MX2013010437A - Metodo y sistema para medir la temperatura de una fosa de combustible usado y el nivel de liquido sin energia electrica externa. - Google Patents

Metodo y sistema para medir la temperatura de una fosa de combustible usado y el nivel de liquido sin energia electrica externa.

Info

Publication number
MX2013010437A
MX2013010437A MX2013010437A MX2013010437A MX2013010437A MX 2013010437 A MX2013010437 A MX 2013010437A MX 2013010437 A MX2013010437 A MX 2013010437A MX 2013010437 A MX2013010437 A MX 2013010437A MX 2013010437 A MX2013010437 A MX 2013010437A
Authority
MX
Mexico
Prior art keywords
thermocouples
spent fuel
fuel pool
measuring
temperature
Prior art date
Application number
MX2013010437A
Other languages
English (en)
Other versions
MX345977B (es
Inventor
Robert J Ginsberg
John Robert Bass
Original Assignee
Ge Hitachi Nucl Energy America
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 Ge Hitachi Nucl Energy America filed Critical Ge Hitachi Nucl Energy America
Publication of MX2013010437A publication Critical patent/MX2013010437A/es
Publication of MX345977B publication Critical patent/MX345977B/es

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G21C17/112—Measuring temperature
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/02—Devices or arrangements for monitoring coolant or moderator
    • G21C17/035—Moderator- or coolant-level detecting devices
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/02—Details of handling arrangements
    • G21C19/06—Magazines for holding fuel elements or control elements
    • G21C19/07—Storage racks; Storage pools
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/02—Devices or arrangements for monitoring coolant or moderator
    • G21C17/022—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
    • 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
    • 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
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
    • Y10T29/00—Metal working
    • Y10T29/49—Method of mechanical manufacture
    • Y10T29/49826—Assembling or joining

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Measurement Of Levels Of Liquids Or Fluent Solid Materials (AREA)

Abstract

Un método y un sistema para medir la temperatura y el nivel de líquido de agua dentro de una fosa de combustible usado (SFP) de un reactor de agua ligera, sin el uso de energía eléctrica externa. El método y el sistema pueden usar una cadena de termoacopladores acoplados con el cable y montados en la fosa de combustible usado. Los termoacopladores suministran su propia energía cuando se calientan con el agua que está expuesta a los termoacopladores dentro de la fosa de combustible usado. Los termoacopladores pueden medir la temperatura en el SFP. Al medir la temperatura, el nivel de líquido del SFP se puede inferir al comparar la diferencia en las mediciones de temperatura de los termoacopladores, ya que los termoacopladores expuestos al aire ambiental experimentarán una temperatura notablemente diferente de los termoacopladores cubiertos por el agua. El cable (con los termoacopladores en un extremo) puede terminar en una ubicación que está lejos del SFP.
MX2013010437A 2012-09-11 2013-09-11 Metodo y sistema para medir la temperatura de una fosa de combustible usado y el nivel de liquido sin energia electrica externa. MX345977B (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US13/609,466 US20140072086A1 (en) 2012-09-11 2012-09-11 Method and system for measuring a spent fuel pool temperature and liquid level without external electrical power

Publications (2)

Publication Number Publication Date
MX2013010437A true MX2013010437A (es) 2014-03-24
MX345977B MX345977B (es) 2017-02-28

Family

ID=49115448

Family Applications (1)

Application Number Title Priority Date Filing Date
MX2013010437A MX345977B (es) 2012-09-11 2013-09-11 Metodo y sistema para medir la temperatura de una fosa de combustible usado y el nivel de liquido sin energia electrica externa.

Country Status (6)

Country Link
US (1) US20140072086A1 (es)
EP (1) EP2706534B1 (es)
JP (1) JP6110765B2 (es)
ES (1) ES2634794T3 (es)
MX (1) MX345977B (es)
TW (1) TWI582792B (es)

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CN108225481A (zh) * 2016-12-09 2018-06-29 国核华清（北京）核电技术研发中心有限公司 一种多运行工况下乏燃料水池液位监测系统及方法
CN106500798B (zh) * 2016-12-16 2024-01-05 宁波奥崎自动化仪表设备有限公司 一种通过导热块导热的分段加热式多点热电偶液位探测器
CN106768159B (zh) * 2017-02-27 2023-11-21 宁波奥崎自动化仪表设备有限公司 一种核电站反应堆堆芯液位探测器
JP6752169B2 (ja) * 2017-03-14 2020-09-09 日立Ｇｅニュークリア・エナジー株式会社 熱電対式液位計測システム
CN109974808B (zh) * 2017-12-27 2024-03-19 核动力运行研究所 一种乏燃料水池自补偿式液位测量系统
CN109102910A (zh) * 2018-09-21 2018-12-28 上海核工程研究设计院有限公司 一种确定乏燃料棒束最小喷淋流量密度的试验装置和方法
CN110853781B (zh) * 2019-10-24 2021-12-03 中广核工程有限公司 一种核电站乏燃料水池综合监测系统和方法
CN111323098A (zh) * 2020-02-28 2020-06-23 中广核研究院有限公司 一种用于反应堆堆芯水位测量的传感器

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Also Published As

Publication number Publication date
TWI582792B (zh) 2017-05-11
US20140072086A1 (en) 2014-03-13
EP2706534B1 (en) 2017-06-21
EP2706534A1 (en) 2014-03-12
JP2014055945A (ja) 2014-03-27
MX345977B (es) 2017-02-28
ES2634794T3 (es) 2017-09-29
JP6110765B2 (ja) 2017-04-05
TW201415481A (zh) 2014-04-16

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