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 PDF

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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
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ppm
range
tube
alloy
tin
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Jean-Paul Mardon
Jean Senevat
Daniel Charquet
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Areva NP SAS
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Areva NP SAS
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/06Casings; Jackets
    • G21C3/07Casings; Jackets characterised by their material, e.g. alloys
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear 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.

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 (%)
First pass 40 70
Passes (2 or 3) 50 to 60 80
Last pass 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 :
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; and
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.
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)

We claim:
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.
US10/624,757 1995-07-27 1996-07-22 Tube for a nuclear fuel assembly, and method for making same Expired - Lifetime USRE43182E1 (en)

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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

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Families Citing this family (35)

* Cited by examiner, † Cited by third party
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
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
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
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
WO2005094504A2 (en) * 2004-03-23 2005-10-13 Westinghouse Electric Company, Llc Zirconium alloys with improved corrosion resistance and method for fabricating zirconium alloys with improved corrosion resistance
US10221475B2 (en) 2004-03-23 2019-03-05 Westinghouse Electric Company Llc Zirconium alloys with improved corrosion/creep 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
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
JP5275998B2 (en) * 2006-10-16 2013-08-28 コミサリア ア レネルジー アトミック エ オ ゼネルジー アルテルナティブ Method for producing and forming erbium-containing zirconium alloy, and structural member containing the 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
KR101474864B1 (en) 2007-12-26 2014-12-19 토륨 파워 인코포레이티드 Nuclear reactor(variants), fuel assembly consisting of driver-breeding modules for a nuclear reactor(variants) and a fuel cell for a fuel assembly
EP3032541B1 (en) 2008-12-25 2019-02-20 Thorium Power, Inc. A fuel element and a method of manufacturing a fuel element for a fuel assembly of a nuclear reactor
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
US10170207B2 (en) 2013-05-10 2019-01-01 Thorium Power, Inc. 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
CN103898361B (en) * 2012-12-27 2017-02-22 中国核动力研究设计院 Zirconium alloy for nuclear reactor core
CN103898363A (en) * 2012-12-27 2014-07-02 中国核动力研究设计院 Zirconium alloy for nuclear power
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
US20220316040A1 (en) * 2019-12-26 2022-10-06 Joint-Stock Company "Tvel" Method of Manufacturing Zirconium Alloy Tubular Products

Citations (14)

* Cited by examiner, † Cited by third party
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)

* Cited by examiner, † Cited by third party
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

Patent Citations (15)

* Cited by examiner, † Cited by third party
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)

* Cited by examiner, † Cited by third party
Title
ASTM Standards B349, "Standard Specification for Zirconium Sponge and Other Forms of Virgin Metal for Nuclear Application".
ASTM Standards B350, "Standard Specification for Zirconium and Zirconium Alloy Ingots for Nuclear Application".
ASTM Standards B353, "Standard Specification for Wrought Zirconium and Zirconium Alloy Seamless and Welded Tubes for Nuclear Service (Except Nuclear Fuel Cladding)".
Charquet, D., "Improvement of the Uniform Corrosion Resistance of Zircaloy-4 in the Absence of Irradiation", Journal of Nuclear Materials, pp. 186-195 (1988).
Charquet, D., et al. "Hydrogen Absorption Kinetics During Zircaloy Oxidation in Steam", Anand M. Garde and E. Ross Bradley, "Zirconium in the Nuclear Industry: Tenth International Symposium", STP 1245 ASTM, (1994), pp. 80-97.
Kass, S., "The Development of the Zircaloys," in Proc. Symp. on Zirconium Alloy Development, Castlewood, Pleasanton, California, Nov. 12-14, 1962; Report GEAP-4089, U.S. Atomic Energy Commission.
Kass, S., "The Development of the Zircaloys;" Corrosion of Zirconium Alloys: A Symposium Presented at the 1963 Winter Meeting of the American Nuclear Society, ASTM STP 368, (1964).
Mardon, J.P., et al., "Development of New Zirconium Alloys for PWR Fuel Rod Cladding", American Nuclear Society Inc., "Proceedings of the 1994 International Topical Meeting on Light Water Reactor Fuel Performance", West Palm Beach Florida, Apr. 17-24, 1994.
Patent Abstracts of Japan-vol. 016, No. 393 (P-1406), Aug. 20, 1992. *
Patent Abstracts of Japan-vol. 016, No. 393 (P-1406), Aug. 20, '92 & JP,A,04 128687 (Nuclear Fuel Ind. Ltd.), Apr. 30, '92.
VanSwam et al., Zirconium in the Nuclear Industry: Eighth International Symposium, Jun. 1988, ASTM, pp. 227-244.

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