Zirconium-based alloy for components in nuclear reactors

Abstract: Zirconium-based alloy for components in nuclear reactors with excellent resistance both to corrosion by water and water steam and to hydrogen absorption under operating conditions consists of 1.0-2.0 percent by weight tin, 0.07-0.70 percent by weight iron, 0.05-0.15 percent by weight chromium, 0.16-0.40 percent by weight nickel, 0.015-0.30, preferably 0.015-0.20 percent by weight niobium, 0.002-0.05, preferably 0.015-0.05 percent by weight silicon, 0.09-0.20, preferably 0.09-0.16 percent by weight oxygen, the balance being zirconium and impurities, normally occurring in reactor grade sponge zirconium, of other kind than the above-mentioned substances.

Description: Zirconium-based alloys have been used for a long time in components for nuclear reactors both of boiling-water type and of pressurized-water type because of the low absorption cross-section of the zirconium for neutrons and the good corrosion resistance to water and water steam under the operating conditions prevailing in the reactor core. The alloys which are most used are zirconium-tin alloys, especially the zirconium-based alloys known under the trade names Zircaloy 2 and Zircaloy 4, the contents of alloying materials of which are within the limits 1.2-1.7 percent by weight for tin, 0.07-0.24 percent by weight for iron, 0.05-0.15 percent by weight for chromium, 0-0.08 percent by weight for nickel, 0.09-0.16 percent by weight for oxygen, the balance being zirconium and impurities normally occurring in reactor grade sponge zirconium. Zircaloy 2 contains 1.2-1.7 percent by weight tin, 0.07-0.20 percent by weight iron, 0.05-0.15 percent by weight chromium, 0.03-0.08 percent by weight nickel and 0.09-0.16 percent by weight oxygen. Zircaloy 4 contains 1.2-1.7 percent by weight tin, 0.18-0.24 percent by weight iron, 0.07-0.13 percent by weight chromium and 0.09-0.16 percent by weight oxygen. The impurities occurring in reactor grade sponge zirconium consist of the following substances in the contents stated: aluminium 75 ppm or less, boron 0.4 ppm or less, cadmium 0.4 ppm or less, carbon 270 ppm or less, chromium 200 ppm or less, cobalt 20 ppm or less, copper 50 ppm or less, hafnium 100 ppm or less, hydrogen 25 ppm or less, iron 1500 ppm or less, magnesium 20 ppm or less, manganese 50 ppm or less, molybdenum 50 ppm or less, nickel 70 ppm or less, niobium 100 ppm or less, nitrogen 80 ppm or less, oxygen 200-1200 ppm, silicon 120 ppm or less, tin 50 ppm or less, tungsten 100 ppm or less, titanium 50 ppm or less, and uranium 3.5 ppm or less. Of the above-mentioned alloys, above all Zircaloy 2 has become extensively used because of its good resistance to corrosion by water and water steam. Zircaloy 2 is thus a conventional and well-tested material which fulfills the existing specifications for the applications in questions. Zircaloy 4 does not possess the same good resistance to corrosion by water and water steam as Zircaloy 2 but has a greater resistance to hydrogen absorption during operation of the reactor. Hydrogen absorption leads to embrittlement of the material. The invention aims at providing a zirconium-based alloy for components in nuclear reactors which exhibits both excellent resistance to corrosion by water and water steam and excellent resistance to hydrogen absorption under operating conditions. To achieve this aim the invention suggests a zirconium-based alloy for components in nuclear reactors according to the introductory part of claim 1, which is characterized by the features of the characterizing part of claim 1. The content of silicon preferably amounts to 0.015-0.05 percent by weight, the content of niobium preferably to 0.015-0.20 percent by weight, and the content of oxygen preferably 0.09-0.16 percent by weight. Further developments of the invention are characterized by the features of the additional claims. The alloy according to the invention exhibits a combination of resistance to corrosion by water and water steam and of resistance to hydrogen absorption, which is better than in previously known zirconium-based alloys. According to the invention, this result is obtained by causing zirconium-based alloys, which otherwise have the same composition as or a similar composition to Zircaloy 2 or Zircaloy 4, to simultaneously contain higher, definite contents of nickel and niobium and, in certain embodiments, also of silicon and of oxygen. According to an especially preferred embodiment of the invention the zirconium-based alloy contains 1.2-1.7 percent by weight tin, 0.07-0.20 percent by weight iron, 0.05-0.15 percent by weight chromium, 0.16-0.40 percent by weight nickel, 0.015-0.30, preferably 0.015-0.20 percent by weight niobium, 0.002-0.05, preferably 0.015-0.05 percent by weight silicon, 0.09-0.20, preferably 0.09-0.16 percent by weight oxygen, the balance being zirconium and impurities, normally occurring in reactor grade sponge zirconium, of other kind than the substances mentioned above. This alloy deviates from Zircaloy 2 only in that the nickel, niobium and possibly silicon and oxygen contents are higher. According to another preferred embodiment of the invention the zirconium-based alloy contains 1.2-1.7 percent by weight tin, 0.18-0.24 percent by weight iron, 0.07-0.13 percent by weight chromium, 0.16-0.40 percent by weight nickel, 0.015-0.30, preferably 0.015-0.20 percent by weight niobium, 0.002-0.05, preferably 0.015-0.05 percent by weight silicon, 0.09-0.20, preferably 0.09-0.16 percent by weight oxygen, the balance being zirconium and impurities, normally occurring in reactor grade sponge zirconium, of other kind than the substances mentioned above. This alloy deviates from Zircaloy 4 only in that the nickel, niobium and possibly silicon and oxygen contents are higher. The alloys according to the invention are excellently suited as material in, among other things, cladding tubes for radioactive fuel, as well as for such cladding tubes filled with water, in sheets for channels for fuel assemblies for boiling-water reactors and in spacers between cladding tubes in fuel assemblies. The alloys offer particularly great advantages as material in the spacers, especially because of its good resistance to hydrogen absorption. The alloys can be manufactured in conventional manner by enclosing the necessary quantities of the alloying materials, while maintaining a vacuum, in a cavity in a briquette of sponge zirconium, which in the form of an electrode is then melted repeatedly in vacuum in an arc furnace before being cast into an ingot. The ingot is then subjected to machining or other forms of shaping of conventional kind, such as extrusion, rolling operations and heat treatments for the manufacture of the desired components for nuclear reactors. The invention will be illustrated more closely by exemplifying compositions of alloys according to the invention. Such exemplification has been done in the table below. The substances which are not named in the table consist for each one of the alloys of zirconium and of impurities, normally occurring in reactor grade sponge zirconium, of other kinds than the substances stated for the alloys in the table. Contents in percentage by weight of the respective alloying material: Sn Fe Cr Ni Nb Si O Ex 1 1.2-1.7 0.07-0.20 0.05-0.15 0.17-0.40 0.015-0.20 0.015-0.05 0.09-0.16 Ex 2 1.2-1.7 0.18-0.24 0.07-0.13 0.17-0.40 0.015-0.20 0.015-0.05 0.09-0.16 Ex 3 1.5 0.20 0.10 0.17 0.02 0.025 0.12 Ex 4 2.0 0.30 0.10 0.20 0.10 0.025 0.12 Ex 5 1.0 0.30 0.10 0.20 0.10 0.025 0.12 Ex 6 1.5 0.35 0.10 0.30 0.05 0.04 0.12 Ex 7 1.5 0.40 0.10 0.30 0.20 0.015 0.12 Ex 8 1,5 0,20 0,10 0,17 0,02 0,015 0,15 Ex 9 1,2 0,25 0,10 0,20 0,10 0,035 0,16 Ex10 1,0 0,35 0,10 0,25 0,20 0,045 0,15 Ex11 2,0 0,30 0,10 0,20 0,10 0,025 0,18

