Technical Report Archive & Image Library (TRAIL) - 200 Matching Results
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- Two-Phase Pressure Losses Third Quarterly Progress Report August 12-November 12, 1962
- This is the third quarterly report on the work done under Contract AT(04-30-189, Project Agreement No.27, and covers the period August 12 to November 12, 1962.
- Accurate Nuclear Fuel Burnup Analyses: Fourth Quarterly Progress Report September-November, 1962
- Work has continued on the development of accurate nuclear fuel burnup analysis. Work performed during the fourth quarter is summarized here.
- The Measurement Of Free Fission Gas Pressure In Operating Reactor Fuel Elements
- The experimental program described has had as its objective the determination of the pressure exerted by free fission gas in operating UO2-filled reactor fuel elements.
- Fabrication of Zirconium Alloys For Specific Zirconium Alloy Design Program
- The raw materials and fabrication procedures employed in preparing thirty two zirconium alloy compositions for evaluation as described in GEAP-3979 are reported. Considerations involved in the extension of reported laboratory procedures to larger scale production are discussed.
- Heavy Element Isotopic Analysis of UO2 Fuel Irradiated In The VBWR: Report #1
- The primary objective of this program is to obtain improved data on the changes in nuclear characteristics with burnup of uranium oxide fuel in a boiling water reactor.
- High Power Density Development Project Tenth Quarterly Progress Report July-September 1962
- The Big Rock Point Reactor of the Consumers Power Company went critical for the first time on September 27, 1962. Summarized here are objectives and accomplishments of the pre-operational period as well as an indication of work scope remaining.
- FORE - A Computational Program For The Analysis Of Fast Reactor Excursions
- A digital computer program, FORE, which calculates transients for a fast reactor, has been coded for the TRANSAC 2000 computer. Its purpose is to provide understanding of the dynamics of fast reactors with particular emphasis on large ceramic-fueled fast reactors. The program calculates reactor power and temperatures of fuel, coolant, clad, and structure.
- Fuel Cycle Program - A Boiling Water Reactor Research and Development Program: Ninth Quarterly Progress Report July 1962 - September 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.
- Studies ot UO2-Cladding Mechanical Interactions (Short Time Irradiations in the GETR Trail Cable Facility)
- This report is a supplement to GEAP-3759, Plastic Strain In Thin Fuel Element Cladding Due to UO2 Thermal Expansion. Cladding growth results are reported for repetitively irradiated, UO2 pellet-filled, annular capsules: for two UO2 powder-filled, annular capsules: and for six solid cylindrical pellet-filled capsules. Dimensional changes of the capsules irradiated during the entire program were analyzed, and the relationship of these results to the over-all fuel development program were evaluated.
- Two-Phase Pressure Losses Second Quarterly Progress Report May 12-August 12, 1962
- This is the second quarterly report on the work done under Contract AT(04-3)-189, Project Agreement No. 27. The results reported here have to do primarily with the loss in a rectangular (1/2" x 1-3/4") channel in the horizontal orientation, without contraction-expansion inserts.
- Accurate Nuclear Fuel Burnup Analyses: Third Quarterly Progress Report June - August, 1962
- Work has continued on the development of accurate nuclear fuel burnup analysis. Work performed by the third quarter of 1962 is summarized.
- 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
- 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.
- 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.
- Power Cycling of High Power Density Fuel Specimens Clad With 10-Mil Wall Stainless Steel
- 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.
- 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.
- 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.
- 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.
- 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.
- 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.
- 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.
- Sodium Mass Transfer: III - The Application of Liquid Ammonia as a Sodium Leaching Agent
- A technique is presented for liquid ammonia leaching of metallic sodium from corrosion coupons, filter elements, and sodium samples to reveal contaminants and impurities.
- High Power Density Development Project Seventh Quarterly Progress Report October - December 1961
- During the seventh quarter the twenty-four high power density fuel assemblies were irradiated in the VBWR to an average of about 2572 MWD/T. Also during this period the instrumental assembly tasks were completed, and the award of the contract for the Scheduling Computer was made. A summary of progress by task is presented here.
- Sodium-Cooled Reactors Program: Fast Ceramic Reactor Development Program - Second Quarterly Report, January - March 1962
- This is the second in a series of quarterly progress reports on the Fast Ceramic Reactor Development Program, an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide.
- Sodium Cooled Reactors Program: Fast Ceramic Reactor Development Program Third Quarterly Report, April - June 1962
- This is the third in a series of quarterly progress reports on the Fast Ceramic Reactor Program, an analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide.
- Maritime Loop Irradiation Program Savannah I Fuel Irradiation Quarterly Progress Report: January 1, 1962 -March 31, 1962
- This report covers the S-I-5-B-M fuel irradiation in the GETR Maritime Loop during the third quarter of fiscal year 1962. The data are summarized in Section II. Discussions on fuel performance, fuel environment (water chemistry), and loop operations are included.
- High Power Density Development Project Eighth Quarterly Progress Report January - March 1962
- During the eighth quarter the instrumented assemblies were removed from VBWR and examined for effects of the exposure to reactor conditions. Also during this period the Big Rock developmental fuel assembly design was completed and a topical report was issued. A summary of progress by task is presented here.
