos Atomic Laboratory
This report contains technical specifications and supporting data for the Critical Experiment Facility, information to justify operation of the facility, procedural control to be used to ensure safe operation, changes in neutron instrumentation and safety system, an evaluation of the safety of the Facility. It also contains descriptions of the site, the facility and the Critical Assemblies, operating standards and procedures. Amendment no.18 to license application for Critical Experiment Facility is also attached.
Date:
July 1962
Creator:
General Electric Company
System:
The UNT Digital Library
Maritime Loop Irradiation Program Savannah I Fuel Irradiation Quarterly Progress Report April 1, 1962 - July 31, 1962
This report covers the S-I-5-B-M fuel irradiation in the GETR Maritime Loop during the final quarter of fiscal year 1962 plus the month of July 1962 to conclude the irradiation program. The data are summarized in Section II.
Date:
August 17, 1962
Creator:
Danielson, D. W.
System:
The UNT Digital Library
Fuel Cycle Program - A Boiling Water Reactor Research and Development Program: Seventh Quarterly Progress Report January 1962 - March 1962
The Fuel Cycle Program is an integrated program of investigation in the Vallecitos Boiling Water Reactor and other facilities to improve the technological limits of boiling water reactors in several areas. Progress is reported here.
Date:
April 30, 1962
Creator:
Hodde, J. A.
System:
The UNT Digital Library
Application of Boron Carbide Nickel Dispersion to a Prototype Control Rod
Previously reported results on the testing of small samples of boron carbide dispersed in nickel by electrolytic codeposition were adequately encouraging to lead to the development of a prototype control rod for operation in the Vallecitos Boiling Water Reactor. The operation of the control rod has been entirely satisfactory.
Date:
May 1962
Creator:
Williamson, H.E. & Alexander, A. J.
System:
The UNT Digital Library