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Mechanical, Fluid Flow, and Heat Transfer Out-Of-Pile Tests on EVESR MKI Prototype Fuel Bundle

Description: Summary: An EVESR MKI prototype fuel bundle was fully instrumented and operated intermittently for a 5-month period at the Pacific Gas and Electric Company’s Moss Landing Power Station. The vessel was operated up to 1000 psi with steam flows from 3000 to 26,600 lb/h, and steam inlet temperatures up to 825 degrees F. Data was recorded for blowout, vibration, flow distribution, heat transfer and pressure drop. The mechanical integrity of the fuel bundle, riser, and jumper system was satisfact… more
Date: February 1964
Creator: Polomik, E. E.; Fritz, J. R. & Ianni, P. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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
Partner: UNT Libraries Government Documents Department
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
Partner: UNT Libraries Government Documents Department
open access

Post-Irradiation Examination of Cored, Edge Loaded, Thoria-Urania Nuclear Fuel

Description: Three edge loaded thoria-urania nuclear fuel samples were assembled into a capsule, irradiated and examined. This irradiation was the first of a series to develop thoria-urania fuel for high heat flux, specific power and burn-up operation in a sodium graphite reactor.
Date: July 15, 1959
Creator: Slosek, T. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

High Power Density Development Project Sixth Quarterly Progress Report: July-September 1961

Description: 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.
Date: 1961
Creator: Holland, L. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Studies ot UO2-Cladding Mechanical Interactions (Short Time Irradiations in the GETR Trail Cable Facility)

Description: 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 evaluate… more
Date: October 1962
Creator: Hazel, V. E.; Lyons, M. F. & Comprelli, F. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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