USRE43182E1 - Tube for a nuclear fuel assembly, and method for making same - Google Patents
Tube for a nuclear fuel assembly, and method for making same Download PDFInfo
- Publication number
- USRE43182E1 USRE43182E1 US10/624,757 US62475798A USRE43182E US RE43182 E1 USRE43182 E1 US RE43182E1 US 62475798 A US62475798 A US 62475798A US RE43182 E USRE43182 E US RE43182E
- Authority
- US
- United States
- Prior art keywords
- ppm
- range
- tube
- alloy
- tin
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Lifetime
Links
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
- G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Definitions
- the present invention relates to tubes of zirconium-base alloy suitable for use, in particular, for constituting all or the outer portion of the cladding of a nuclear fuel rod, and also to a method of manufacturing them.
- Alloys have also been proposed that contain, in addition to zirconium, tin to improve creep resistance, and iron.
- An object of the invention is to provide tubes that have simultaneously good creep behavior and good resistance to corrosion, even in a high temperature medium containing lithium, while nevertheless being capable of being manufactured with a low reject rate, and being suitable for use in making cladding or guide tubes for fuel assemblies.
- a tube of zirconium-base alloy containing, by weight, 0.8% to 1.8% niobium, 0.2% to 0.6% tin, and 0.02% to 0.4% iron, the alloy being in the recrystallized state or in relaxed state, depending on whether it is desired to enhance resistance to corrosion or to creep.
- the alloy has a carbon content lying in the range 30 parts per million (ppm) to 180 ppm, a silicon content lying in the range 10 ppm to 120 ppm, and an oxygen content lying in the range 600 ppm to 1600 ppm.
- niobium content which is always above the solubility limit (about 0.6%), provides high resistance to corrosion in an aqueous medium at high temperature. If used alone, niobium at such concentrations imparts creep characteristics to the alloy which are of interest but insufficient. Tin, when associated with niobium, improves creep resistance and also resistance to an aqueous medium containing lithium, without running the risk of causing cracks to be formed during rolling if its content does not exceed 0.6%. An iron content of up to 0.4% participates in compensating for the unfavorable effect of tin on generalized corrosion.
- the alloy contains inevitable impurities, but always at very low contents.
- recrystallization during metal-making can be performed at a relatively low temperature, below 620° C., and that has a favorable effect on hot corrosion resistance and on creep.
- the invention also provides a method of manufacturing a tube for constituting cladding for a nuclear fuel rod or a guide tube for a nuclear fuel assembly.
- the initial alloy-making stage can be that performed conventionally for so-called “Zircaloy 4” alloys.
- the final stages are different, and in particular they make use of recrystallization heat treatments at relatively low temperature only.
- the method may comprise the following steps:
- the recrystallization ratio is advantageously increased from one step to the next in order to render grain size finer.
- the final heat treatment is performed in the range 560° C. to 620° C. when the alloy is to be in recrystallized state, and in the range 470° C. to 500° C. when the tube is to be used in relaxed state.
- the alloy obtained in this way has resistance to generalized corrosion in an aqueous medium at high temperature, representative of conditions within a pressurized water reactor, that is comparable to that of known Zr—Nb alloys having high niobium content, and it has thermal creep resistance that is much greater than that of such alloys and that is comparable to that of the best “Zircaloy 4” alloys.
- an alloy comprising 0.9% to 1.1% niobium, 0.25% to 0.35% tin, and 0.03% to 0.06% iron has been made.
- the metallurgical treatment sequence used comprised rolling over four cycles, with two-hour periods of heat treatment at 580° C. interposed between the rolling step.
- the work hardening ratios and the recrystallization ratios were as follows:
- FIGS. 1 and 2 give the weight increase of alloys according to the invention after 140 days in lithium containing water at 360° C., for different contents of Sn and Fe;
- FIG. 3 represents weight increase (which represents uniform corrosion), after 132 days at 400° C. in water steam;
- FIG. 4 similar to FIG. 3 , corresponds to an exposition of 155 days at 415° C.;
- FIG. 5 again similar to FIG. 3 , corresponds to an exposition of 24 hours to steam at 500° C. and gives a representation of nodular corrosion
- FIG. 6 is a graph indicating limits of zones in which the resistance to corrosion in different conditions is particularly favorable, making it clear that there is a particular interest in ranges 0.2-0.3% Sn and 0.15-0.3 Fe as regards resistance to corrosion.
- FIGS. 1 and 2 indicate that there is no significant enhancement of the resistance to corrosion in lithium containing water beyond about 0.6% Sn and 0.2% Fe.
