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Author: R. W. Bohl Publisher: ISBN: Category : Alloys Languages : en Pages : 34
Book Description
The equilibrium microstructures and the kinetics of gamma decomposition of uranium-fissium alloys containing technetium were studied and compared with the characteristics of similar alloys which did not contain technetium. The technetium concentration in the fissium was 12.5 wt.% and the uranium-fissium alloys that were examined contained from 3 to 10 wt.% fissium.
Author: R. W. Bohl Publisher: ISBN: Category : Alloys Languages : en Pages : 34
Book Description
The equilibrium microstructures and the kinetics of gamma decomposition of uranium-fissium alloys containing technetium were studied and compared with the characteristics of similar alloys which did not contain technetium. The technetium concentration in the fissium was 12.5 wt.% and the uranium-fissium alloys that were examined contained from 3 to 10 wt.% fissium.
Author: Publisher: ISBN: Category : Languages : en Pages : 2
Book Description
A recent study (Report ANL-6495) was completed in which the phase relationships and decomposition kinetics of alloys with the complete fissium analysis were measured and compared with U-Fs alloys without technetium. The presence of the Tc addition appeared to have a relatively minor influence on the U-Fs alloys. (W.D.M.).
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
The equilibrium microstructures and the kinetics of gamma decomposition of uranium-fissium alloys containing technetium were studied and compared with the characteristics of similar alloys which did not contain technetium. The technetium concentration in the fissium was 12.5 wt% and the uranium-fissium alloys that were examined contained from 3 to 10 wt% fissium. The presence of technetium did not result in the presence of any new phases; it produced only minor changes in the phase relationshipB and in the stability of the gamma- uranium solid solution. Studies of aging behavior and of the structure of slowly cooled alloys indicated that the gamma is slightly more sluggish in its transformation characteristics in the presence of technetium. On this basis, it appears that the property measurements made earlier on uranium --fissium alloys which did not contain technetium can be reliably applied to true fissium alloys. (auth).
Author: Howard Savage Publisher: ISBN: Category : Breeder reactors Languages : en Pages : 34
Book Description
The heat contents of high-purity uranium and uranium-fissium alloys containing 3, 5, and 8 wt.% fissium were measured at temperatures from 0 deg C through their fusion temperatures. The total heat content above 0 deg C was determined by drop calorimetry and quantitative differential thermal analysis.
Author: S. T. Zegler Publisher: ISBN: Category : Crystals Languages : en Pages : 56
Book Description
A study was made of the phase relations and the properties of uranium-fissium alloys which have compositions bracketing that intended for the first core loading of Experimental Breeder Reactor II. The fissium aggregate in the alloys consisted of the elements Zr, Nb, Mo, Ru, Rh, and Pd. Phase relations are shown to parallel closely those in the dominant U--Mo--Ru ternary system. The uranium gamma phase is stabilized down to 552 deg C, while the beta phase is entirely suppressed at high fissium contents. Certain crystallographic data are given and the minor phases that occur in the alloys are identified. In cast and gamma-quenched alloys the retention of the high-temperature gamma phase produced low hardness and low density. The thermal expansion behavior of the alloys is shown to be dependent upon composition and prior thermal history. Thermal conductivity data are presented for uranium and the uranium-fission alloys. The thermal conductivities of the alloys decrease with increasing fissium concentration.
Author: J. A. Horak Publisher: ISBN: Category : Alloys Languages : en Pages : 40
Book Description
A total of 35 specimens of U-Pu-fissium alloy and 2 specimens of U-10 wt% Pu-5 wt% Mo alloy were irradiated as a part of the fuel-alloy development program for fast breeder reactors at Argonne National Laboratory. Total atom burnups ranged from 1.0 to 1.8% at maximum fuel temperatures ranging from 230 to 470 deg C. Emphasis was placed on the EBR-II Core-III reference fuel material, which is an injection-cast, U-20 wt% Pu-10 wt% fissium alloy. It was found that this material begins to swell catastrophically at irradiation temperatures above 370 deg C. The ability of the fuel to resist swelling did not appear to vary appreciably with minor changes in zirconium or fissium content. Decreasing the Pu to 10 wt%, however, significantly improved the swelling behavior of the alloy. Both pour-cast and thermally cycled material and pour-cast, extruded, and thermally cycled material appeared to be more stable under irradiation than injection-cast material. Under comparable irradiation conditions, the specimens of U-20 wt% Pu- 5 wt% Mo alloy were less dimensionally stable than the U-Pu-fissium alloys investigated.
Author: National Research Council Publisher: National Academies Press ISBN: 0309130395 Category : Medical Languages : en Pages : 220
Book Description
This book is the product of a congressionally mandated study to examine the feasibility of eliminating the use of highly enriched uranium (HEU2) in reactor fuel, reactor targets, and medical isotope production facilities. The book focuses primarily on the use of HEU for the production of the medical isotope molybdenum-99 (Mo-99), whose decay product, technetium-99m3 (Tc-99m), is used in the majority of medical diagnostic imaging procedures in the United States, and secondarily on the use of HEU for research and test reactor fuel. The supply of Mo-99 in the U.S. is likely to be unreliable until newer production sources come online. The reliability of the current supply system is an important medical isotope concern; this book concludes that achieving a cost difference of less than 10 percent in facilities that will need to convert from HEU- to LEU-based Mo-99 production is much less important than is reliability of supply.
Author: R. W. Bohl
Author: R. W. Bohl
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Author: Howard Savage
Author: S. T. Zegler
Author: Helen C. Friedemann
Author: J. A. Horak
Author: National Research Council
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