U.S. patent application number 10/728237 was filed with the patent office on 2004-06-24 for alloy and tube for nuclear fuel assembly and method for making same.
Invention is credited to Charquet, Daniel, Mardon, Jean-Paul, Senevat, Jean.
Application Number | 20040118491 10/728237 |
Document ID | / |
Family ID | 32598919 |
Filed Date | 2004-06-24 |
United States Patent
Application |
20040118491 |
Kind Code |
A1 |
Mardon, Jean-Paul ; et
al. |
June 24, 2004 |
Alloy and tube for nuclear fuel assembly and method for making
same
Abstract
The invention concerns a method for making tubes designed for a
nuclear fuel pencil case or guide tube which consists in forming a
bar in a zirconium based alloy containing equally 0.3 to 0.25 wt. %
of the total iron, of chromium or vanadium, 0.8 to 1.3 wt. % of
niobium, less than 2000 ppm of tin, 500 to 2000 ppm of oxygen, less
than 100 ppm of carbon, 5 to 30 ppm of sulphur and less than 50 ppm
of silicon. The bar is soaked in water after being heated at a
temperature between 1000.degree. C. and 1200.degree. C. A blank is
spun after being heated at a temperature between 600.degree. C. and
800.degree. C. The blank is cold-rolled, in at least three of four
passes, to obtain a tube with intermediate heat treatments between
560.degree. C. and 620.degree. C. and s final heat treatment is
carried out between 560.degree. C. and 620.degree. C. in inert
atmosphere or under vacuum.
Inventors: |
Mardon, Jean-Paul; (Caluire,
FR) ; Senevat, Jean; (Annecy, FR) ; Charquet,
Daniel; (Ugine Cedex, FR) |
Correspondence
Address: |
Richard Wiener
Pollock, Vande Sande & Priddy, R.L.L.P.
P.O. Box 19088
Washington
DC
20036-3425
US
|
Family ID: |
32598919 |
Appl. No.: |
10/728237 |
Filed: |
December 3, 2003 |
Related U.S. Patent Documents
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Application
Number |
Filing Date |
Patent Number |
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10728237 |
Dec 3, 2003 |
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09647339 |
Nov 27, 2000 |
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09647339 |
Nov 27, 2000 |
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PCT/FR99/00737 |
Mar 30, 1999 |
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Current U.S.
Class: |
148/668 ;
148/672 |
Current CPC
Class: |
Y02E 30/40 20130101;
G21C 3/07 20130101; Y02E 30/30 20130101 |
Class at
Publication: |
148/668 ;
148/672 |
International
Class: |
C22F 001/18 |
Foreign Application Data
Date |
Code |
Application Number |
Mar 31, 1998 |
FR |
9803970 |
Claims
1. Zirconium based alloy also containing, by weight, 0.03 to 0.25%
in total firstly of iron and secondly at least one of the elements
from the group comprising chromium and vanadium, 0.8% to 1.3% by
weight of niobium, less than 2000 ppm of tin, 500 to 2000 ppm of
oxygen, less than 100 ppm of carbon, 5 to 35 ppm of sulfur and less
than 50 ppm of silicon.
2. Sheathing tube for a nuclear fuel rod or guide tube for a
nuclear fuel assembly, made from a zirconium based alloy also
containing, by weight, 0.03 to 0.25% in total firstly of iron and
secondly at least one of the elements from the group comprising
chromium and vanadium, 0.8% to 1.3% by weight of niobium, less than
2000 ppm of tin, 500 to 2000 ppm of oxygen, less than 100 ppm of
carbon, 5 to 35 ppm of sulfur and less than 50 ppm of silicon, in
the re-crystallized state, at least the greater part of the iron
being in the form Zr(Nb,Fe,Cr).sub.2 or Zr(Nb,Fe,V).sub.2 and in
which the intermetallic compounds are of a size not exceeding 200
nm.
3. Tube as claimed in claim 2, characterized in that the oxygen
content is between 1000 and 1600 ppm.
4. Tube as claimed in claim 2 or 3, characterized in that the
content of tin is less than 300 ppm.
5. Tube as claimed in claim 2 or 3, characterized in that the
content of tin is between 300 and 1500 ppm.
6. Sheet of alloy as claimed in claim 1.
7. Method of manufacturing tubes intended for making all or the
external part of a sheathing tube for a nuclear fuel rod or a guide
tube for a nuclear fuel assembly, characterized in that a bar is
formed of a zirconium based alloy which also contains, firstly 0.03
to 0.25% in total firstly of iron, secondly, at least one of the
elements from the group comprising chromium and vanadium, 0.8 to
1.3% of niobium, less than 2000 ppm of tin, 500 to 2000 ppm of
oxygen, less than 100 ppm of carbon, 5 to 35 ppm of sulfur and less
than 50 ppm of silicon, quenching the bar in water after heating to
between 1000.degree. and 1200.degree. C., extruding a blank after
heating to a temperature of between 600.degree. C. and 800.degree.
