Serial/Series Title
States
Year
Month
Language
264 Matching Results
Results open in a new window/tab.
Power Cost Normalization Studies Civilian Power Reactor Program - 1959
Introduction: In connection with the development of a comprehensive plan for a ten year civilian power reactor program, the Evaluation and Planning Branch, Division of Reactor Development, United States Atomic Energy Commission has had a series of status reports prepared to present a comprehensive review of the technical and economic status of various nuclear power reactor concepts.
Date:
January 1960
Creator:
Sargent & Lundy
System:
The UNT Digital Library
Reconnaissance for Uranium in the Arica Area, Province of Tarapaca, Chile
Abstract: In August 1958 two geologists of the Instituto de Investigaciones Geológicas de Chile made a one-week reconnaissance for uranium of the Arica area in northern Chile.
Date:
December 1960
Creator:
C., Mario Serrano & H., Erik Klohn
System:
The UNT Digital Library
Tests on Gas Space Reflective Insulations
Introduction: In August and September of 1960 a test program was carried out by Orenda Engines Limited for Oak Ridge National Laboratory on Reflective Insulations, with the object of determining Heat Transfer data applicable to the design of such insulations in reactor loops.
Date:
November 1960
Creator:
unknown
System:
The UNT Digital Library
Evaluation and Design Heavy Water Moderated Power Reactor Plants
From foreword: This report investigates the economics and performance of alternate cycles for heavy water moderated power reactors.
Date:
June 30, 1960
Creator:
unknown
System:
The UNT Digital Library
Evaluation and Design Heavy Water Moderated Power Reactor Plants
From introduction: This report has been prepared to present the details of the heavy water cooled power reactors, including cost estimates, plant design studies, and other work directly related to the current status of D2O reactors.
Date:
April 28, 1960
Creator:
unknown
System:
The UNT Digital Library
The High Intensity Food Irradiator: Report 17
From introduction: A thorough investigation, both experimental and theoretical was carried out on plaque type radiators. Five phases of the work are reported: preliminary design analysis, experimental measurements, computational program and analytical studies, followed by a general discussion of source design principles. The results are summarized in graphs and formulae which may be applied to other design requirements.
Date:
May 1, 1960
Creator:
Curtiss-Wright Corporation
System:
The UNT Digital Library
Boiling Water Reactor Study [Part 4]: 100 Mw Boiling Water Reactor Conceptual Design
From introduction: This report sets forth the results of a study of a 100-mw dual cycle boiling water reactor, nuclear power plant.
Date:
February 1960
Creator:
Ebasco Services Incorporated
System:
The UNT Digital Library
Evaluation of Irradiated OMRE Fuel Elements First Core Loading
Abstract: Irradiated fuel elements from the Organic Moderated Reactor Experiment (OMRE) first core loading have been examined and evaluated to determine: (1) the stability of the floating plate fuel element design, (2) the stability of the stainless steel clad UO2 - stainless steel cermet core fuel plates under irradiation and exposure to the organic coolant, (3) the extent and nature of deposits on the fuel element services, and (4) the distribution of burnup in the fuel elements.
Date:
March 1, 1960
Creator:
Walter, J. H.; Leirich, J. F. & Calkins, G. D.
System:
The UNT Digital Library
Reactivity Absorbed by Xenon-135 in the SRE
Abstract: The measurement and calculation of the reactivity absorbed by Xe135 as functions of time after shutdown for the SRE are described.
Date:
January 28, 1960
Creator:
Woodruff, R. W.
System:
The UNT Digital Library
OMR Degasifier Loop Experiment
Abstract: A loop has been constructed to study the removal of water and highly volatile materials from Organic Moderated Reactor coolant by vacuum degasification. An analysis of the process was made to determine the most important parameters for study during the experimental program.
Date:
May 1, 1960
Creator:
Corporales, G. W. & Benson, P. R.
System:
The UNT Digital Library
OMRE Fuel Plate Surface Temperature Measurement
Abstract: Accurate measurement of OMRE fuel-element surface temperatures is important for evaluation of the performance of organic compound as moderator and coolant materials in nuclear reactors; a mixture of polyphenyls has been used in reactor operation to-date.
Date:
May 1, 1960
Creator:
Sudar, S.
System:
The UNT Digital Library
P-V-T Relationships of BF₃ Gas
Abstract: A generalized equation of state developed by Gouq-Jen Su and Chien-Hou Chang is used for predicting P-V-T behavior of BF3 at high gas densities.
Date:
July 30, 1960
Creator:
Smith, C. R. F.
System:
The UNT Digital Library
Plutonium: Enriched OMR Cores
Abstract: The influence of plutonium on the nuclear characteristics of organic moderated cores is studied.
Date:
May 1, 1960
Creator:
Connolly, T. J.
