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The TRIO Experiment

Description: The TRIO experiment is a test of in-situ tritium recovery and heat transfer performance of a miniaturized solid breeder blanket assembly. The assembly (capsule) was monitored for temperature and neutron flux profiles during irradiation and a sweep gas flowed through the capsule to an analytical train wherein the amounts of tritium in its various chemical forms were determined. The capsule was designed to operate at different temperatures and sweep gas conditions. At the end of the experiment the amount of tritium retained in the solid was at a concentration of less than 0.1 wppM. More than 99.9% of tritium generated during the experiment was successfully recovered. The results of the experiment showed that the tritium inventories at the beginning and at the end of the experiment follow a relationship which appears to be characteristic of intragranular diffusion.
Date: September 1984
Creator: Clemmer, Robert G.
Partner: UNT Libraries Government Documents Department

Reactor Physics Studies in the GCFR Phase-II Critical Assembly

Description: The reactor physics studies performed in the gas cooled fast reactor (GCFR) mockup on ZPR-9 are covered. This critical assembly, designated Phase II in the GCFR program, had a single zone PuO₂-UO₂ core composition and UO₂ radial and axial blankets. The assembly was built both with and without radial and axial stainless steel reflectors. The program included the following measurements: small-sample reactivity worths of reactor constituent materials (including helium); ²³⁸U Doppler effect; uranium and plutonium reaction rate distributions; thorium, uranium, and plutonium alpha and reactor kinetics. Analysis of the measurements used ENDF/B-IV nuclear data; anisotropic diffusion coefficients were used to account for neutron streaming effects. Comparison of measurements and calculations to GCFR Phase I are also made.
Date: September 1976
Creator: Pond, Robert B.
Partner: UNT Libraries Government Documents Department

Reactor Engineering Division Quarterly Report, June 1, 1949 - August 31, 1949

Description: Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date: October 7, 1949
Creator: Argonne National Laboratory. Reactor Engineering Division.
Partner: UNT Libraries Government Documents Department

EBR-II Dry Critical Experiments Experimental Program, Experimental Procedures, and Safety Considerations

Description: Report containing zero power (<1 kw) Dry Critical Experiments that were "to be conducted in the EBR-II Reactor prior to filling the Primary System with sodium coolant" (p. 7.) The two primary objectives of these experiments were to determine how well the system performed without sodium coolant and to "determine and/or verify certain operational data to permit modification or improvement of the system (neutron shield, instrumentation, etc.) prior to the introduction of sodium into the system" (p. 7.)
Date: February 1961
Creator: Koch, L. J.; Loewenstein, W. B.; Lovoff, A.; Hooker, H. H.; Monson, H. O.; Ramp, R. L. et al.
Partner: UNT Libraries Government Documents Department

Description and Proposed Operation of the Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II)

Description: Report regarding "[t]he Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II), the process equipment, and the operations to be conducted in the facility are described. The Fuel Cycle Facility is a plant for reprocessing, by pyro-metallurgical methods, the core and blanket material discharged from EBR-II. The reactor core alloy is uranium-5 percent fissium and contains about 46 wt.% Uranium-235 . The blanket material consists of uranium in which plutonium is bred. Core and blanket subassemblies contained in transfer coffins are transferred between EBR-II and the Fuel Cycle Facility, which is in an adjacent building." (p. 13)
Date: April 1963
Creator: Hesson, J. C.; Feldman, M. J. & Burris, L.
Partner: UNT Libraries Government Documents Department

The Electrical Design of the EBR-II

Description: Report that "summarizes the electrical design of the Experimental Breeder Reactor II Facility (EBR-II). It attempts to gather together and present in reasonable detail the essential features and workings of the completed design, and to present a concise overall view of the system" (p. 11).
Date: June 1966
Creator: Verber, F. & Schmidt, H. L.
Partner: UNT Libraries Government Documents Department

Reactor Development Program Progress Report: September 1966

Description: Report issued by the Argonne National Laboratory discussing progress made within the Reactor Development Program for September, 1966. The report includes highlights of the different project activities including plutonium utilization, fast breeder reactors, general reactor technology, advanced systems research, and nuclear safety. This report includes tables, illustrations, and photographs.
Date: October 26, 1966
Creator: Adams, R. M. & Glassner, A.
Partner: UNT Libraries Government Documents Department

Reactor Engineering Division Quarterly Report: December 1, 1953 Through March 30, 1954

Description: Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date: April 15, 1954
Creator: Argonne National Laboratory. Reactor Engineering Division.
Partner: UNT Libraries Government Documents Department

Idaho Division Summary Report

Description: Report issued by the Argonne National Laboratory discussing a summary of projects conducted with the Idaho Division. Descriptions of each project are presented. This report includes tables, and illustrations.
Date: 1961
Creator: Novick, Meyer & Thalgott, F. W.
Partner: UNT Libraries Government Documents Department

LMFBR Nuclear Safety Program Annual Report: July 1, 1969, to June 30, 1970

Description: Report issued by the Argonne National Laboratory discussing the Liquid Metal Fast Breeder Reactor Nuclear Safety Program. The work completed by the program between 1969 and 1970 is presented. This report includes tables, illustrations, and photographs.
Date: July 1971
Creator: Simmons, W. R. & Marchaterre, J. F.
Partner: UNT Libraries Government Documents Department