C., cold-rolling said blank in at least four passes to obtain a
tube, with intermediate heat treatments between 560.degree. C. and
620.degree. C., and applying a final heat treatment at between
560.degree. C. and 620.degree. C., all the heat treatments being
applied in an inert atmosphere or under vacuum.
8. Method as claimed in claim 7, characterized in that the alloy
contains at most 0.20% of iron.
9. Method as claimed in claim 7, characterized in that the
Fe/(Cr+V) ratio is between 0.5 and 30 by weight.
10. Method as claimed in claim 7, characterized in that the
Fe/(Cr+V) ratio is at least 0.5 and the content of Fe+Cr+V is at
least 0.03%.
11. Method as claimed in any one of claims 7 to 10, characterized
in that the oxygen content is between 1000 and 1600 ppm.
Description
[0001] The present invention relates to tubes made from an alloy
with a zirconium base intended for making all or the external part
of the sheath of a nuclear fuel rod or a guide tube as well as the
alloys used to make such tubes. One important although not
exclusive application is the manufacture of sheathing tubes for
fuel rods designed for those of light water reactors and in
particular pressurized water reactors in which the risks of
corrosion are particularly high due to a high lithium content
and/or risks of boiling.
[0002] A method of manufacturing tubes enabling a high resistance
to corrosion and a satisfactory capacity to withstand creep has
already been proposed (FR A-2 729 000 or EP 720 177), starting with
an ingot of a zirconium based alloy which also contains 50 to 250
ppm of iron, 0.8 to 1.3% by weight of niobium, less than 1600 ppm
of oxygen, less than 200 ppm of carbon and less than 120 ppm of
silicon.
[0003] An object of this invention is to provide an alloy and a
method of manufacturing tubes which are even more resistant to
corrosion and whose composition will not hamper the rolling stages
of manufacture.
[0004] To this end, the invention proposes in particular an alloy
with a zirconium base which also contains, by weight, other than
the inevitable impurities, 0.03 to 0.25% in total firstly of iron,
secondly of at least one of the elements from the group comprising
chromium and vanadium, with 0.8 to 1.3% of niobium, less than 2000
ppm of tin, 500 to 2000 ppm of oxygen, less than 100 ppm of carbon,
5 to 35 ppm of sulfur and less than 50 ppm of silicon, the ratio
between the iron content firstly and the chromium or vanadium
content secondly ranging between 0.5 and 30.
[0005] If it has a low content of iron, chromium, vanadium and tin,
an alloy of this type can also be used to make grill plates for a
nuclear fuel assembly.
[0006] The invention also proposes a casing tube for a nuclear fuel
rod or guide tube for a fuel assembly made from an alloy with a
zirconium base, also containing, by weight, 0.03 to 0.25% in total
of, firstly iron, secondly, at least one of the elements from the
group comprising chromium and vanadium, 0.8 to 1.3% by weight of
niobium, less than 2000 ppm of tin, 500 to 2000 ppm of oxygen, less
than 100 ppm of carbon, 5 to 35 ppm of sulfur and less than 50 ppm
of silicon, in the recrystallized state, at least the greater part
of the iron therein being in the form of Zr(Nb,Fe,Cr).sub.2 or
Zr(Nb,Fe,v).sub.2.
[0007] The invention also proposes a manufacturing method,
comprising:
[0008] forming a bar of a zirconium based alloy which also
contains, other than the inevitable impurities, 0.03 to 0.25% in
total firstly of iron, secondly, of at least one of the elements
from the group comprising chromium and vanadium, having 0.8 to 1.3%
of niobium, less than 2000 ppm of tin, 500 to 2000 ppm of oxygen,
less than 100 ppm of carbon, 5 to 35 ppm of sulfur and less than 50
ppm of silicon, the ratio between firstly the iron content and
secondly the chromium or vanadium content ranging between 0.5 and
30,
[0009] quenching the bar in water after heating to between
1000.degree. C. and 1200.degree. C.,
[0010] extruding a blank after heating to a temperature of between
600.degree. C. and 800.degree. C.,
[0011] cold rolling said blank in at least four passes to obtain a
tube, with intermediate heat treatments between 560.degree. C. and
620.degree. C., and
[0012] applying a final heat treatment at between 560.degree. C.
and 620.degree. C., all heat treatments being applied in an inert
atmosphere or under vacuum.
[0013] The final heat treatment brings the tube to the
recrystallized state without modifying the nature of the
phases.
[0014] An oxygen content ranging between 1000 and 1600 ppm is of
particular advantage. It may be adjusted by deliberate and
controlled addition of zirconia before casting.
[0015] More often than not, an alloy without vanadium will be used.
However, vanadium may replace some of the chromium for a high Fe/Cr
ratio or even all.
[0016] In alloys containing approximately 1% of Nb, the presence of
iron with a content in excess of 75 ppm and chromium and/or
vanadium in a content in excess of 5 ppm produces iron contents of
not more than 0.20% with intermetallic compounds of the type Zr(Nb,
Fe, Cr).sub.2 or Zr(Nb,Fe,V).sub.2. Chromium is always present to
form such compounds if contained in the alloy in a quantity of more
than 5 ppm. The existence of the intermetallic compound reduces the
quantity of .beta. phase niobium precipitates and also reduces the
niobium content in solid solution.
