[go: up one dir, main page]
More Web Proxy on the site http://driver.im/

CA2764270C - Patin d'espacement pour canal de combustible - Google Patents

Patin d'espacement pour canal de combustible Download PDF

Info

Publication number
CA2764270C
CA2764270C CA2764270A CA2764270A CA2764270C CA 2764270 C CA2764270 C CA 2764270C CA 2764270 A CA2764270 A CA 2764270A CA 2764270 A CA2764270 A CA 2764270A CA 2764270 C CA2764270 C CA 2764270C
Authority
CA
Canada
Prior art keywords
fuel channel
spacer
channel spacer
tube
calandria
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.)
Active
Application number
CA2764270A
Other languages
English (en)
Other versions
CA2764270A1 (fr
Inventor
James M. King
Paul G. Adams
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 CA2764270A priority Critical patent/CA2764270C/fr
Priority to PCT/CA2013/000013 priority patent/WO2013104052A1/fr
Publication of CA2764270A1 publication Critical patent/CA2764270A1/fr
Application granted granted Critical
Publication of CA2764270C publication Critical patent/CA2764270C/fr
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/14—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
    • G21C1/16—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor
    • G21C1/18—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised
    • G21C1/20—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F16—ENGINEERING ELEMENTS AND UNITS; GENERAL MEASURES FOR PRODUCING AND MAINTAINING EFFECTIVE FUNCTIONING OF MACHINES OR INSTALLATIONS; THERMAL INSULATION IN GENERAL
    • F16L—PIPES; JOINTS OR FITTINGS FOR PIPES; SUPPORTS FOR PIPES, CABLES OR PROTECTIVE TUBING; MEANS FOR THERMAL INSULATION IN GENERAL
    • F16L7/00—Supporting pipes or cables inside other pipes or sleeves, e.g. for enabling pipes or cables to be inserted or withdrawn from under roads or railways without interruption of traffic
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28F—DETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
    • F28F1/00—Tubular elements; Assemblies of tubular elements
    • F28F1/003—Multiple wall conduits, e.g. for leak detection
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28F—DETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
    • F28F9/00—Casings; Header boxes; Auxiliary supports for elements; Auxiliary members within casings
    • F28F9/007—Auxiliary supports for elements
    • F28F9/013—Auxiliary supports for elements for tubes or tube-assemblies
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02—Details
    • G21C5/06—Means for locating or supporting fuel elements
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28D—HEAT-EXCHANGE APPARATUS, NOT PROVIDED FOR IN ANOTHER SUBCLASS, IN WHICH THE HEAT-EXCHANGE MEDIA DO NOT COME INTO DIRECT CONTACT
    • F28D21/00—Heat-exchange apparatus not covered by any of the groups F28D1/00 - F28D20/00
    • F28D2021/0019—Other heat exchangers for particular applications; Heat exchange systems not otherwise provided for
    • F28D2021/0054—Other heat exchangers for particular applications; Heat exchange systems not otherwise provided for for nuclear applications
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28F—DETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
    • F28F2240/00—Spacing means
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28F—DETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
    • F28F2265/00—Safety or protection arrangements; Arrangements for preventing malfunction
    • F28F2265/10—Safety or protection arrangements; Arrangements for preventing malfunction for preventing overheating, e.g. heat shields
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28F—DETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
    • F28F2270/00—Thermal insulation; Thermal decoupling
    • 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

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Mechanical Engineering (AREA)
  • Thermal Sciences (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

La présente invention concerne un écarteur permettant de maintenir une distance entre un tube de force et un tube de cuve de réacteur dans un réacteur nucléaire et, de façon plus précise, un écarteur fixé en position entre le tube de force et le tube de cuve de réacteur. La position axiale de lécarteur est maintenue par le fait que lécarteur a un profil extérieur en contact étroit ou légèrement serré avec un profil localement élargi du tube de cuve de réacteur. Un écarteur, un tube de cuve de réacteur correspondant et un procédé dinstallation dudit écarteur sont décrits.
CA2764270A 2012-01-13 2012-01-13 Patin d'espacement pour canal de combustible Active CA2764270C (fr)

Priority Applications (2)