- FIGS. 3 and 4 show there is an interest in an iron content higher than 0.2%, for enhancing the resistance to corrosion in water steam at 400° C. and 415° C. and reducing the undesirable effect of a high Sn content. Such Figures also indicate that the favorable results which are found for an alloy according to the invention are lost if there is a low tin content or no tin.
- FIG. 5 indicates that there is a progressive loss of the resistance to nodular corrosion when the tin content increases, without significant improvement of the characteristics by adding iron.
- FIG. 5 shows that beyond a tin content of 0.6%, corrosion became faster and it also shows that, for an acceptable tin content, corrosion is faster if the iron content increases beyond about 0.3%.
- Curve A limits a zone of interest as regards resistance in water at 360° C. with a 70 ppm lithium content i.e. under conditions which are more severe than those which prevail in a reactor, as regards the lithium content.
- Curve B limits a zone in which there is satisfactory resistance in lithium containing steam at a temperature slightly beyond 400° C.
- curve C approximately corresponds to a limit of the acceptable contents as regards nodular corrosion resistance, in water steam at 500° C.
Landscapes
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Metallurgy (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Heat Treatment Of Steel (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Rigid Pipes And Flexible Pipes (AREA)
- Production Of Liquid Hydrocarbon Mixture For Refining Petroleum (AREA)
- Metal Extraction Processes (AREA)
Abstract
A zirconium alloy tube for forming the whole or the outer portion of a nuclear fuel pencil housing or a nuclear fuel assembly guide tube. The zirconium alloy contains 0.8-1.8 wt. % of niobium, 0.2-0.6 wt. % of tin and 0.02-0.4 wt. % of iron, and has a carbon content of 30-180 ppm, a silicon content of 10-120 ppm and an oxygen content of 600-1800 ppm. The tube may be used when recrystallized or stress relieved.
Description
The present invention relates to tubes of zirconium-base alloy suitable for use, in particular, for constituting all or the outer portion of the cladding of a nuclear fuel rod, and also to a method of manufacturing them.
Until now, use has been made above all of cladding made of a so-called “Zircaloy 4” alloy which contains tin, iron, and chromium in addition to zirconium. Numerous other compositions have been proposed, with content ranges that are often so broad that, to the person skilled in the art, they can be seen immediately to be purely speculative.
In particular, various alloys have been proposed with a niobium content lying in a range so broad that their resistance to thermal creep is quite poor at maximum values, whatever the metallurgical treatments used in making the alloy.
Alloys have also been proposed that contain, in addition to zirconium, tin to improve creep resistance, and iron.
An object of the invention is to provide tubes that have simultaneously good creep behavior and good resistance to corrosion, even in a high temperature medium containing lithium, while nevertheless being capable of being manufactured with a low reject rate, and being suitable for use in making cladding or guide tubes for fuel assemblies.
One of the causes of rejects is the formation of cracks during mechanical and heat treatments, giving rise to defects that make the tubes unacceptable. This risk exists particularly for high tin contents.
To achieve the above objects, there is provided a tube of zirconium-base alloy containing, by weight, 0.8% to 1.8% niobium, 0.2% to 0.6% tin, and 0.02% to 0.4% iron, the alloy being in the recrystallized state or in relaxed state, depending on whether it is desired to enhance resistance to corrosion or to creep.
The alloy has a carbon content lying in the range 30 parts per million (ppm) to 180 ppm, a silicon content lying in the range 10 ppm to 120 ppm, and an oxygen content lying in the range 600 ppm to 1600 ppm.
The relatively high niobium content, which is always above the solubility limit (about 0.6%), provides high resistance to corrosion in an aqueous medium at high temperature. If used alone, niobium at such concentrations imparts creep characteristics to the alloy which are of interest but insufficient. Tin, when associated with niobium, improves creep resistance and also resistance to an aqueous medium containing lithium, without running the risk of causing cracks to be formed during rolling if its content does not exceed 0.6%. An iron content of up to 0.4% participates in compensating for the unfavorable effect of tin on generalized corrosion.
The contents given above take account of the way in which tolerances and variations within a single ingot mean that the limits can be reached even for set specific contents lying within a narrower range. For example, set contents of 0.84% and 1.71% Nb may give rise within a single ingot to local contents of 0.8% and of 1.8% depending on proximity to the leading end or the trailing end of the ingot.
In addition to the above-specified elements, the alloy contains inevitable impurities, but always at very low contents.
It has been found that set content values of niobium in the range 0.9% to 1.1%, of tin in the range 0.25% to 0.35%, and of iron in the range 0.2% to 0.3% give results that are particularly favorable.
