CA1163120A - Tubes en alliage a base de zr a coefficient de dilatation reduit pour reacteurs - Google Patents

Tubes en alliage a base de zr a coefficient de dilatation reduit pour reacteurs

Info

Publication number
CA1163120A
CA1163120A CA000355707A CA355707A CA1163120A CA 1163120 A CA1163120 A CA 1163120A CA 000355707 A CA000355707 A CA 000355707A CA 355707 A CA355707 A CA 355707A CA 1163120 A CA1163120 A CA 1163120A
Authority
CA
Canada
Prior art keywords
extruded
tubes
service
product
range
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
Application number
CA000355707A
Other languages
English (en)
Inventor
Brian A. Cheadle
Richard A. Holt
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Atomic Energy of Canada Ltd AECL
Original Assignee
Atomic Energy of Canada Ltd AECL
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Atomic Energy of Canada Ltd AECL filed Critical Atomic Energy of Canada Ltd AECL
Priority to CA000355707A priority Critical patent/CA1163120A/fr
Priority to GB8120617A priority patent/GB2079317B/en
Priority to RO81104795A priority patent/RO83384A/fr
Priority to IT22790/81A priority patent/IT1137284B/it
Priority to SE8104233A priority patent/SE8104233L/
Priority to KR1019810002464A priority patent/KR830006454A/ko
Priority to JP56105159A priority patent/JPS5794542A/ja
Priority to FR8113581A priority patent/FR2486541A1/fr
Application granted granted Critical
Publication of CA1163120A publication Critical patent/CA1163120A/fr
Expired legal-status Critical Current

Links

Classifications

    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22F—CHANGING THE PHYSICAL STRUCTURE OF NON-FERROUS METALS AND NON-FERROUS ALLOYS
    • C22F1/00—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working
    • C22F1/16—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working of other metals or alloys based thereon
    • C22F1/18—High-melting or refractory metals or alloys based thereon
    • C22F1/186—High-melting or refractory metals or alloys based thereon of zirconium or alloys based thereon

Landscapes

  • Chemical & Material Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Thermal Sciences (AREA)
  • Crystallography & Structural Chemistry (AREA)
  • Engineering & Computer Science (AREA)
  • Materials Engineering (AREA)
  • Physics & Mathematics (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Heat Treatment Of Steel (AREA)
  • Heat Treatment Of Nonferrous Metals Or Alloys (AREA)
  • Extrusion Of Metal (AREA)
  • Rigid Pipes And Flexible Pipes (AREA)
CA000355707A 1980-07-08 1980-07-08 Tubes en alliage a base de zr a coefficient de dilatation reduit pour reacteurs Expired CA1163120A (fr)

Priority Applications (8)

Application Number Priority Date Filing Date Title
CA000355707A CA1163120A (fr) 1980-07-08 1980-07-08 Tubes en alliage a base de zr a coefficient de dilatation reduit pour reacteurs
GB8120617A GB2079317B (en) 1980-07-08 1981-07-03 Zr base alloy tubes providing low inreactor creep
RO81104795A RO83384A (fr) 1980-07-08 1981-07-06 Procede de fabrication des tubes en alliage de zirconium
IT22790/81A IT1137284B (it) 1980-07-08 1981-07-07 Procedimento per fabbricare tubi in leghe di zirconio destinati all'impiego in reattori ed energia nucleare
SE8104233A SE8104233L (sv) 1980-07-08 1981-07-07 Zr-legeringsror med lag reaktorkrypning
KR1019810002464A KR830006454A (ko) 1980-07-08 1981-07-07 원자로용 저크립 Zr-기본 합금관
JP56105159A JPS5794542A (en) 1980-07-08 1981-07-07 Alloy product and production thereof
FR8113581A FR2486541A1 (fr) 1980-07-08 1981-07-08 Tubes en alliage de zirconium a faible fluage pour reacteurs nucleaires, et leur procede de fabrication

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CA000355707A CA1163120A (fr) 1980-07-08 1980-07-08 Tubes en alliage a base de zr a coefficient de dilatation reduit pour reacteurs

Publications (1)

Publication Number Publication Date
CA1163120A true CA1163120A (fr) 1984-03-06

Family

ID=4117371

Family Applications (1)

Application Number Title Priority Date Filing Date
CA000355707A Expired CA1163120A (fr) 1980-07-08 1980-07-08 Tubes en alliage a base de zr a coefficient de dilatation reduit pour reacteurs

Country Status (8)

