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Interim report No. 1, RT 105-577-A: Irradiation of solid and cored hot pressed fuel elements

Description: In order to evaluate the performance of uranium slugs canned by the hot press method, several tubes of this metal were charged at C Pile and scheduled for irradiation until a specified number of ruptures had occurred. At the present time, all scheduled ruptures of hot-pressed slugs have been obtained. This report summarizes the irradiation experience under this test and the results obtained to the present time, and presents conclusions which are drawn from this experience.
Date: May 18, 1955
Creator: Anderson, J. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Annealing of crystal distortion in irradiated graphite

Description: From introduction: "As part of the program for improvement of graphite, the structural characteristics of graphite have been studied to determine the relation between physical and structural changes during irradiation."
Date: 1955
Creator: Austin, Alfred E. & Harrison, Ralph J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Specifications for WAPD Loop

Description: Specifications for the proposed in-pile loop to be placed in the Hanford Reactor. The the purpose of the proposed installation of an irradiation facility accounting to a high pressure, high temperature recirculating loop for the Westinghouse Atomic Power Division (WAPD) is to test the integrity of fuel specimens. This report, in support of the feasibility study, cost estimates, and schedule, presents design specifications for the loop.
Date: February 16, 1955
Creator: Berberet, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Attenuation properties of Hanford pile shield materials

Description: This report discusses an extended program of measurements has been carried out at Hanford to determine the attenuation characteristics of various concretes which might be used as inexpensive yet efficient shields for large, stationary, production piles. The original Hanford piles have biological
Date: September 1, 1955
Creator: Bunch, W. L. & Tomlinson, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Quarterly progress report, Metallurgy Research sub-section, April 1955--June 1955

Description: One uranium tensile specimen irradiated to 620 MWD/T (1.75 x 10{sup 20} nvt) was tested at 285 C (545 F). The values obtained were: ultimate tensile strength 71,000 psi, 0.1% offset yield strength 70,000 psi, percent elongation (one inch gage length) 0.7, and modulus of elasticity 12 x 10{sup 6}. These values are comparable to the as-irradiated values of specimens tested at room temperature which were: ultimate tensile strength 76,000 psi, 0.1% offset yield strength 71,500 psi, and percent elon… more
Date: August 15, 1955
Creator: Cadwell, J.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Uranium Dioxide-Stainless Steel Specimens for Irradiation in Sodium- Experiment PW-5-1

Description: The preparation, pre-irradiation testing, and encapsulation of stainless- U cored, plate-type fuel elements for irradiation in;tagnant sodium are discussed The eight specimens for Experiment PW-5-1 are examined. (auth)
Date: April 25, 1955
Creator: Calkins, G. D.; Pobereskin, M.; Keeler, J. R. & Keller, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Tube Power Limits -- Past, Present and Future

Description: During the history of operation of the Hanford reactors, several methods have been utilized to establish an outlet water temperature or ``Panellit`` limit based on the stability of water flowing through the process tubes. These methods have been known as ``Excess Header Pressure Limits,`` ``Trip Before Boiling Limits,`` and the most recent, ``Trip Before Instability Limits.`` Each new concept vas accepted only after considerable experimental data had proved the new method to be safe and operati… more
Date: May 31, 1955
Creator: Carbon, M. W. & Gilbert, W. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Effects of Reactor Irradiation of Thorium-Uranium Alloy Fuel Plates

Description: Several plates of 98.7% Th - 1.2% U 235 (clad in aluminum) were irradiated in the MTR for an integrated flux of 2.6 x 10 21 neutrons/cm2. Although these samples represent an early development in bonding of aluminum to thorium and there are better methods at present, the bond proved to be quite strong and both clad and core were dimensionally stable under irradiation. The production of uranium 233 was as much as theory would indicate and the total amount of fissionable material material after ir… more
Date: September 7, 1955
Creator: Carrell, R. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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