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Nuclear design of the LLL-GA U/sub 3/Si blanket

Description: The nuclear design analysis and performance of the blanket for the Pu/sup 239/ producing standard mirror hybrid is discussed. The blanket is based on present day materials and technology. It is designed for peak power density and burnup in the uranium fuel of 500 W/cc and 3 atom percent. The blanket produces 2.0 Mg/yr of Pu-239 (net) from 400 MW fusion (D-T) and depleted uranium and has an average energy multiplication of 11.
Date: May 26, 1978
Creator: Lee, J. D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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World nuclear fuel cycle requirements 1990

Description: This analysis report presents the projected requirements for uranium concentrate and uranium enrichment services to fuel the nuclear power plants expected to be operating under three nuclear supply scenarios. Two of these scenarios, the Lower Reference and Upper Reference cases, apply to the United States, Canada, Europe, the Far East, and other countries with free market economies (FME countries). A No New Orders scenario is presented only for the United States. These nuclear supply scenarios … more
Date: October 26, 1990
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Irradiation performance of coextruded enriched uranium fuel rod PT-IP-A172-A: Final report

Description: The proposed operating conditions for fuel elements to be charged into the NPR require the fuel to be of an extended surface geometry and maintain adequate strength and corrosion resistance in 300 C water. A contract was let to Nuclear Metals Inc. to produce by co-extrusion lengths of fuel rod containing both natural and 1.6% enriched uranium of irradiation quality for fabrication into fuel elements. The fuel rods used in the irradiation test represent the first enriched uranium rods coextruded… more
Date: May 26, 1959
Creator: Claudson, T. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Yankee Core Evaluation Program Quarterly Progress Report: June-September 1962

Description: Quarterly report regarding the activities of the Yankee Core Evaluation Program, the purpose of which is to evaluate the performance of the core used in the Yankee Plant and to compare actual performance with predictions, as well as the revision of designs to address any differences between actual and predicted performance.
Date: October 26, 1962
Creator: Westinghouse Electric Corporation. Atomic Power Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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COMPARISON OF BORON AND HAFNIUM IN APPR CONTROL RODS

Description: A comparison of B and Hf for use in APPR control rods shows that it is possible to substitute Hf plate. Increased wall thickness of Hf will result in a smaller water volume, but reduction of the moderating center will not decrease the effectiveness of Hf rods. Burnup of Hf results in only small change of the initial blackness. Since neutron absorption in most of the Hf isotopes are (n, gamma ) reactions there is no heat generation in Hf rod. (W.L.H.)
Date: April 26, 1956
Creator: Johnson, W. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation Studies of Uranium-10 W/O Molybdenum Fuel Alloy

Description: Bare and zirconium-clad uranium-10 wt% molybdenum specimens were irradiated in NaK-filled capsules in the MTR. Irradiation conditions varied to include central-core temperatures ranging from 300 to over 1200 deg F, fuel burnups ranging from 0.36 to over 3.0 total at.% and fission rates in the range of 0.35 to 1.9 x 10/sup 14/ fissions/(sec)(cm/sup 3/) of alloy. Other parameters studied included the effects of heat treatment, changes in composition, different fabrication techniques, and changes … more
Date: January 26, 1961
Creator: Gates, J. E.; Murr, W. E.; Bauer, A. A. & Rough, F. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Application of Control charts and isotope correlations to spent fuel measurements at FCF.

Description: The material control and accountancy system for the Fuel Conditioning Facility (FCF) initially uses calculated values for the mass flows of irradiated EBR-II driver fuel to be processed in the electrorefiner. These calculated values are continually verified by measurements performed by the Analytical Laboratory (AL) on samples from the fuel element chopper retained for each chopper batch. Measured values include U and Pu masses, U and Pu isotopic fractions, and burnup (via La and Tc). When the … more
Date: July 26, 1999
Creator: McKnight, R. D.; Soltys, I. & Yacout, A. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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