Country Link
JP (1) JPS5794542A (fr)
KR (1) KR830006454A (fr)
CA (1) CA1163120A (fr)
FR (1) FR2486541A1 (fr)
GB (1) GB2079317B (fr)
IT (1) IT1137284B (fr)
RO (1) RO83384A (fr)
SE (1) SE8104233L (fr)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4649023A (en) * 1985-01-22 1987-03-10 Westinghouse Electric Corp. Process for fabricating a zirconium-niobium alloy and articles resulting therefrom
EP0196286B1 (fr) * 1985-03-12 1989-05-17 Santrade Ltd. Procédé de fabrication de tubes en alliage de zirconium à haute résistance à la corrosion pour réacteurs nucléaires thermiques
CN105808910B (zh) * 2014-12-30 2018-11-02 中核核电运行管理有限公司 锆铌压力管在candu反应堆中的辐照变形计算方法

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CA1014833A (fr) * 1974-07-12 1977-08-02 Stuart R. Macewen Alliage a base de zirconium et methode de fabrication
CA1027781A (fr) * 1975-05-06 1978-03-14 Brian A. Cheadle Procede de fabrication de tubes tres resistants en alliage de sn-mo-nb-zr

Also Published As

Publication number Publication date
SE8104233L (sv) 1982-01-09
IT8122790A0 (it) 1981-07-07
FR2486541A1 (fr) 1982-01-15
JPS5794542A (en) 1982-06-12
KR830006454A (ko) 1983-09-24
RO83384A (fr) 1984-08-17
GB2079317A (en) 1982-01-20
IT1137284B (it) 1986-09-03
RO83384B (ro) 1984-04-30
GB2079317B (en) 1984-11-07
FR2486541B1 (fr) 1984-09-14

Similar Documents

Publication Publication Date Title
KR100382997B1 (ko) 고연소도 핵연료 용 니오븀 함유 지르코늄 합금 관재 및판재의 제조방법
EP1256634B1 (fr) Alliage de zirconium présentant une excellente résistance à la corrosion ainsi que des propriétés mécaniques et procédé de fabrication d'une gaine en alliage de zirconium pour barres de combustible nucléaire
KR20030037137A (ko) 우수한 내식성을 갖는 니오븀 함유 지르코늄 합금핵연료피복관의 제조방법
KR930009987B1 (ko) 개선된 내부식성 지르코니움 합금관 소둔방법
JPH0625389B2 (ja) 高耐食低水素吸収性ジルコニウム基合金及びその製造法
US20050205175A1 (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
US4452648A (en) Low in reactor creep ZR-base alloy tubes
CN1068065C (zh) 用于核反应堆燃料组件的锆基合金管及生产这种管的方法
JP2731414B2 (ja) 均質腐食及びノジュラー腐食に対して耐食性の管、バー、シート又はストリップ、及びその製造方法
US5047093A (en) Heat treatment of Alloy 718 for improved stress corrosion cracking resistance
US4360389A (en) Zirconium alloy heat treatment process
EP0529907A1 (fr) Procédé pour le recuit d'alliages de zirconium en vue d'améliorer la résistance à la corrosion nodulaire
EP0899747A2 (fr) Procédé de fabrication d'alliages de Zirconium-Etain-Fer pour des barreaux de combustible nucléaire et des éléments structurels qui permettent un haut degré de combustion
CA1163120A (fr) Tubes en alliage a base de zr a coefficient de dilatation reduit pour reacteurs
CA1080513A (fr) Procede de traitement thermique de profiles en alliage de zirconium
JPH10501846A (ja) 原子炉のためのジルコニウム基合金の管の製造方法及びその用途
CN112981273A (zh) 铁素体合金及利用其制造核燃料包壳管的方法
Cheadle et al. Low in reactor creep Zr-base alloy tubes
KIM et al. Mechanism of Abrupt Ductile-To-Brittle Transition of Hydrided Zircaloy and Improving Resistance to Hydride Embrittlement Via Grain Size Control
Sabol et al. Improved PWR fuel cladding
Kapoor et al. Microstructure evolution and tensile properties of Zr-2.5 wt% Nb pressure tubes processed from billets with different microstructures
JPH07173587A (ja) ジルコニウム合金溶接部材の製造方法
EP0745258B1 (fr) Element combustible nucleaire pour reacteur a eau pressurisee et son procede de production
EP1149180A1 (fr) Alliage a base de zirconium et composant dans une installation d'energie nucleaire
Bai Effect of hydriding temperature and strain rate on the ductile-brittle transition in β treated Zircaloy-4

Legal Events

Date Code Title Description
MKEX Expiry