Application Number Priority Date Filing Date Title
CA2764270A CA2764270C (fr) 2012-01-13 2012-01-13 Patin d'espacement pour canal de combustible
PCT/CA2013/000013 WO2013104052A1 (fr) 2012-01-13 2013-01-11 Système écarteur de canal de combustible et procédé

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CA2764270A CA2764270C (fr) 2012-01-13 2012-01-13 Patin d'espacement pour canal de combustible

Publications (2)

Publication Number Publication Date
CA2764270A1 CA2764270A1 (fr) 2013-07-13
CA2764270C true CA2764270C (fr) 2021-02-16

Family

ID=48778845

Family Applications (1)

Application Number Title Priority Date Filing Date
CA2764270A Active CA2764270C (fr) 2012-01-13 2012-01-13 Patin d'espacement pour canal de combustible

Country Status (2)

Country Link
CA (1) CA2764270C (fr)
WO (1) WO2013104052A1 (fr)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN109003690B (zh) * 2018-07-04 2023-08-15 江苏核电有限公司 一种限位盘保护罩及其安装方法

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3593390A (en) * 1968-06-03 1971-07-20 Ca Atomic Energy Ltd Self-locking wedge ring support
JPH0266727U (fr) * 1988-10-31 1990-05-21
GB0719246D0 (en) * 2007-10-03 2007-11-14 Feonic Plc Transducer for vibration absorbing, sensing and transmitting
CA2751147C (fr) * 2009-02-03 2017-01-17 Leslie Donald Dunn Ensemble arbre tronque et palier, et galet porteur de transporteur l'incorporant

Also Published As

Publication number Publication date
CA2764270A1 (fr) 2013-07-13
WO2013104052A1 (fr) 2013-07-18

Similar Documents

Publication Publication Date Title
RU2536817C2 (ru) Корпус тепловыделяющей сборки и теплвыделяющая сборка с таким корпусом
JP5107287B2 (ja) ナトリウム冷却高速炉用蒸気発生器の伝熱管の破損感知装置
KR102087689B1 (ko) 동심 튜브 사이에서 원환 스페이서의 위치를 검출하기 위한 장치 및 방법
KR101675077B1 (ko) 2루프 가압경수로형 증기발생기의 시공방법 및 이를 위한 원자로 배관 시공용 역변위 시스템
US20140270045A1 (en) Nuclear reactor cores comprising a plurality of fuel elements, and to fuel elements for use therein
CA2764270C (fr) Patin d'espacement pour canal de combustible
CN102506409A (zh) 气冷堆蒸汽发生器高温蒸汽连接管的结构布置
Field Problems caused by irradiation deformation in CANDU reactors
JPS60142292A (ja) 原子炉装置
Ross-Ross et al. Some engineering aspects of the investigation into the cracking of pressure tubes in the Pickering reactors
JPS59798B2 (ja) 原子炉の閉鎖装置
EP3170575A1 (fr) Procédé de fabrication d'un élément cylindrique
JP2009115633A (ja) 超音波流量計センサヘッド、これを備えた超音波流量計センサヘッド装置及びその位置決め方法
GB2208961A (en) Anti-vibration flux thimble
Ashida et al. Experimental reactor Joyo
Chatterjee et al. Development of Technology for Detachment of Calandria Tube Rolled Joint of Pressurised Heavy Water Reactors
CA3066139A1 (fr) Raccordement entre un tube a pression et un embout et procede d'assemblage d'un ensemble canal de combustible pour reacteur nucleaire
Althaus et al. Refueling system fabrication and testing
Strachan et al. Operating performance and reliability of CANDU PHWR fuel channels in Canada
Grandjean A state-of-the-art review of past programs devoted to fuel behavior under LOCA conditions
Maeda et al. Plant Component Design (from Mechanism to Structure)
Kochetkov Development of Fast Reactors in the USSR and the Russian Federation: Malfunctions and Incidents in the Course of their Operation and Solution of Problems
Fastabend N-REACTOR PROCESS TUBE ROLLED JOINT STEP REMOVAL. Interim Report
Babu V et al. Design Improvement Studies for Future SFR
Kim et al. Structural Analysis of the Upper Internal Structure in PGSFR

Legal Events

Date Code Title Description
EEER Examination request

Effective date: 20170113