- 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.
- 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.
- 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.
- Design Report: Superheat Strain - Cycle Capsule
- In order to investigate the low frequency strain cycle fatigue for tubular sheath geometries an apparatus was designed and fabricated for laboratory and reactor experiments. The design of this apparatus is described herein.
- Physics Calculations for the Consumers Big Rock Point Process Computer
- The physics calculations to be performed on the Consumers On-Line Process Computer are reported. As a result of these calculations, a three-dimensional power shape is simulated, a reactivity balance is approximated, and the neutron exposure of each third of fuel bundle and control rod are accumulated. The work was reported as a part of the Consumers Research and Development Program.
- Resonance Integral Calculations for Evaluation of Doppler Coefficients: The Rapture Code
- A code (RAPTURE) was programmed for the Philco TRANSAC 2000 computer to perform calculations needed for the evaluation of Doppler Coefficients in fast reactors with degraded neuron spectra. This code computes resonance integrals, averages them over resonance parameter distributions, and computes fission and capture cross sections as a function of fuel temperature and of potential scattering cross section per absorber isotope.
- Program For the Development of Plutonium Recycle For Use in Light Water Moderated Reactors: Quarterly Report For Period January 1 - March 31, 1962
- This is a report of work completed during the period January 1, 1962, to March 31, 1962. Work was done on fuel irradiation, activation studies and UO2 scattering experiment
- Maritime Loop Irradiation Program Savannah I Fuel Irradiation Quarterly Progress Report October 1, 1961 - December 31, 1961
- This report covers the S-I-5-B-M fuel irradiation in the GETR Maritime Loop during the second quarter of fiscal year 1962. The data are summarized in Section II. Discussions on fuel performance, fuel environment (water chemistry), problems with loop operations, and the crud deposition program are included.
- Program For the Development of Plutonium Recycle For Use in Light Water Moderated Reactors: Third Quarterly Report
- This is a report of work completed during the period October 1, 1961, to December 31, 1961. The Program fuel element was completed and assembled. After extensive analysis, it was concluded that the fuel was satisfactory for use in the Program.
- Experimental Fast Ceramic Reactor Design Status Report as of October 31, 1961
- The design status of the Experimental Fast Ceramic Reactor (EFCR) is described for the period up to October 31, 1961. The primary purpose of the facility is to study the dynamic behavior of a fast ceramic reactor, including the experimental demonstration of the effectiveness of the Doppler coefficient in limiting the power excursion following a rapid insertion of reactivity.
- 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.
- 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.
- Fuel Cycle Program - A Boilng Water Reactor Research and Development Program. Fifth Quarterly Report, July 1961-September 1961
- This report summarizes progress on investigation into improving the technological limits of boiling water reactors, Vallecitos Boiling Water Reactor and other facilities.
- 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.
- Consumers Baffle Two-Phase Air-Water Flow Tests in a One-Fifth Scale Model
- Tests in a one-fifth scale clear plastic model were conducted to investigate the flow characteristics of the asymmetrical riser configuration in the Consumers Big Rock power plant.
- Maritime Loop Irradiation Program Savannah I Fuel Irradiation Quarterly Progress Report: April 1, 1961-June 30, 1961
- This report covers the S-I-5-B-M* fuel irradiation in the GETR Maritime Loop during the fourth quarter of fiscal year 1961. The data are summarized in Section II.
- Control Worth of B4C Rods
- This report considers the theoretical evaluation of a system for gaining increased control strength and increased control lifetime and presents a theoretical model which is applicable to conventional multigroup diffusion theory.
- Consumers Big Rock Point Nuclear Power Reactor Stability Analysis
- This report presents the results of an analysis which was undertaken to investigate the power stability of the Consumers Big Rock Point Nuclear Power Reactor.
- Plan For VBWR Stability Experiment
- Stability tests are to be made in the VBWR (boiling water reactor). The tests are of three types: steady state measurements, rod oscillator tests, and transient tests.
- High Performance UO2 Program Quarterly Progress Report No. 13 April-June 1964
- Work performed during the quarter is summarized by: loop operations, performance of UO2 fuel, UO2 grain growth and melting studies, fuel rod mechanism failure studies.
- High Performance UO2 Program Quarterly Progress Report No. 12 January-March 1964
- Work performed during the quarter is summarized by: direct measurement of fission gas pressure, loop operations, performance of UO2 fuel, UO2 grain growth and melting studies.
- High Performance UO2 Program Quarterly Progress Report No. 11 October-December 1963
- Work performed during the quarter is summarized by: direct measurement of fission gas pressure, loop operations, performance of UO2 fuel, UO2 grain growth and melting studies.
- High Performance UO2 Program Quarterly Progress Report No. 10 July-September 1963
- Work performed during the quarter is summarized by; direct measurement of fission gas pressure, loop operations, performance of UO2 fuel, UO2 grain growth and melting studies.
- High Performance UO2 Program Quarterly Progress Report No. 9 April-June 1963
- Work performed during the quarter is summarized by: direct measurement of fission gas pressure, loop operations, performance of UO2 fuel, UO2 grain growth and melting studies.