System:
The UNT Digital Library
Engineering Evaluation of a Mixed Alloy Fuel Element Irradiated at Elevated Temperatures in the SRE
Abstract: A fuel material evaluation was made by destructively examining a full-scale experimental fuel element, irradiated in the SRE to a maximum of 850 Mwd/MTU.
Date:
June 1, 1960
Creator:
Ballif, J. L.; Hayward, B. R. & Walter, J. W.
System:
The UNT Digital Library
Valve Stem Freeze Seal for High-Temperature Sodium
Abstract: An experimental study of valve stem freeze seals was undertaken as part of the effort to develop components for high temperature service in advanced sodium-cooled reactor systems.
Date:
July 30, 1960
Creator:
McDonald, J. S.
System:
The UNT Digital Library
Piqua Prototype Handling System
Abstract: Equipment has been developed to handle the fuel elements and control rods for the Piqua (OMR) reactor.With the handling machine, which consists of a shielded cask mounted on a gantry, a fuel element can be replaced in the core in about 27 minutes.
Date:
May 1960
Creator:
Nadler, H.
System:
The UNT Digital Library
An Advanced Sodium-Graphite Reactor Nuclear Power Plant
Abstract: This report describes an advanced sodium-cooled, graphite-moderated nuclear power plant which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency.
Date:
March 15, 1960
Creator:
Churchill, J. R. & Renard, J.
System:
The UNT Digital Library
A Multichannel Digital Recording System
Abstract: This report is a description of a 200 channel digital recording system used to record high temperature strain gage outputs and associated temperatures.
Date:
September 15, 1960
Creator:
Truitt, R. W.
System:
The UNT Digital Library
Fabrication of Yankee Core I Prototype Fuel Element
Introduction: Development of a process for manufacturing fuel elements for the Yankee reactor and fabrication and testing of a prototype assembly is reported.
Date:
May 1960
Creator:
D'Amore, M.
System:
The UNT Digital Library
Heavy Water Moderated Power Reactor Plants [Part 1]: Design Study
From preface: This report is one of a series covering a design study of heavy water moderated power reactor plants with the objective of selection and recommendation of a conceptual design for providing optimum economics with slight fuel enrichment.
Date:
February 1960
Creator:
unknown
System:
The UNT Digital Library
Civilian Power Reactor Program: Part 3, Status Report on Pressurized Water Reactors as of 1959
Introduction: The U.S. Atomic Energy Commission has undertaken a study of various reactor concepts to develop a comprehensive plan for a 10-year civilian power reactor program. This study reports the status of pressurized water reactors on a technical, economic, and operating experience basis.
Date:
1960
Creator:
U.S. Atomic Energy Commission
System:
The UNT Digital Library
Operation of an In-Reactor Loop Capsule for the Determination of "G" Values for the Production of NO₂ in N₂-O₂ Systems
Partial abstract: "The direct utilization of fission fragment recoil energy in chemical production shows outstanding promise as a significant application of atomic energy. Highly efficient use of the liberatied energy under high temperature conditions and with unusually rapid quenching is within engineering grasp. This contract has covered a measurement of the efficiency with which nitric acid can be produced by such a process under industrial plant conditions. Equipment, techniques, and instrumentation were developed and perfected which permitted an in-reactor yield measurement using fissile smoke dispersed in a 4:1 nitrogen-oxygen gas mixture at 1000 psi and 200 C" (p. iii).
Date:
April 1960
Creator:
unknown
System:
The UNT Digital Library
Relationships Between the Geologic Environment and Mortality from Congenital Malformation
Abstract: Deaths from congenital malformations as a fraction of total deaths for the period 1952-1956 were tabulated from vital statistics records of the United States. The data were tabulated by county and state and the results grouped by geologic province. The data from this preliminary study suggest that mortality incidence from malformation may be higher in those geologic provinces of the United States that contain major uranium ore deposits, uraniferous waters or helium concentrations. It is inferred that these provinces have a higher than average level of environmental radiation. Although the data do not permit conclusive statements regarding the etiology of congenital malformation in reference to the geologic environment, they are sufficiently provocative to warrant further investigation.
Date:
January 1960
Creator:
Kratchman, Jack & Grahn, Douglas
System:
The UNT Digital Library
A Compendium of Information for Use in Controlling Radiation Emergencies: Including Lecture Notes from a Training Session at Idaho Falls, Idaho, February 12-14, 1958
From introduction: This report is a summary of the lecture material in the training course held at Idaho Falls, Idaho, to familiarize members of radiological assistance teams with information helpful in the response to an unusual accident including release of radioactive materials to a populated environment.
Date:
February 1960
Creator:
Brodsky, Allen & Beard, G. Victor
System:
The UNT Digital Library