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Subcooled burnout at high flows

Description: 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.
Item Type: Refine your search to only Report
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Design and Operating Experience of the ESADA Vallecitos Experimental Superheat Reactor (EVESR)

Description: Summary: "The various design features significant to superheat are described for the 12-1/2 MW., 960 psig, 1050° F, steam-cooled, low-enriched, annular-fueled, experimental superheat reactor built by the General Electric Company at the Vallecitos Atomic Power Laboratory. Results obtained during the first six months of full-power operation, on the emergency cooling system, core thermal performance, and pressure vessel temperatures are presented and compared with predictions. Operating experience… more
Date: February 1965
Creator: Ianni, P. W.; Fritz, J. R. & Law, D. D.
Item Type: Refine your search to only Report
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Pressure Vessel Steel Surveillance Program for General Electric Power Reactors

Description: Abstract: "Pressure vessel steel surveillance programs are performed in nuclear power reactors to provide knowledge of the mechanical properties of the pressure vessel material as neutron irradiation proceeds. A standard surveillance program is described. Design of specimens, capsules, and associated equipment, as well as selection of test material and techniques for special preparation and testing, are discussed."
Date: January 8, 1965
Creator: Brandt, F. A.
Item Type: Refine your search to only Report
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Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: April 1 - June 30, 1964

Description: A research program is being conducted to obtain experimental data in the irradiation of plutonium-enriched fuel to confirm a theoretical model for predicting isotopic composition and reactivity changes in plutonium-enriched, light-water-moderated reactors. Quarterly progress: Project fuel fins irradiated to 1860, 3000, and 5300 MWD/T have been successfully sampled in the Radioactive Materials Laboratory. The samples have been dissolved and aliquots delivered to Chemistry for Mass Spectrometry … more
Date: July 15, 1964
Creator: Robkin, M. A.
Item Type: Refine your search to only Report
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Development Program for Increased Output in the Garigliano Nuclear Reactor. Quarterly Report No. 7

Description: The United States and the European Atomic Energy Community (Euratom), on May 29, and June 18, 1958, signed an agreement which provides a basis for co-operation in programs for the advancement of the peaceful applications of atomic energy. The work described in this report represents the Joint U.S.-Euratom effort. The over-all development program is designed to obtain the test data and operating experience necessary to eventually realize a 50 percent increase in the output of the Garigliano Nucl… more
Date: July 1, 1964
Creator: Howard, C. L.
Item Type: Refine your search to only Report
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Transition Boiling Heat Transfer Program; Sixth Quarterly Progress Report, April - June 1964

Description: Summary: Transition boiling data was taken with an improved flow loop, to explore the influence of loop characteristics on rod temperature fluctuations the transition region was found to be much smaller than for comparable conditions with a different loop. Also the amplitude, and frequency of the temperature oscillations, were significantly less than before. These results indicate that loop characteristic and flow disturbance parameters play a prominent part in governing the transition tempe… more
Date: July 1, 1964
Creator: Quinn, E. P.
Item Type: Refine your search to only Report
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UO2 Pellet Thermal Conductivity From Irradiations With Central Melting

Description: Abstract: Continued irradiation experience under the AEC - Euratom, UO2 High Performance Program provided five separate and distinct sets of data on UO2 thermal conductivity. Four of these results are expressed in terms of the value of the thermal conductivity. The first two of these measurements were applicable -- strictly -- to poly crystalline UO2. Recently, three additional sets of measurements have been obtained -- all pertinent to UO2 after the formation of large columnar grains. The … more
Date: July 1964
Creator: Lyons, M. F.; Coplin, D. H.; Pashos, T. J. & Weidenbaum, B.
Item Type: Refine your search to only Report
open access

Development of Pulsed Neutron Application to Power Reactor Start-Up Procedures. Seventh and Eighth Quarterly Progress Report, October 1, 1963-March 31, 1964

Description: Activities in a program to develop techniques in the use of pulsed neutron sources to measure shutdown parameters related to large thermal power reactors are reported. In the course of this program, a new theory was suggested and an experimental apparatus was designed and built. Experiments were carried out to test the new model. This present report contains additional data and information extracted from the experiments at PG&E Humboldt Bay Power Reactor at Eureka, California. During the las… more
Date: April 24, 1964
Creator: Garelis, Edward & Meyer, P.
Item Type: Refine your search to only Report
open access

Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: January 1 - March 31, 1964

Description: A research program is being conducted to obtain experimental data in the irradiation of plutonium-enriched fuel to confirm a theoretical model for predicting isotopic composition and reactivity changes in plutonium-enriched, light-water-moderated reactors. Quarterly progress: Work has begun in the Radioactive Materials Laboratory to sample the project fuel from the pins irradiated to 1800 and 5000 MWT/T. Some delay has been experienced due to preemption of the hot cells by priority work. Exa… more
Date: April 15, 1964
Creator: Robkin, M. A.
Item Type: Refine your search to only Report
open access

Development Program for Increased Output in the Garigliano Nuclear Reactor. Quarterly Report No. 6

Description: The United States and the European Atomic Energy Community (Euratom), on May 29, and June 18, 1958, signed an agreement which provides a basis for co-operation in programs for the advancement of the peaceful applications of atomic energy. The work described in this report represents the Joint U.S.-Euratom effort. The over-all development program is designed to obtain the test data and operating experience necessary to eventually realize a 50 percent increase in the output of the Garigliano Nucl… more
Date: April 1, 1964
Creator: Howard, C. L.
Item Type: Refine your search to only Report
open access

