Search Results

open access

Program For The Development of Plutonium Recycle For Use In Light Water Moderated Reactors Program Summary and Sixth Quarterly Report, July 1 - September 30, 1962

Description: The work described in this report represents progress toward an agreement signed by the United States and the European Atomic Energy Community which provides a basis for cooperation in programs for the advancement of peaceful applications of atomic energy.
Date: October 15, 1962
Creator: Carver, J. G.; Lagache, M. P. & Morgan, W. R.
Partner: UNT Libraries Government Documents Department
open access

Power Cycling of High Power Density Fuel Specimens Clad With 10-Mil Wall Stainless Steel

Description: Three thin-wall stainless steel fuel specimens made using fabrication processes and materials similar to the Consumers Big Rock Plant research and development fuel rods were power cycled 3000 times between 500,000 and 75,000 BTU/hr-ft2 in the General Electric Test Reactor (GETR) Trail Cable facility. The fuel specimens were exposed to 1000 psi boiling water. All of the fuel specimens withstood the test without failing or without any significant changes in the clad characteristics.
Date: October 1962
Creator: Rowland, T. C. & Atkinson, J. S.
Partner: UNT Libraries Government Documents Department
open access

High Performance UO2 Program Quarterly Progress Report Number 2: July-September 1961

Description: The primary purpose of this joint USAEC-Euratom program is to obtain a better understanding if the maximum achievable operating characteristics of UO2 as a reactor fuel. During the program work will be performed in two areas that have been of concern to reactor core designers for a long time, namely fission gas release and central melting in fuel rods.
Date: October 1, 1961
Creator: Weidenbaum, B.
Partner: UNT Libraries Government Documents Department
open access

High Power Density Development Project (Contract Pending) Advance Requisition 474-49976 - Second Quarterly Progress Report, July-September, 1960

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. 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.
Partner: UNT Libraries Government Documents Department
open access

Further Experimental Results on Natural Circulation Loop Performance at 1000 psia Under Periodic Accelerations

Description: Experimental results on the effect of periodic acceleration on a natural circulation, 1000 psia, two-phase flow loop are presented, and related to the topic of marine reactor design. The initial results of this work were given previously in GEAP 3397.
Date: October 24, 1960
Creator: Quinn, E. P.
Partner: UNT Libraries Government Documents Department
open access

Collected Methods for Analysis of Sodium Metal

Description: Methods for analyzing chemical impurities in sodium metal samples are presented. Chemical analysis was used to determine the following impurities: Calcium, Carbon, Chromium, Iron, Lithium, Nickel, Oxygen, Potassium, and Zirconium. Spectrographic analysis was used to determine many other impurities. Sodium samples obtained from experimental apparatus operated as part of the work being conducted for Atomics International were analyzed by these methods.
Date: October 15, 1959
Creator: Perrine, H. E.
Partner: UNT Libraries Government Documents Department
open access

Enclosure Pressure Calculation Method

Description: A method of determining enclosure pressure in the event of a reactor rupture is presented and a sample calculation is shown. This method was used in calculating the design pressure of the Dresden Nuclear Power Station enclosure.
Date: October 6, 1956
Creator: Bailey, J. A.
Partner: UNT Libraries Government Documents Department
open access

In-Core Instrumentation Development Program Quarterly Progress Report June - September 1963

Description: Introduction: The objective of Project Agreement 22 is to determine the feasibility of covering the complete reactor neutron flux start range from 10(3) - 5 x 10(13) nv by using in-core chambers. The counting mode of operating will be used at low neutron fluxes and the root mean square voltage fluctuation mode will be used at high neutron flux levels. Experiments have been run utilizing various ion chambers, gases, gas pressures, voltage, and cables to measure sensitivities and range operating … more
Date: October 1963
Creator: DuBridge, R. A.
Partner: UNT Libraries Government Documents Department
open access

Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: July 1 - September 30, 1963

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: The densitometry procedure (for measurement of alpha autoradiographs of fuel pellets) has been modified to eliminate the need for a second emulsion. The existence of a problem of latent image fading and non-reciprocity of … more
Date: October 15, 1963
Creator: Robkin, M. A.
Partner: UNT Libraries Government Documents Department
open access

Specific Zirconium Alloy Design Program Quarterly Progress Report: Sixth Quarter, July - September, 1963

Description: Summary: Fundamental studies in support of the alloy design work are complete except for the experimental determination of the diffusion of oxygen in alloy-doped non-stoichiometric ZrO2. Over 100 oxidation runs have now been made on samples of ZrO2 doped with 1 mole percent of the oxides of Al, Y, Fe, Cr, and Ni. The first round testing of 31 alloys is now essentially complete. Analysis of the steam corrosion rate and hydriding raw data taken at 300, 400, and 500 degrees C indicates that Zr-C… more
Date: October 1, 1963
Creator: Klepfer, H. H.; Jaech, John L.; Douglass, D. L. (David Leslie), 1931-; Blood, R. E. & Perrine, H. E.
Partner: UNT Libraries Government Documents Department
open access