Because of the relatively low tin content, recrystallization during metal-making can be performed at a relatively low temperature, below 620° C., and that has a favorable effect on hot corrosion resistance and on creep.
The invention also provides a method of manufacturing a tube for constituting cladding for a nuclear fuel rod or a guide tube for a nuclear fuel assembly. The initial alloy-making stage can be that performed conventionally for so-called “Zircaloy 4” alloys. However, the final stages are different, and in particular they make use of recrystallization heat treatments at relatively low temperature only.
In particular, the method may comprise the following steps:
making a bar of zirconium-base alloy having the above-specified composition;
quenching the bar in water, after being heated to a temperature in the range 1000° C. to 1200° C.;
drawing the bar into a tubular blank after heating to a temperature lying in the range 600° C. to 800° C.;
annealing the drawn blank at a temperature in the range 590° C. to 650° C.; and
cold-rolling said blank in at least four passes in order to obtain a tube, with intermediate heat treatments at temperatures in the range 560° C. to 620° C.
The recrystallization ratio is advantageously increased from one step to the next in order to render grain size finer.
In general, the final heat treatment is performed in the range 560° C. to 620° C. when the alloy is to be in recrystallized state, and in the range 470° C. to 500° C. when the tube is to be used in relaxed state.
The alloy obtained in this way has resistance to generalized corrosion in an aqueous medium at high temperature, representative of conditions within a pressurized water reactor, that is comparable to that of known Zr—Nb alloys having high niobium content, and it has thermal creep resistance that is much greater than that of such alloys and that is comparable to that of the best “Zircaloy 4” alloys.
By way of example, an alloy comprising 0.9% to 1.1% niobium, 0.25% to 0.35% tin, and 0.03% to 0.06% iron has been made. The metallurgical treatment sequence used comprised rolling over four cycles, with two-hour periods of heat treatment at 580° C. interposed between the rolling step. The work hardening ratios and the recrystallization ratios were as follows:
Work hardening | Recrystallization | |||
ratio (%) | ratio (%) | |||
| 40 | 70 | ||
Passes (2 or 3) | 50 to 60 | 80 | ||
| 30 | 100 | ||
Additional tests have been carried out for determining the influence of the iron and tin content on alloys having 1% of niobium, with contents C, Si and O2 in the above indicated ranges formed into sheets and processed up to Σa=5.23×10−18, with a final recristallization step at 580° C. The corrosion tests were carried out:
at 500° C., 415° C. and 400° C. in water steam
at 360° C., in water containing 70 ppm of lithium.
The tests results are represented on the attached drawings, wherein :
Last, FIG. 5 indicates that there is a progressive loss of the resistance to nodular corrosion when the tin content increases, without significant improvement of the characteristics by adding iron. FIG. 5 shows that beyond a tin content of 0.6%, corrosion became faster and it also shows that, for an acceptable tin content, corrosion is faster if the iron content increases beyond about 0.3%.
From a general consideration of all results, a composition range which is favorable regarding corrosion is defined by the three curves indicated in FIG. 6 . Curve A limits a zone of interest as regards resistance in water at 360° C. with a 70 ppm lithium content i.e. under conditions which are more severe than those which prevail in a reactor, as regards the lithium content. Curve B limits a zone in which there is satisfactory resistance in lithium containing steam at a temperature slightly beyond 400° C. Last, curve C approximately corresponds to a limit of the acceptable contents as regards nodular corrosion resistance, in water steam at 500° C.
It is however possible to exceed the above indicated zone when some types of corrosion are not likely to occur.
Claims (12)
1. A tube of zirconium-base alloy for constituting all or the outside portion of cladding for a nuclear fuel rod or of a guide tube for a nuclear fuel assembly, made of a zirconium-base alloy containing, by weight, 0.8% to 1.8% niobium, 0.2% to 0.6% tin, and 0.02% to 0.4% iron, plus inevitable impurities, and having a carbon content controlled to lie in the range 30 ppm to 180 ppm, a silicon content in the range 10 ppm to 120 ppm, and an oxygen content in the range 600 ppm to 1800 ppm.
2. A tube according to claim 1 , wherein the alloy is in recrystallized state.
3. A tube according to claim 1 , wherein the alloy is in relaxed state.
4. A tube according to claim 1 , wherein the alloy has set contents: 0.9% to 1.1% niobium, 0.25% to 0.35% tin, and 0.2% to 0.3% iron.