[0017] The above-mentioned intermetallic compounds, which
constitute a Laves phase, precipitate in a very fine form, with a
size of between 100 and 200 nanometers. They substitute to the
precipitates of phase .beta. niobium. They significantly improve
the resistance in a lithium-containing medium without significantly
affecting the uniform resistance to corrosion at a temperature of
400.degree. C., representative of the temperature prevailing in
reactors.
[0018] It is preferable not to exceed a total Fe+(Cr and/or V)
content of 2500 ppm (i.e. 0.25% by weight), even though higher
contents remain beneficial in terms of resistance to corrosion in a
lithium-containing medium. The reason for this is that, in addition
to the Laves phase, a precipitate of the type (Zr,
Nb).sub.4Fe.sub.2 appears, the diameter of which can be as much as
1 .mu.m and which is detrimental from the point of view of
rollability. A maximum content of 0.20% constitutes a compromise
close to optimum between corrosion in a lithium-containing medium
and rollability.
[0019] The presence of chromium in the intermetallic precipitates
of type Zr (Nb, Fe, Cr).sub.2 does not have any marked effect on
corrosion at 400.degree. C. up to a Fe/Cr ratio of about 30 because
in this range, chromium is simply substituted for iron in the
intermetallic precipitates as the chromium content increases. The
Fe content may be limited to 0.20% to avoid that excess iron causes
too high a content in the (Zr, Nb).sub.4Fe.sub.2 phase. Improved
resistance to corrosion at 400.degree. C. is obtained if the
Fe/(Cr+V) ratio is higher than 0.5 and the sum of Fe+Cr+V is at
least 0.03%.
[0020] Table I below illustrates how the iron content affects the
corrosion behavior of a sample of zirconium alloy with 1% of
niobium for different iron contents:
1 TABLE I Mass increase (mg/dm.sup.2) lithium-containing steam
water with 70 ppm Li phase Fe 360.degree. C. - 28 days
400.degree.C. - ppm (with pre-filming) 262 days 120 2070 240 1480
1670 250 2920 315 240 4300 25 270
[0021] The contents of C, Si, S, O.sub.2 and Sn were essentially
identical for all samples and were below the maximum values given
above; they were less than 300 ppm for tin.
[0022] Pre-filming is an operation intended to accelerate the
response and selectivity of the corrosion test; this operation
makes it possible to determine the effect of additives on corrosion
more rapidly.
[0023] The sample was manufactured by thermo-metallurgical
operations comparable to those given above, i.e. not exceeding a
temperature of 620.degree. C.
[0024] The effect of the Fe/Cr ratio in the precipitates is shown
in table 2 below, which gives the increase in weight of alloy
samples after being kept in steam for 200 days at a temperature of
400.degree. C. It may be noted that the variation due to change of
Fe/Cr is relatively low.
2 TABLE II Fe/Cr in the Gain in weight precipitates mg/dm.sup.2 0.5
100 1 110 2 120 5 110 30 100
[0025] Complementary tests have shown that similar results are
obtained if the chromium is replaced by vanadium. The chromium or
vanadium contents are selected so as to be low enough not to cause
any major difficulties during the metallurgical treatments and in
particular rolling.
[0026] At present, the lithium content in the water in pressurized
water reactors is not more than a few ppm. This being the case, it
is of advantage to keep the tin content to less than 300 ppm. A
higher content has a slightly adverse affect on resistance to
uniform corrosion in water steam at about 415.degree. C. (whereas
its effect on nodular corrosion in steam at 500.degree. C. is
negligible).
[0027] On the other hand, incorporating tin in a quantity of
between 300 and 2000 ppm and in particular between 1000 and 1500
ppm considerably reduces corrosion in an aqueous medium with the
levels of lithium content currently used to run reactors. Above
1500 ppm, resistance in the lithium-containing medium is only
slightly improved by increasing the tin content so that there would
rarely be any point in going above a value of 1500 ppm of tin.
[0028] The effects described above are set out in Table III
below:
3TABLE III Corrosion in autoclave Mass gain (mg/dm.sup.2) mass gain
in water with 70 ppm lithium after 28 days Tin Steam Steam at
360.degree. C., content 1 day 105 days with pre-heating as a % at
500.degree. C. at 415.degree. C. in steam 0.00 37 135 2560 0.05 43
141 2270 0.10 43 155 1200 0.15 42 165 580 0.25 44 173 280
[0029] The tests set out in table III, the purpose of which was to
ascertain the effect of tin, were conducted on an alloy with a 1%
Nb content, iron, chromium and vanadium being present only as
impurities. They demonstrate an unexpectedly favorable effect of
tin in a lithium-containing medium without any unacceptable
degradation as regards corrosion in steam.
[0030] The contents of C, Si, S, O.sub.2 and Sn were substantially
identical for all samples and were below the maximum values given
above.
* * * * *