Zr+Nb>99.5 Nb0.8-1.1 1 DEVELOPMENT OF ZR-NB ALLOYS Shenzhen Sunrise Metal Industry Co.,Ltd
The first information of the use of zirconium alloys in nuclear reactor environments
appeared with the U.S. publication of some of their development work on Zr-Sn based
alloys at the First U.N. Conference on the Peaceful Uses of Atomic Energy in Geneva
during August 1955. Although little was said during the actual conference sessions, the
simultaneous publication of “The Metallurgy of Zirconium”, Lustman & Kerze, 1955,
presented data on these alloys; and remained the “reference text” for many years.
Although it took sometime to get details of the development of the Zircaloys, Kass,
1963, Lustman and Kerze actually made no mention of the composition of the
Zircaloys!°C
The Russians had been “caught napping” by this U.S. publication of previously
classified data so, at the next U.N. Conference on the Peaceful Uses of Atomic Energy
(also in Geneva in 1958) they presented extensive results on a range of Zr-Nb alloys.
These ranged from the all α ozhennites, through the Zr-1%Nb (E110) alloy, to higher
alloys with up to 5%Nb, Figure 1-1, Ambartsumyan, et al., 1958; Ivanov &
Grigorovich, 1958 and Korobkov, et al., 1958. It was quite sometime after this before it
was evident that only the Zr-1%Nb (E110) and the Zr-2.5%Nb (E125) alloys were being
used commercially in Russian reactors, and that the ozhennites (despite their apparently
better corrosion resistance) were not being used, Table 1-1, IAEA TECDOC-996,
1998(a).
Exposure Time, hours
100
300
500
700
900
1100
1300
1500
1000 2000 3000 4000 5000 6000 7000 8000
Weight Gain (mg/dm2
)
450°C
400°C
350°C
550°2L`)4X2H.png)
C
Figure 1-1(a): Corrosion of zirconium alloy with 1% niobium in water and superheated
steam at various temperatures.
ZIRAT-9 Special Topic on Corrosion of Zr-Nb Alloys
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1.1 HISTORICAL INTRODUCTION (BRIAN COX) Website：http://www.sunriseta.com
E-Mail：sales@sunriseta.com
The first information of the use of zirconium alloys in nuclear reactor environments
appeared with the U.S. publication of some of their development work on Zr-Sn based
alloys at the First U.N. Conference on the Peaceful Uses of Atomic Energy in Geneva
during August 1955. Although little was said during the actual conference sessions, the
simultaneous publication of “The Metallurgy of Zirconium”, Lustman & Kerze, 1955,
presented data on these alloys; and remained the “reference text” for many years.
Although it took sometime to get details of the development of the Zircaloys, Kass,
1963, Lustman and Kerze actually made no mention of the composition of the
Zircaloys!°C
The Russians had been “caught napping” by this U.S. publication of previously
classified data so, at the next U.N. Conference on the Peaceful Uses of Atomic Energy
(also in Geneva in 1958) they presented extensive results on a range of Zr-Nb alloys.
These ranged from the all α ozhennites, through the Zr-1%Nb (E110) alloy, to higher
alloys with up to 5%Nb, Figure 1-1, Ambartsumyan, et al., 1958; Ivanov &
Grigorovich, 1958 and Korobkov, et al., 1958. It was quite sometime after this before it
was evident that only the Zr-1%Nb (E110) and the Zr-2.5%Nb (E125) alloys were being
used commercially in Russian reactors, and that the ozhennites (despite their apparently
better corrosion resistance) were not being used, Table 1-1, IAEA TECDOC-996,
1998(a).
Exposure Time, hours
100
300
500
700
900
1100
1300
1500
1000 2000 3000 4000 5000 6000 7000 8000
Weight Gain (mg/dm2
)
450°C
400°C
350°C
550°
CFigure 1-1(a): Corrosion of zirconium alloy with 1% niobium in water and superheated
steam at various temperatures.
Shenzhen Sunrise Metal Industry Co.,Ltd
TEL：0086-0755-27185042
Website：http://www.sunriseta.com
E-Mail：sales@sunriseta.com
Website：http://www.sunriseta.com
E-Mail：sales@sunriseta.com
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