Claims: Zirconium-based alloy for components in nuclear reactors, characterized in that it contains 1.0-2.0 percent by weight tin, 0.07-0.70 percent by weight iron, 0.05-0.15 percent by weight chromium, 0.16-0.40 percent by weight nickel, 0.015-0.30 percent by weight niobium, 0.002-0.05 percent by weight silicon, 0.09-0.20 percent by weight oxygen, the balance being zirconium and impurities, normally occurring in reactor grade sponge zirconium, of other kind than the above-mentioned substances. Zirconium-based alloy for components in nuclear reactors according to claim 1, characterized in that it contains 1.2-1.7 percent by weight tin, 0.07-0.20 percent by weight iron, 0.05-0.15 percent by weight chromium, 0.16-0.40 percent by weight nickel, 0.015-0.30 percent by weight niobium, 0.002-0.05 percent by weight silicon, 0.09-0.20 percent by weight oxygen, the balance being zirconium and impurities, normally occurring in reactor grade sponge zirconium, of other kind than the above-mentioned substances. Zirconium-based alloy for components in nuclear reactors according to claim 1, characterized in that it contains 1.2-1.7 percent by weight tin, 0.18-0.24 percent by weight iron, 0.07-0.13 percent by weight chromium, 0.16-0.40 percent by weight nickel, 0.015-0.30 percent by weight niobium, 0.002-0.05 percent by weight silicon, 0.09-0.20 percent by weight oxygen, the balance being zirconium and impurities, normally occurring in reactor grade sponge zirconium, of other kind than the above-mentioned substances. Zirconium-based alloy for components in nuclear reactors according to any of the preceding claims, characterized in that it contains 0.015-0.05 percent by weight silicon. Zirconium-based alloy for components in nuclear reactors according to any of the preceding claims, characterized in that it contains 0.015-0.20 percent by weight niobium. Zirconium-based alloy for components in nuclear reactors according to any of the preceding claims, characterized in that it contains 0.09-0.16 percent by weight oxygen.

Inventors: RUDLING PETER, RUDLING, PETER
Applicants: ASEA ATOM AB, ABB ATOM AB
Application year: 1992
Main classification: C22C16
IPC codes: G21C3, C22C16