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Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Experiments concerned with the development of zirconium-base alloys having corrosion resistance and strength superior to Zircaloy-2 and/or the development of materials of equivalent corrosion resistance but exhibiting enhanced strength are presented. After 3000 hr exposure to 680 deg F water, binary zirconium alloys showed corrosion resistance superior to Zircaloy-2. Alloys considered promising and which offer the highest chance of success are based on the binary compositions Zr--1Cr, Zr--ISb, Zr--O.5Nb, and Zr--O.5Sn with small additions of Te, Ge, Cr, or Fe. Alloys containing relatively high percentages of solute elements did not exhibit satisfactory corrosion properties. Corrosion data on experimental alloys in 750 deg F steam indicate a few highly proising and initially acceptable materials, which are Zr--3Cr --lFe, Zr--3Cr-- 0.25Te, and Zr--lV--lFe. Thus far the corrosion resistance is better than Zircaloy-2 and the higher alloy content indicates enhanced elevated temperature strength. (P.C.H.).
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Experiments concerned with the development of zirconium-base alloys having corrosion resistance and strength superior to Zircaloy-2 and/or the development of materials of equivalent corrosion resistance but exhibiting enhanced strength are presented. After 3000 hr exposure to 680 deg F water, binary zirconium alloys showed corrosion resistance superior to Zircaloy-2. Alloys considered promising and which offer the highest chance of success are based on the binary compositions Zr--1Cr, Zr--ISb, Zr--O.5Nb, and Zr--O.5Sn with small additions of Te, Ge, Cr, or Fe. Alloys containing relatively high percentages of solute elements did not exhibit satisfactory corrosion properties. Corrosion data on experimental alloys in 750 deg F steam indicate a few highly proising and initially acceptable materials, which are Zr--3Cr --lFe, Zr--3Cr-- 0.25Te, and Zr--lV--lFe. Thus far the corrosion resistance is better than Zircaloy-2 and the higher alloy content indicates enhanced elevated temperature strength. (P.C.H.).
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
A number of ternary compositions were developed for service in 680 deg F water which meet the objectives of a zirconium alloy improvement program on the basis of corrosion resistance, strength, and hydrogen pickup. These are compositions based on Zr-- 1Sb, Zr-- 1Cr, Zr--0.5Nb, and Zr--0.5Sn with minor additions of Te, Ge, Cr, or Fe. In 750 deg F steam, the materials Zr--3Cr-1Fe, Zr--3Cr--0.25Te, and Zr-- 1V--1Fe are initially acceptable on the basis of corrosion resistance and strength; however, hydrogen pickup is excessive. The current work is for the study of ternary alloys which are intended to show an optimum combination of corrosion, strength, and hydrogen-pickup properties. (auth).
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
A number of zirconium ternary alloys have been developed for service in 680 deg F water which meet objectives of corrosion resistance, strength, and hydrogen pickup. Ternary alloys have been developed for service in 750 deg F steam which are superior to Zircaloy-2 regarding corrosion resistance and strength. (R.J.S.).
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Corrosion and hydrogen pickup data are available on ternary alloys in 680 deg F water for an exposure time of 4800 hr. 1n general, the longer the time to transition, the lower the post-transition corrosion rate was. Ternary zirconium alloys were exposed to 750 deg F steam for a period of 3000 hr. Weight gain and hydrogen pickup values were.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Corrosion testing data are presented for a large number of Zr alloys in 68O deg F water (1043 and 1902 hr), 750 deg F steam (329 hr), and 900 deg F steam (97 hr). These alloys include Zircaloy-2 and Zr alloyed with Nb, Sn, V, Sb, C r, Cu, Fe, Si, W, Mo, Ta, Co, Pt, Pd, Rh, As, Bi, Te, Ge, Ag, and Ni. Tensile test data are also reported for ten of these alloys at 68O deg F; these alloys are Zr alloyed with Nb, Sn, Fe, V, Cr, Mo, Sb, and Co, in addition to unalloyed Zr and Zircaloy-2. (D.L.C.).
Author: United States. Department of Commerce. Office of Technical Services Publisher: ISBN: Category : Government publications Languages : en Pages : 990
Author: United States. Department of Commerce. Office of Technical Services Publisher: ISBN: Category : Government publications Languages : en Pages : 836
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Author: United States. Department of Commerce. Office of Technical Services
Author: United States. Department of Commerce. Office of Technical Services
Author: International Atomic Energy Agency
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