Improved Zirconium Alloys Quarterly Report January 1 1962 March 31 1962

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Improved Zirconium Alloys Quarterly Report January 1 1962 March 31 1962

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Author :
language : en
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Release Date : 1962

Improved Zirconium Alloys Quarterly Report January 1 1962 March 31 1962 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1962 with categories.

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.).

Improved Zirconium Alloys Quarterly Report October 1 1962 December 31 1962

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Improved Zirconium Alloys Quarterly Report October 1 1962 December 31 1962 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1963 with categories.

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).

Improved Zirconium Alloys Quarterly Report July 1 1962 September 30 1962

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Improved Zirconium Alloys Quarterly Report July 1 1962 September 30 1962 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1962 with categories.

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.).

Improved Zirconium Alloys Quarterly Report For January 1 1961 March 31 1961

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Improved Zirconium Alloys Quarterly Report For January 1 1961 March 31 1961 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1961 with categories.

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.).

Improved Zirconium Alloys Quarterly Report April 1 1962 June 30 1962

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Improved Zirconium Alloys Quarterly Report April 1 1962 June 30 1962 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1962 with categories.

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.

Improved Zirconium Alloys Quarterly Report April 1 1963 June 30 1963

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Improved Zirconium Alloys Quarterly Report April 1 1963 June 30 1963 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1963 with categories.

The oxidation of the following zirconium alloys in water at 680 deg F is reported: Zircaloy-2, Zr--Cr-- Te, Zr-Nb-Te, Zi--Sn-Te, Zr--Sn-Ge, Zr--Sb-Ge, Zr-- Sb-Te, and Zi-Sb--Nb. The tensile properties of Zircaloy-2, ZrCr-Te, and Zr-Nb-- Te alloys at room temperature and 680 deg are given. (N.W.R.).

Improved Zirconium Alloys Quarterly Report October 1 1960 December 31 1960

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Improved Zirconium Alloys Quarterly Report October 1 1960 December 31 1960 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1961 with categories.

Corrosion studies were made on several binary and ternary zirconium alloys in 680 deg F water after 168 and 355 hr exposure. The binary compositions included zirconium with 0.25 to 3 wt.% Fe, Co, Ni, Cu, Cr, W, Mo, Ta, Te, Si, Ge, As, Bi, Pb, Pt, Pd, Rh, Ag, Au, In, or Y; 0.5 to 75 wt.% Nb; 0.5 to 20 wt.% Sn; 0.25 to 9 wt.% V; and 0.25 to 10 wt.% Sb. The ternary compositions included Zr- 25 Nb-1(Sn, Sb, Cr, V, Fe, Cu, or Pd). (B.O.G.).

Improved Zirconium Alloys Quarterly Report April 1 1961 June 30 1961

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Improved Zirconium Alloys Quarterly Report April 1 1961 June 30 1961 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1961 with categories.

Progress reported includes the selection of 15 ternary bases for further study in steam or water. About 75 compositions were prepared and are being arc- melted for fabrication into corrosion specimens. Investigations of Zr purity and heat treatment effects on corrosion are being continued. Included are data from corrosion tests on binary alloys with superheated water and steam, and a list of alloys for initial investigation based on results of corrosion screening tests. (J.H.D.).

Improved Zirconium Alloys Quarterly Report January 1 1963 March 31 1963

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language : en
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Improved Zirconium Alloys Quarterly Report January 1 1963 March 31 1963 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1963 with categories.

On the basis of 4800 hr exposure to 680 l F water, a number of ternary compositions were shown to have corrosion resistance superior to Zircaloy-2. In addition, the strength and hydrogen pickup properties of the alloys were generally improved over Zircaloy-2. The promising alloys were based on the binary materials Zr- 1Sb, Zr- 1Cr, Zr0.5Nb, and Zr-0.5Sn to which small percentages of Te, Ge, Cr, or Fe were added. At present, 680 l F water corrosion data for an exposure time of 5000 hr are available for the modified ternary alloys. Development of materials for potential service in 750 and 900 l F steam proceeded in a manner similar to that for 680 l F water application. On the basis of corrosion resistance and strength, the alloys Zr3Cr- 1Fe, Zr-3Cr- 0.25Te, and Zr- 1V- 1Fe were considered highly promising and initially acceptable. However, hydrogen pickup properties, which were about the same as Zircaloy-2, were judged as unacceptable. In an attempt to improve this characteristic as well as to further enhance corrosion resistance and strength, an additional series of ternary alloys was prepared. The compositions studied in 900 l F steam did not exhibit satisfactory corrosion resistance. (P.C.H.).

Improved Zirconium Alloys Quarterly Report July 1 1961 September 30 1961

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Author :
language : en
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Release Date : 1961

Improved Zirconium Alloys Quarterly Report July 1 1961 September 30 1961 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1961 with categories.

Corrosion data for zirconium alloys exposed to 680 deg F water for 336 hr are presented. For this exposure time, all specimens exhibited the desirable tenacious, black oxide coating. Preliminary studies were made of the transformation kinetics of Zr-30 Nb, Zr-30 Nb-1 Mo, and Zr30 Nb-3 Mo alloys. Hot rolling these ingots at 1550 deg F resulted in severe edge cracking and excessive air contamination. Nevertheless, small specimens were betaquenched from 1000 deg C and isothermally transformed at 680 and 750 deg F. Hardness versus transformation time curves did not show the relatively sharp hardness increase which signifies the beginning of beta transformation. Corrosion specimens are being prepared for investigation of the effect of zirconium purity on corrosion resistance. (M.C.G.).