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SIGMA PLUG WELDING OF SPUN-OVER FUEL CANS

Description: Efforts made to employ the sigma welding process for plug welding Closures in spun-over fuel cans were unsuccessful. No combination of welding conditions was found which would produce satisfactory, leak-tight, plug welds in aluminum. (auth)
Date: December 1, 1952
Creator: Winsor, F.J.
Partner: UNT Libraries Government Documents Department

METALLOGRAPHIC TECHNIQUES FOR BOND STUDY OF ALUMINUM-CLAD NICKEL-PLATED URANIUM FUEL ELEMENTS

Description: Various metallographic techniques were employed to determine the best method for the preparation of Al-clad, Ni-plated U fuel elements for bond studies. The quality of the final results and the speed of the preparation were the most important factors to be considered. The procedure presented was found to yield the most advantageous results in the minimum amount of time. (W.L.H.)
Date: March 27, 1957
Creator: Woods, H.W.
Partner: UNT Libraries Government Documents Department

ELECTRON BEAM WELDING OF NUCLEAR FUEL CLADDING COMPONENTS

Description: The rapid technological development of the nuclear and space industries has placed a great demand on metal joining processes. One of the most promising processes is electron beam welding. Welding with the electron beam ofiers high integrity in addition to the ability to fabricate unusual configurations. Advanced nuclear fuels require both reliability and unusual designs for satisfactory operation under extreme conditions of temperature and stress. To investigate the problems and techniques involved in fabricating large, advanced nuclear fuel components from Zircaloy-2 material, several cladding pieces were designed and built using the electron beam process. These designs included five basic joint types for assembling the cladding. Destructive and nondestructive examinations were employed including corrosion testing and extensive metallographic examination. Weldment size, fit-up'' of the parts to be joined, fixturing and work carriage mechanisms, as they pertain to electron beam welding, are also discussed. The electron beam process has been demonstrated as a very satisfactory method for fabricating unusual fuel cladding. Fuel cladding components with lengths up to 8 ft have been fabricated for in-reactor irradiation. (auth)
Date: October 1, 1963
Creator: Klein, R.F.
Partner: UNT Libraries Government Documents Department

Surface Modification of Fuel Cladding Materials with Integral Fuel BUrnable Absorber Boron

Description: Integral fuel burnable absorgers (IFBA) are added to some rods in the fuel assembly to counteract excessive reactivity. These IFBA elements (usually boron or gadolinium) are presently incorporated in the U)2 pellets either by mixing in the pellets or as coatings on the pellet surface. In either case, the incorporation of ifba into the fuel has to be performed in a nuclear-regulated facility that is physically separated from the main plant. These operations tend to be costly and can add from 20 to 30% to the manufacturing cost of the fuel. The goal of this NEER research project was to develop an alternative approach that involves incorporation of IFBA element boron at the surface of the fuel cladding material.
Date: November 3, 2008
Creator: Sridharan, Dr. Kumar; Allen, Dr. Todd; Gudmundson, Jesse & Maier, Benjamin
Partner: UNT Libraries Government Documents Department

EFFECT ON POWER COST OF SUBSTITUTING ALUMINUM FOR ZIRCONIUM FUEL CLADDING IN A BOILING WATER REACTOR

Description: The substitution of Al-clad for Zr-clad fuel necessitates reducing the operating temperature. The amount of saving that must be made in fabrication and chemical reprocessing to overcome the cost of operating at reduced thermal efficiency is estimated for a boiling water reactor. (auth)
Date: July 24, 1958
Creator: Albrecht, W.L.
Partner: UNT Libraries Government Documents Department

POWER REACTOR FUEL REPROCESSING: MECHANICAL PHASE

Description: An occurrence at the SRE which caused approximately 7 fuel elements to part when being pulled from the reactor complicated reprocessing, however the bulk of the elements may still be reprocessed as planned. New or reworked pants for the mechanical decladder were supplied by the fabricators for rebuilding in ORNL shops. Administrative actions dictated by budgetary considerations include reduction of UO/sub 2/ pellet order to the quantity needed this fiscal year, reduction of Mark III prototype fuel element to 12, stoppage of all work by REE Division personnel, and stoppage of all work not related to SRE fuel element reprocessing. (auth)
Date: September 1, 1959
Creator: Klima, B.B.
Partner: UNT Libraries Government Documents Department

EVALUATION OF LOW IMPURITY CORE MATERIAL IN THE SM-2

Description: The worth of reduced cobalt and tantalum impurity concentrations of AlSl Type 347 stainless steel in the SM-2 core cladding and structural material was evaluated on the basis of material costs involved and accessibility for maintenance. (auth)
Date: August 14, 1959
Creator: Pancer, G.P. & Zegger, J.L.
Partner: UNT Libraries Government Documents Department

Seam-Welded Tubular Fuel Elements for Use in CP-5

Description: ALPR fuel plates were converted into tubular fuel elements for use as additional fuel for the CP-5 reactor. fabrication was carried out by introducing a cross-roll step in the ALPR rolling schedule and roll-forming tubes from these plates. (D.L.C.)
Date: May 1, 1961
Creator: Hymes, L. C.
Partner: UNT Libraries Government Documents Department

Zirflex Dissolution of the Annular Cladding of Simulated Power Fuel Elements

Description: A study was conducted to compare the estimated dissolution rate of Zircaloy-2 clad annular fuel elements on the fully expesed metal with that in the annuli. Results indicate that decladding of these elements should proceed uniformly on all surfaces. Heat balance data from the study are also reported. (J.R.D.)
Date: December 1, 1959
Creator: Smith, P. W.
Partner: UNT Libraries Government Documents Department

Na{sup 24} ACTIVITY IN THE HFIR PRIMARY COOLANT WATER

Description: Sodium-24, produced by the Al (n, alpha )Na/sup 24/ reaction, has been found in the coolant of reactors using aluminum-clad fuel elements. Methods of calculating the activity due to scdium-24 are outlined. This activity was calculated to be normally 1.4 x 10/sup 5/ to 6 x 10/sup 5/ disintegrations per min per ml. The Na/sup 24/ isotope disintegrates with 2.76- snd 1.38-Mev gammas. (B. O. G.)
Date: June 1, 1960
Creator: McLain, H A
Partner: UNT Libraries Government Documents Department

Aluminum Corrosion and Turbidity

Description: Aluminum corrosion and turbidity formation in reactors correlate with fuel sheath temperature. To further substantiate this correlation, discharged fuel elements from R-3, P-2 and K-2 cycles were examined for extent of corrosion and evidence of breaking off of the oxide film. This report discusses this study.
Date: March 10, 2003
Creator: Longtin, F.B.
Partner: UNT Libraries Government Documents Department