5. A method of manufacturing a tube according to claim 1 of zirconium-base alloy for constituting all or an outside portion of cladding for a nuclear fuel rod or of a guide tube for a nuclear fuel assembly, made of a zirconium-base alloy consisting essentially of, by weight, 0.8% to 1.8% niobium, 0.2% to 0.6% tin, and 0.02% to 0.4% iron, plus inevitable impurities, and having a carbon content controlled to lie in the range 30 ppm to 180 ppm, a silicon content in the range 10 ppm to 120 ppm, and an oxygen content in the range 600 ppm to 1800, including the following steps of:
making a bar of an alloy containing 0.8% to 1.8% niobium, 0.2% to 0.6% tin, and 0.02% to 0.4% iron;
after heating in the bar to a temperature in the range 1000° C. to 1200° C., quenching the bar in water;
drawing the bar into a blank after heating to a temperature in the range 600° C. to 800° C.;
annealing the drawn blank at a temperature in the range 590° C. to 650° C.; and
cold rolling the annealed blank in at least four passes into a tube, with intermediate heat treatments at temperatures in the range 560° C. to 620° C.
6. A method according to claim 5 , wherein the rolling passes are performed on tubes having increasing recrystallization ratios.
7. A method according to claim 5 , further including a recrystallizing final heat treatment step at a temperature in the range 560° C. to 620° C.
8. A method according to claim 5 , further including a strain relieving final heat treatment step at a temperature in the range from about 470° C. to 500° C.
9. A tube for constituting all or an outside portion of cladding for a nuclear fuel rod or of a guide tube for a nuclear fuel assembly, made of zirconium-base alloy consisting essentially of:
0.8% wt. to 1.8% wt. niobium,
0.2% wt. to 0.6% wt. tin,
0.02% wt. to 0.4% wt. iron, plus inevitable impurities,
a carbon content controlled to lie in the range 30 ppm to 180-ppm,
a silicon content in the range 10 ppm to 120 ppm, and
an oxygen content in the range 600 ppm to 1800 ppm, with the balance zirconium.
10. A tube according to claim 9, wherein the alloy is in recrystallized state.
11. A tube according to claim 9, wherein the alloy is in relaxed state.
12. A tube according to claim 9, wherein the alloy has set contents: 0.9 wt. % to 1.1 wt. % niobium, 0.25 wt. % to 0.35 wt. % tin, and 0.2 wt. % to 0.3 wt. % iron.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US10/624,757 USRE43182E1 (en) | 1995-07-27 | 1996-07-22 | Tube for a nuclear fuel assembly, and method for making same |
Applications Claiming Priority (5)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR9509166A FR2737335B1 (en) | 1995-07-27 | 1995-07-27 | TUBE FOR NUCLEAR FUEL ASSEMBLY AND METHOD FOR MANUFACTURING SUCH A TUBE |
FR9509166 | 1995-07-27 | ||
US09/000,104 US5940464A (en) | 1995-07-27 | 1996-07-22 | Tube for a nuclear fuel assembly, and method for making same |
US10/624,757 USRE43182E1 (en) | 1995-07-27 | 1996-07-22 | Tube for a nuclear fuel assembly, and method for making same |
PCT/FR1996/001149 WO1997005628A1 (en) | 1995-07-27 | 1996-07-22 | Tube for a nuclear fuel assembly and method for making same |
Publications (1)
Publication Number | Publication Date |
---|---|
USRE43182E1 true USRE43182E1 (en) | 2012-02-14 |
Family
ID=9481461
Family Applications (2)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
US09/000,104 Ceased US5940464A (en) | 1995-07-27 | 1996-07-22 | Tube for a nuclear fuel assembly, and method for making same |
US10/624,757 Expired - Lifetime USRE43182E1 (en) | 1995-07-27 | 1996-07-22 | Tube for a nuclear fuel assembly, and method for making same |
Family Applications Before (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
US09/000,104 Ceased US5940464A (en) | 1995-07-27 | 1996-07-22 | Tube for a nuclear fuel assembly, and method for making same |
Country Status (11)
Country | Link |
---|---|
US (2) | US5940464A (en) |
EP (1) | EP0840931B1 (en) |
JP (1) | JP4022257B2 (en) |
KR (1) | KR100441979B1 (en) |