Survey and Status Report on Application of Acoustic-Boiling-Detection Techniques to Liquid-Metal-Cooled Reactors

Description: Report issued by the Argonne National Laboratory discussing acoustic-boiling-detection techniques. As stated in the abstract, "this report summarizes literature through June 1967 concerning acoustic methods. In the acoustic method for boiling detection, either acoustic waveguides or high-temperature acoustic sensors are recommended" (p. 1). This report includes tables, and illustrations.
Date: April 1970
Creator: Anderson, T. T.; Mulcahey, T. P. & Hsu, C.
Partner: UNT Libraries Government Documents Department

Calculated Burnups and Fluences for Experimental Fuel Elements Irradiated in EBR-II Runs 5-55B

Description: A procedure is described for calculation of burnups and fluences at any point in a subassembly in EBR-II runs 5-55B. The calculations are performed by the BRN program package and require data generated for any element in the highly inhomogeneous fueled experimental subassemblies is the most important application of the pointwise capability. Tables allow calculation of burnup and fluences for any element in such a subassembly.
Date: October 1976
Creator: Kucera, D. A. & Meneghetti, D.
Partner: UNT Libraries Government Documents Department

First Mechanized In-Service Inspection EBR-II Steam Generator

Description: A mechanized ultrasonic test system was developed and built at Southwest Research Institute (SwRI) to conduct the first in-service inspection of the 2.25 Cr- 1 Mo steel duplex tubing in the EBR-II steam-generator system. This inspection required tube inspection from the bore side, complete volumetric examination, wall-thickness measurement, and evaluation of the braze condition. The test equipment was thoroughly checked and routinely calibrated, using a standard containing artificial flaws. Artificial flaws as small as 1.6 mm long by 0.23 mm deep were readily detected.
Date: September 1977
Creator: Longua, K. J.; Whitham, G. K. & Reimann, K. J.
Partner: UNT Libraries Government Documents Department

The Dynamic Response of Cracked Hexagonal Subassembly Ducts

Description: This report examines the dynamic elastic response of flawed and unflawed reactor subassembly ducts. A plane- strain finite-element analysis is presented for hexagonal ducts containing either internal corner cracks or external midflat cracks. Two geometric loading conditions are considered: uniform internal pressurization and point loads applied at opposite midflats. The time dependence of these loads was chosen as a Heaviside step function for the worst-case situation and as a triangular pulse to simulate the more likely condition.
Date: April 1979
Creator: Glazik, J. L. & Petroski, H. J.
Partner: UNT Libraries Government Documents Department

Postirradiation Examinations of Fuel Pins from the GCFR F-1 Series of Mixed-Oxide Fuel Pins at 5. 5 at. % Burnup

Description: Postirradiation examinations were performed on five fuel pins from the Gas-Cooled Fast-Breeder Reactor F-1 experiment irradiated in EBR-II to a peak burnup of approximately 5.5 at. %. These encapsulated fuel pins were irradiated at peak-power linear ratings from approximately 13 to 15 kW/ft and peak cladding inside diameter temperatures from approximately 625 to 760°C. The maximum diametral change that occurred during irradiation was 0.2% .delta.D/D₀. The maximum fuel-cladding chemical interaction depth was 2.6 mils in fuel pin G-1 and 1 mil or less in the other three pins examined destructively. Significant migration of the volatile fission products occurred axially to the fuel-blanket interfaces. The postirradiation examination data indicate that fuel melted at the inner surface of the annular fuel pellets in the two highest power rating fuel pins, but little axial movement of fuel occurred.
Date: May 1978
Creator: Johnson, C. E. & Strain, R. V.
Partner: UNT Libraries Government Documents Department

Computerized Operating Procedures for Shearing and Dissolution of Segments from LWBR (Light Water Breeder Reactor) Fuel Rods

Description: This report presents two detailed computerized operating procedures developed to assist and control the shearing and dissolution of irradiated fuel rods. The procedures were employed in the destructive analysis of end-of-life fuel rods from the Light Water Breeder Reactor (LWBR) that was designed by the Westinghouse Electric Corporation Bettis Atomic Power Laboratory. Seventeen entire fuel rods from the end-of-life core of the LWBR were sheared into 169 precisely characterized segments, and more than 150 of these segments were dissolved during execution of the LWBR Proof-of-Breeding (LWBR-POB) Analytical Support Project at Argonne National Laboratory. The procedures illustrate our approaches to process monitoring, data reduction, and quality assurance during the LWBR-POB work.
Date: May 1987
Creator: Osudar, J.; Deeken, P. G.; Graczyk, D. G.; Fagan, J. E.; Martino, F. J.; Parks, J. E. et al.
Partner: UNT Libraries Government Documents Department

Investigations of Materials Compatibility Relevant to the EBR-II System: Fiscal Year 1976

Description: Annual report on investigations of components of the EBR-II reactor plant and on out-of-reactor experiments in which materials or techniques are tested before they are used in the EBR-II reactor system. It includes a discussion of wide ranges of materials, circumstances, and evaluation techniques.
Date: January 1977
Creator: Longua, K. J.; Ruther, W. E.; Shields, J. A. & Clark, A. F.
Partner: UNT Libraries Government Documents Department