The Effects of Non-Uniform Flow and Concentration Distributions and the Effect of the Local Relative Velocity on the Average Volumetric Concentration in Two-Phase Flow

Description: Abstract: A general expression which can be used either for predicting the average volumetric concentration or for analyzing and interpreting experimental data is derived. The analysis takes into account both the effect of non-uniform flow and concentration profiles as well as the effect of the local relative velocity between phases. The first effect is taken into account by a distribution parameter, whereas the latter is accounted for by the weighted average drift velocity.
Date: April 1964
Creator: Zuber, N. & Findlay, J. A.
Item Type: Refine your search to only Report
open access

Fabrication of fuel Cladding From Incoloy Alloy 800 : an Evaluation of Methods

Description: Summary: On the basis of its high temperature, physical and corrosion properties, Incoloy Alloy 800 was selected as a candidate for fuel cladding nuclear superheat applications. At the time of its selection, there was little information or experience with Incoloy 800 in the production of thin-walled, small diameter tubing suitable for nuclear fuel cladding. As a result, special purchasing efforts were required for the procurement of initial tubing used in fuel fabrication. As-received welde… more
Date: April 1964
Creator: Kirby, R. F.; MacMillan, D. F. & Punches, J. R.
Item Type: Refine your search to only Report
open access

High Power Density Development Project: Sixteenth Quarterly Progress Report, January-March 1964

Description: 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. Five tasks are in progress: (1) Task 1A-High Power Density Fuel Development, (2) Task 1B-Fuel Fabrication Development. Assembly, (3) Task II-Stability, Heat Transfer and Fluid Flow, (4) Task III-Physics Development, and (5) Task IV-Co-Ordination and Test Planning.
Date: April 1, 1964
Creator: Holladay, R. L.
Item Type: Refine your search to only Report
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In-Core Instrumentation Development Program Quarterly Progress Report January - March 1964

Description: The objective of Project Agreement 22 is to determine the feasibility of using in-core ion chambers to cover the complete reactor neutron flux startup range from 10(4) -5 - 10(13) nv using in-core ion chambers. This technical report discusses the following topics: low versus high cable termination impedance, amplifier considerations, noise considerations, gas and pressure selection, cable selection, effect of gamma, effect of temperature, and remaining problems.
Date: April 1964
Creator: DuBridge, R. A.
Item Type: Refine your search to only Report
open access

Transition Boiling Heat Transfer Program; Fifth Quarterly Progress Report, January - March 1964

Description: Summary: Tests with the two-rod assembly were performed with liquid film trippers attached to the unheated wall, and a variation in rod spacing. Experimental data and improved high-speed motion pictures have been obtained of transition boiling behavior. The changes of the local heat transfer process between nucleate and film boiling can be readily distinguished i the motion pictures. Observational test performed with very short fins on the heated surface resulted in essentially eliminating … more
Date: April 1, 1964
Creator: Quinn, E. P.
Item Type: Refine your search to only Report
open access

A Program of Two-Phase Flow Investigation Quarterly Report: Fourth Quarterly Report, January-March, 1964

Description: Summary: The design, construction and assembly of all components were completed during the first contract year previous to December 1963. These efforts, defined by Tasks A-F, are document in (1), (2), and (3). Brief summaries of these completed efforts are given in the introduction to each of the tasks in the text of this report. The digest given below covers only the shakedown and analysis work carried out in the fourth quarter of the first contract year. Task G Shakedown Tests. The photo… more
Date: March 16, 1964
Creator: Staub, F. W. & Zuber, N.
Item Type: Refine your search to only Report
open access

Accurate Nuclear Fuel Burnup Analyses; Ninth Quarterly Progress Report, (December 1963 - February 1964)

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: March 1, 1964
Creator: Rider, B. F.; Peterson, J. P., Jr.; Ruiz, C. P. & Smith, F. R.
Item Type: Refine your search to only Report
open access

AEC Fuel Cycle Program Design and Fabrication of Special Assembly 9-L : Irradiation Performance Test of UO2-Cermet Fuel

Description: Technical report describing a UO2-Mo cermet fuel assembly fabricated for long-term irradiation performance testing in the Vallecitos Boiling water Reactor. The design and fabrication histories of this assembly are described and pre-irradiation data on each individual rod are presented. Molybdenum was added to improve the bulk thermal conductivity of the fuel, so that fuel temperatures would remain comparatively low during high-power level operation of the fuel element. The molybdenum was inc… more
Date: March 1964
Creator: Ogawa, S. Y.
Item Type: Refine your search to only Report
open access

General Corrosion of Incoloy-800 in Simulated Superheat Reactor Environment

Description: The 300 series stainless steels had been selected originally as the reference fuel cladding material for utilization in several superheat reactor (SHR) systems being built as part of the United States Atomic Energy Commission (USAEC) program. The adequacy of the general corrosion resistance of Type-304 stainless steel for superheat fuel cladding was confirmed in the Phase I portion of the study reported previously. Fuel jacket failures that occurred in Type-304 stainless clad fuel elements exp… more
Date: March 1964
Creator: Pearl, W. L.; Brush, E. G.; Gaul, G. G. & Wozadlo, G. P.
Item Type: Refine your search to only Report
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