CN (1) | CN1119817C (en) |
DE (1) | DE69605305T2 (en) |
ES (1) | ES2140117T3 (en) |
FR (1) | FR2737335B1 (en) |
TW (1) | TW335495B (en) |
WO (1) | WO1997005628A1 (en) |
ZA (1) | ZA966275B (en) |
Families Citing this family (35)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5838753A (en) * | 1997-08-01 | 1998-11-17 | Siemens Power Corporation | Method of manufacturing zirconium niobium tin alloys for nuclear fuel rods and structural parts for high burnup |
SE513185C2 (en) † | 1998-12-11 | 2000-07-24 | Asea Atom Ab | Zirconium-based alloy and component of a nuclear power plant |
US7627075B2 (en) | 1999-09-30 | 2009-12-01 | Framatome Anp | Zirconium-based alloy and method for making a component for nuclear fuel assembly with same |
FR2799209B1 (en) * | 1999-09-30 | 2001-11-30 | Framatome Sa | ZIRCONIUM-BASED ALLOY AND METHOD OF MANUFACTURING COMPONENT FOR ASSEMBLY OF NUCLEAR FUEL IN SUCH AN ALLOY |
FR2799210B1 (en) | 1999-09-30 | 2001-11-30 | Framatome Sa | ZIRCONIUM-BASED ALLOY AND METHOD OF MANUFACTURING COMPONENT FOR ASSEMBLY OF NUCLEAR FUEL IN SUCH AN ALLOY |
KR100334252B1 (en) * | 1999-11-22 | 2002-05-02 | 장인순 | Niobium-containing zirconium alloys for nuclear fuel cladding |
DE10026241B4 (en) * | 2000-05-26 | 2007-06-28 | Eckard Steinberg | Production of a cladding tube of a pressurized water reactor fuel rod, cladding tube and corresponding fuel assembly |
KR100382997B1 (en) * | 2001-01-19 | 2003-05-09 | 한국전력공사 | Method of Manufacturing A Tube and A Sheet of Niobium-containing Zirconium Alloys for High Burn-up Nuclear Fuel |
KR100461017B1 (en) * | 2001-11-02 | 2004-12-09 | 한국수력원자력 주식회사 | Method for preparing niobium-containing zirconium alloys for nuclear fuel cladding tubes having the excellent corrosion resistance |
DE10332239B3 (en) * | 2003-07-16 | 2005-03-03 | Framatome Anp Gmbh | Zirconium alloy and components for the core of light water cooled nuclear reactors |
EP1730318A4 (en) * | 2004-03-23 | 2010-08-18 | Westinghouse Electric Corp | Zirconium alloys with improved corrosion resistance and method for fabricating zirconium alloys with improved corrosion resistance |
US9284629B2 (en) | 2004-03-23 | 2016-03-15 | Westinghouse Electric Company Llc | Zirconium alloys with improved corrosion/creep resistance due to final heat treatments |
US10221475B2 (en) | 2004-03-23 | 2019-03-05 | Westinghouse Electric Company Llc | Zirconium alloys with improved corrosion/creep resistance |
FR2874119B1 (en) | 2004-08-04 | 2006-11-03 | Framatome Anp Sas | METHOD FOR MANUFACTURING A FUEL SINK TUBE FOR A NUCLEAR REACTOR, AND A TUBE THUS OBTAINED |
KR100733701B1 (en) * | 2005-02-07 | 2007-06-28 | 한국원자력연구원 | Zr-based Alloys Having Excellent Creep Resistance |
US7625453B2 (en) * | 2005-09-07 | 2009-12-01 | Ati Properties, Inc. | Zirconium strip material and process for making same |
FR2890767B1 (en) * | 2005-09-09 | 2007-10-19 | Framatome Anp Sas | METHOD FOR DETERMINING AT LEAST ONE FACTOR OF TECHNOLOGICAL UNCERTAINTY OF NUCLEAR FUEL ELEMENTS, DESIGN METHOD, MANUFACTURING METHOD AND METHOD FOR CONTROLLING CORRESPONDING NUCLEAR FUEL ELEMENTS |
CN101528957B (en) * | 2006-10-16 | 2012-07-04 | 法国原子能委员会 | Erbium-containing zirconium alloy, method for preparing and shaping the same, and structural part containing said alloy |
KR100831578B1 (en) * | 2006-12-05 | 2008-05-21 | 한국원자력연구원 | Zirconium alloy compositions having excellent corrosion resistance for nuclear applications and preparation method thereof |
FR2909798A1 (en) * | 2006-12-11 | 2008-06-13 | Areva Np Sas | Designing fuel assembly, useful for light-water nuclear reactor comprising structural components of zirconium alloy, comprises calculating uniaxial constraints using traction/compression and choosing the alloys |
KR20080074568A (en) * | 2007-02-09 | 2008-08-13 | 한국원자력연구원 | High fe contained zirconium alloy compositions having excellent corrosion resistance and preparation method thereof |
US8116423B2 (en) | 2007-12-26 | 2012-02-14 | Thorium Power, Inc. | Nuclear reactor (alternatives), fuel assembly of seed-blanket subassemblies for nuclear reactor (alternatives), and fuel element for fuel assembly |
EA015019B1 (en) | 2007-12-26 | 2011-04-29 | Ториум Пауэр Инк. | Nuclear reactor (variants), fuel assembly consisting of driver-breeding modules for a nuclear reactor (variants) and a fuel cell for a fuel assembly |
HUE043364T2 (en) | 2008-12-25 | 2019-08-28 | Thorium Power Inc | A fuel element and a method of manufacturing a fuel element for a fuel assembly of a nuclear reactor |
US10170207B2 (en) | 2013-05-10 | 2019-01-01 | Thorium Power, Inc. | Fuel assembly |
WO2011143172A1 (en) | 2010-05-11 | 2011-11-17 | Thorium Power, Inc. | Fuel assembly with metal fuel alloy kernel and method of manufacturing thereof |
US10192644B2 (en) | 2010-05-11 | 2019-01-29 | Lightbridge Corporation | Fuel assembly |
ES2886336T3 (en) * | 2011-06-16 | 2021-12-17 | Westinghouse Electric Co Llc | Manufacturing process of a zirconium-based liner tube with improved creep resistance due to final heat treatment |
KR20130098621A (en) * | 2012-02-28 | 2013-09-05 | 한국원자력연구원 | Zirconium alloys for nuclear fuel cladding, having a superior oxidation resistance in a severe reactor operation conditions, and the preparation method of zirconium alloys nuclear fuel claddings using thereof |
CN102660699B (en) * | 2012-05-16 | 2014-02-12 | 上海大学 | Zr-Sn-Nb-Fe-Si alloy for fuel cladding of nuclear power station |
CN103898363A (en) * | 2012-12-27 | 2014-07-02 | 中国核动力研究设计院 | Zirconium alloy for nuclear power |
CN103898361B (en) * | 2012-12-27 | 2017-02-22 | 中国核动力研究设计院 | Zirconium alloy for nuclear reactor core |
KR101557391B1 (en) | 2014-04-10 | 2015-10-07 | 한전원자력연료 주식회사 | Zirconium alloys compositions and preparation method having low-hydrogen pick-up rate and resistance against hydrogen embrittlement |
FR3098224B1 (en) * | 2019-07-05 | 2021-10-01 | Framatome Sa | Tubular component of a pressurized water nuclear reactor and method of manufacturing this component |
CN113613807B (en) * | 2019-12-26 | 2023-12-26 | Tvel股份公司 | Method for manufacturing zirconium alloy tubular product |
Citations (14)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4309250A (en) * | 1979-07-05 | 1982-01-05 | The United States Of America As Represented By The United States Department Of Energy | Between-cycle laser system for depressurization and resealing of modified design nuclear fuel assemblies |
US4649023A (en) | 1985-01-22 | 1987-03-10 | Westinghouse Electric Corp. | Process for fabricating a zirconium-niobium alloy and articles resulting therefrom |
JPS63145735A (en) | 1986-12-08 | 1988-06-17 | Sumitomo Metal Ind Ltd | Zirconium alloy |
US5023048A (en) | 1989-01-23 | 1991-06-11 | Framatome | Rod for a fuel assembly of a nuclear reactor resisting corrosion and wear |
JPH04128687A (en) | 1990-09-20 | 1992-04-30 | Nuclear Fuel Ind Ltd | Covering tube for nuclear fuel and its manufacture |
US5112573A (en) | 1989-08-28 | 1992-05-12 | Westinghouse Electric Corp. | Zirlo material for light water reactor applications |
US5125985A (en) | 1989-08-28 | 1992-06-30 | Westinghouse Electric Corp. | Processing zirconium alloy used in light water reactors for specified creep rate |
EP0533073A1 (en) | 1991-09-16 | 1993-03-24 | Siemens Power Corporation | Structural elements for a nuclear reactor fuel assembly |
US5230758A (en) | 1989-08-28 | 1993-07-27 | Westinghouse Electric Corp. | Method of producing zirlo material for light water reactor applications |
US5254308A (en) | 1992-12-24 | 1993-10-19 | Combustion Engineering, Inc. | Zirconium alloy with improved post-irradiation properties |
US5266131A (en) | 1992-03-06 | 1993-11-30 | Westinghouse Electric Corp. | Zirlo alloy for reactor component used in high temperature aqueous environment |
US5289513A (en) * | 1992-10-29 | 1994-02-22 | Westinghouse Electric Corp. | Method of making a fuel assembly lattice member and the lattice member made by such method |
WO1994023081A1 (en) | 1993-03-04 | 1994-10-13 | Vnii Neorga | Zirconium-based material, article made of the said material for use in the active zones of atomic reactors, and a process for obtaining such articles |
US5648995A (en) | 1994-12-29 | 1997-07-15 | Framatome | Method of manufacturing a tube for a nuclear fuel assembly, and tubes obtained thereby |
Family Cites Families (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE4130650A1 (en) * | 1991-09-14 | 1993-03-18 | Kesslertech Gmbh | AIR CONDITIONING FOR THE HUMAN AREA, ESPECIALLY FOR LIVING AND WORKING AREAS |
FR2686445B1 (en) * | 1992-01-17 | 1994-04-08 | Framatome Sa | NUCLEAR FUEL PENCIL AND METHOD FOR MANUFACTURING THE SHEATH OF SUCH A PENCIL. |
US5278882A (en) * | 1992-12-30 | 1994-01-11 | Combustion Engineering, Inc. | Zirconium alloy with superior corrosion resistance |
-
1995
- 1995-07-27 FR FR9509166A patent/FR2737335B1/en not_active Expired - Fee Related
-
1996
- 1996-07-22 WO PCT/FR1996/001149 patent/WO1997005628A1/en active IP Right Grant
- 1996-07-22 JP JP50727497A patent/JP4022257B2/en not_active Expired - Fee Related
- 1996-07-22 ES ES96926439T patent/ES2140117T3/en not_active Expired - Lifetime
- 1996-07-22 US US09/000,104 patent/US5940464A/en not_active Ceased
- 1996-07-22 KR KR10-1998-0700623A patent/KR100441979B1/en not_active IP Right Cessation
- 1996-07-22 CN CN96196564A patent/CN1119817C/en not_active Expired - Lifetime
- 1996-07-22 US US10/624,757 patent/USRE43182E1/en not_active Expired - Lifetime
- 1996-07-22 DE DE69605305T patent/DE69605305T2/en not_active Expired - Lifetime
- 1996-07-22 EP EP96926439A patent/EP0840931B1/en not_active Expired - Lifetime
- 1996-07-24 ZA ZA9606275A patent/ZA966275B/en unknown
- 1996-08-15 TW TW085109964A patent/TW335495B/en not_active IP Right Cessation
Patent Citations (15)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4309250A (en) * | 1979-07-05 | 1982-01-05 | The United States Of America As Represented By The United States Department Of Energy | Between-cycle laser system for depressurization and resealing of modified design nuclear fuel assemblies |
US4649023A (en) | 1985-01-22 | 1987-03-10 | Westinghouse Electric Corp. | Process for fabricating a zirconium-niobium alloy and articles resulting therefrom |
JPS63145735A (en) | 1986-12-08 | 1988-06-17 | Sumitomo Metal Ind Ltd | Zirconium alloy |
US5023048A (en) | 1989-01-23 | 1991-06-11 | Framatome | Rod for a fuel assembly of a nuclear reactor resisting corrosion and wear |
US5125985A (en) | 1989-08-28 | 1992-06-30 | Westinghouse Electric Corp. | Processing zirconium alloy used in light water reactors for specified creep rate |
US5112573A (en) | 1989-08-28 | 1992-05-12 | Westinghouse Electric Corp. | Zirlo material for light water reactor applications |
US5230758A (en) | 1989-08-28 | 1993-07-27 | Westinghouse Electric Corp. | Method of producing zirlo material for light water reactor applications |
JPH04128687A (en) | 1990-09-20 | 1992-04-30 | Nuclear Fuel Ind Ltd | Covering tube for nuclear fuel and its manufacture |
EP0533073A1 (en) | 1991-09-16 | 1993-03-24 | Siemens Power Corporation | Structural elements for a nuclear reactor fuel assembly |
US5266131A (en) | 1992-03-06 | 1993-11-30 | Westinghouse Electric Corp. | Zirlo alloy for reactor component used in high temperature aqueous environment |
US5289513A (en) * | 1992-10-29 | 1994-02-22 | Westinghouse Electric Corp. | Method of making a fuel assembly lattice member and the lattice member made by such method |
US5254308A (en) | 1992-12-24 | 1993-10-19 | Combustion Engineering, Inc. | Zirconium alloy with improved post-irradiation properties |
WO1994023081A1 (en) | 1993-03-04 | 1994-10-13 | Vnii Neorga | Zirconium-based material, article made of the said material for use in the active zones of atomic reactors, and a process for obtaining such articles |
US5560790A (en) | 1993-03-04 | 1996-10-01 | A.A. Bochvar All-Russian Inorganic Materials Research Institute | Zirconium-based material, products made from said material for use in the nuclear reactor core, and process for producing such products |
US5648995A (en) | 1994-12-29 | 1997-07-15 | Framatome | Method of manufacturing a tube for a nuclear fuel assembly, and tubes obtained thereby |
Non-Patent Citations (11)
Also Published As
Publication number | Publication date |
---|---|
DE69605305D1 (en) | 1999-12-30 |
ES2140117T3 (en) | 2000-02-16 |
KR19990035962A (en) | 1999-05-25 |
EP0840931B1 (en) | 1999-11-24 |
FR2737335B1 (en) | 1997-10-10 |
WO1997005628A1 (en) | 1997-02-13 |
TW335495B (en) | 1998-07-01 |
JP4022257B2 (en) | 2007-12-12 |
EP0840931A1 (en) | 1998-05-13 |
JPH11509927A (en) | 1999-08-31 |
FR2737335A1 (en) | 1997-01-31 |
CN1194052A (en) | 1998-09-23 |
US5940464A (en) | 1999-08-17 |
KR100441979B1 (en) | 2004-10-14 |
CN1119817C (en) | 2003-08-27 |
ZA966275B (en) | 1997-02-11 |
DE69605305T2 (en) | 2000-06-08 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
USRE43182E1 (en) | Tube for a nuclear fuel assembly, and method for making same | |
US5648995A (en) | Method of manufacturing a tube for a nuclear fuel assembly, and tubes obtained thereby | |
US7364631B2 (en) | Zirconium-based alloy having a high resistance to corrosion and to hydriding by water and steam and process for the thermomechanical transformation of the alloy | |
US4212686A (en) | Zirconium alloys | |
US5373541A (en) | Nuclear fuel rod and method of manufacturing the cladding of such a rod | |
US6261516B1 (en) | Niobium-containing zirconium alloy for nuclear fuel claddings | |
US5832050A (en) | Zirconium-based alloy, manufacturing process, and use in a nuclear reactor | |
US8882939B2 (en) | Zirconium alloy resistant to corrosion in drop shadows for a fuel assembly component for a boiling water reactor, component produced using said alloy, fuel assembly, and use of same | |
US5702544A (en) | Zirconium-based alloy tube for a nuclear reactor fuel assembly and a process for producing such a tube | |
US6544361B1 (en) | Process for manufacturing thin components made of zirconium-based alloy and straps thus produced | |
KR101604105B1 (en) | Zirconium alloy having excellent corrosion resistance and creep resistance and method of manufacturing for it | |
US4981527A (en) | Tube, bar, sheet or strip made from zirconium alloy resistant both to uniform and nodular corrosion | |
US20070053476A1 (en) | Method of producing a flat zirconium alloy product, flat product thus obtained and a nuclear plant reactor grid which is made from said flat product | |
US4671826A (en) | Method of processing tubing | |
US5887045A (en) | Zirconium alloy tube for a nuclear reactor fuel assembly, and method for making same | |
RU2187155C2 (en) | Alloy and tube for nuclear reactor fuel assembly and tube manufacturing process | |
US7630470B2 (en) | Method for making a flat zirconium alloy product, resulting flat product and fuel, assembly component for nuclear power plant reactor made from said flat product | |
US7292671B1 (en) | Zirconium based alloy and component in a nuclear energy plant | |
US4512819A (en) | Method for manufacturing a cladding tube of a zirconium alloy for nuclear reactor fuel of a nuclear reactor fuel assembly | |
JPH0867954A (en) | Production of high corrosion resistant zirconium alloy | |
RU2172527C2 (en) | Nuclear fuel assembly tube and its manufacturing process | |
US20040118491A1 (en) | Alloy and tube for nuclear fuel assembly and method for making same | |
US7985373B2 (en) | Alloy and tube for nuclear fuel assembly and method for making same | |
JPH05163545A (en) | Zr base alloy excellent in corrosion resistance | |
JPH10183278A (en) | High corrosion resistant zirconium alloy |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
AS | Assignment |
Owner name: AREVA NP, FRANCE Free format text: CHANGE OF NAME;ASSIGNOR:FRAMATOME ANP;REEL/FRAME:026845/0448 Effective date: 20060216 |
|
AS | Assignment |
Owner name: AREVA NP, FRANCE Free format text: CHANGE OF NAME;ASSIGNOR:FRAMATOME ANP;REEL/FRAME:026890/0715 Effective date: 20060216 |