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Eighth Quarterly Report, July-September 1963

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program. Information is reported on vented fuel production, fuel testing in TREAT, fuel performance evaluation, fast-flux irradiation of fuel, and reactor dynamics and design.
Date: October 1963
Partner: UNT Libraries Government Documents Department
open access

Development of Pulsed Neutron Application to Power Reactor Start-Up Procedures. Sixth Quarterly Progress Report, July 1-September 30, 1963

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. The development of pulsed neutron source techniques for large power reactors has led to a new theoretical model recently developed by E. Garelis and J.L. Russell, Jr. The theory is presently based on a bare, one-group model with m-delayed precursors and takes all spatial modes into account. Results indicate, however, that the app… more
Date: October 15, 1963
Creator: Garelis, Edward & Meyer, P.
Partner: UNT Libraries Government Documents Department
open access

Development Program for Increased Output in the Garigliano Nuclear Reactor. Quarterly Report No. 4

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: October 1, 1963
Creator: Sorlie, T.
Partner: UNT Libraries Government Documents Department
open access

Transition Boiling Heat Transfer Program; Third Quarterly Progress Report, July - September 1963

Description: Summary: Initial critical heat flux, transition boiling temperature fluctuation, and film boiling coefficient data have been obtained on a two-rod cluster assembly at 1000 psia and 25 to 90 percent steam qualities. A representation showing the range of critical heat flux data is presented. Typical temperature recordings which indicate transition and film boiling behavior are shown. Fabrication of a new high pressure observational test section is nearly complete. An optical table and illuminatio… more
Date: October 1, 1963
Creator: Quinn, E. P.
Partner: UNT Libraries Government Documents Department
open access

High Power Density Development Project: Fourteenth Quarterly Progress Report, July-September 1963

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. The number of assemblies has been reduced to seven as a result of the failure of two pellet fuel assemblies. The average burnup of the group operating as of September 1 is 7500 MWD/T. (2) Task 1B-Fuel Fabrication Development. Assembly. Assembly 12S gave positiv… more
Date: October 1963
Creator: Holladay, R. L.
Partner: UNT Libraries Government Documents Department
open access

A Controlled-Environment Steam Corrosion Facility

Description: Abstract; Technical report describing a low-flow autoclave system developed for out-of-pile corrosion testing of materials in controlled environment steam up to 500 C. The system has been set up in triplicate to provide for the exposure of various zirconium alloys to steam at 300, 400, and 500 C. The oxygen and hydrogen of the steam were controlled at 25 ppm and 3 ppm, respectively, to simulate the gas conditions from radiolytic water decomposition found in a boiling water reactor. The autocla… more
Date: October 1963
Creator: Nelson, W. B.
Partner: UNT Libraries Government Documents Department
open access

Fuel Cycle Program Design and Fabrication of Special Assembly 10-L : Compacted Powder Fuel Rods Clad With 0.127-MM Wall Stainless Steel

Description: Technical report describing sixteen fuel rods clad with thin type 304 stainless steel and filled with vibratory compact powder UO2 that were fabricated and incorporated into a bundle for irradiation testing in the VBWR. The UO2 powders were tested for gas content. N2, CO, and H2 were the principal gases evolved by both type of UO2, but the arc-fused UO2 released about ten times as much gas as the Dyna Pak UO2. The amount of gas released was also a function of particle size and temperature. The… more
Date: October 1963
Creator: Ogawa, S. Y. & Williamson, N. E.
Partner: UNT Libraries Government Documents Department
open access

Prediction of Two-Phase Critical Flow Rate

Description: Technical report of a proposal of an analytical model to predict two-phase critical flow rate. The model is based upon thermal equilibrium, a "lumped" treatment of the two-phase velocity (each phase is represented by a single mean velocity), and upon the neglect of frictional and hydrostatic pressure losses. A comparison, of the proposed predictions with available test results and previous analyses shows that: (1) The present model agrees very well with the published test data. (2) In contrast … more
Date: October 1963
Creator: Levy, S.
Partner: UNT Libraries Government Documents Department
open access

Environmental Testing of a B4C-Ni Prototype Control Rod

Description: Summary: A prototype control rod containing absorber plates made from an electro- deposited dispersion of boron carbide in nickel was tested in the VBWR. It was exposed to the reactor environment of 545 degree F boiling water and thermal neutron fluxes (perturbed) which ranged from 0.6 to 1.1 x 10/sup 13/ nv for 2236 hours over a period of six months. The maximum B/sup 10/ burnup achieved during the test period was 1.8 percent. After irradiation, the rod was examined. The results of the examina… more
Date: October 15, 1963
Creator: Megerth, F. H. & Zimmerman, D. L.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen