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WO2025136137A1 - Dispositif de contrôle de pression dans une pastille de combustible d'un réacteur nucléaire - Google Patents

Dispositif de contrôle de pression dans une pastille de combustible d'un réacteur nucléaire Download PDF

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Publication number
WO2025136137A1
WO2025136137A1 PCT/RU2023/000386 RU2023000386W WO2025136137A1 WO 2025136137 A1 WO2025136137 A1 WO 2025136137A1 RU 2023000386 W RU2023000386 W RU 2023000386W WO 2025136137 A1 WO2025136137 A1 WO 2025136137A1
Authority
WO
WIPO (PCT)
Prior art keywords
fuel element
measuring unit
fuel
temperature
nuclear reactor
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.)
Pending
Application number
PCT/RU2023/000386
Other languages
English (en)
Russian (ru)
Inventor
Михаил Юрьевич ЗАЙЦЕВ
Андрей Евгеньевич КАЗИКИН
Виктор Яковлевич СОБОЛЕВ
Юрий Семенович ШУЛЬМАН
Александр Геннадиевич МИШИН
Сергей Викторович УЛИЗКО
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.)
Joint Stock Co "machinery Manufacturing Plant"
Original Assignee
Joint Stock Co "machinery Manufacturing Plant"
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 Joint Stock Co "machinery Manufacturing Plant" filed Critical Joint Stock Co "machinery Manufacturing Plant"
Priority to PCT/RU2023/000386 priority Critical patent/WO2025136137A1/fr
Publication of WO2025136137A1 publication Critical patent/WO2025136137A1/fr
Pending legal-status Critical Current
Anticipated expiration legal-status Critical

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Classifications

    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01L—MEASURING FORCE, STRESS, TORQUE, WORK, MECHANICAL POWER, MECHANICAL EFFICIENCY, OR FLUID PRESSURE
    • G01L11/00—Measuring steady or quasi-steady pressure of a fluid or a fluent solid material by means not provided for in group G01L7/00 or G01L9/00
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/06—Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
    • 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 invention relates to devices for monitoring gas pressure inside the sealed shell of fuel elements (fuel rods) and, in particular, can be used in the production of fuel rods for fuel assemblies of nuclear reactors.
  • Helium has high thermal conductivity, which allows for efficient heat transfer from the fuel to the cladding and the reactor coolant. Ensuring helium pressure in the fuel elements of the fuel assembly in accordance with the documentation requirements leads to equalization of thermal fields and reduces the likelihood of failures and emergency situations. High coolant pressure can lead to mechanical damage to the fuel element cladding in the compensation volume zone; helium pressure inside the fuel element helps prevent such accidents.
  • a device for monitoring gas pressure in a fuel element (FE) of a nuclear reactor which comprises a ring-shaped inductive heater (inductor), temperature sensors located on one side of the heater at a distance close to the diameter of the fuel element, on opposite generatrices of the fuel element shell coaxially perpendicular to the fuel element axis.
  • the device additionally includes heat-insulating pads between the temperature sensors in the thermal contact zone, the sensors have metal shoes in the form of rectangular copper plates bent along the radius of the surface generatrice of the fuel element shell, covered with an electrically insulating heat-conducting film, and elastic (for example, rubber) couplings, and there is also a device for rotating the fuel element by 180° relative to its longitudinal axis together with the inductor, sensors and heat-insulating pads (RU 2399970, published 20.09.2010).
  • the disadvantage of this device is the use of heat-insulating pads between the temperature sensors in the thermal contact zone and the metal shoes, which leads to a significant delay in heat transfer from the fuel element to the sensors and errors in temperature measurement due to the high heat capacity of the elements used.
  • the KDG-VVER gas pressure monitoring unit contains two replaceable measuring heads designed to monitor the gas pressure in fuel rods, metal collet clamps of the fuel rod cladding, an induction heating unit, temperature sensors, a motor for rotating the measuring heads, panels used for convenient dismantling and mounting of replaceable measuring heads, an electropneumatic automation unit, and an industrial computer.
  • the operating principle of the unit is based on the excitation of convective gas motion in the product and measuring the increment of the cladding temperature. Convective gas motion in the fuel rod is created by heating the annular region of the cladding in the area of the compensation volume.
  • the increment of the cladding temperature is converted into a change in the resistance of two thermistors (Operating Manual 2309-0048 RE, 2012).
  • the disadvantage of this installation is the need for additional installation work to replace one type of measuring head with another type.
  • Another disadvantage is the use of resistance thermometers placed in glass shells that have constant contact with the fuel element body, which increases the error in measuring the fuel element shell temperature.
  • a method for monitoring gas pressure in a fuel element of a nuclear reactor in which the fuel element is placed horizontally, inserted into a ring induction heater, a thermal pulse is generated that excites a convective flow of gas in the fuel element, the change in temperature is measured by temperature sensors pressed against the shell, and the gas pressure is calculated based on the magnitude of the change in temperature.
  • shoes and couplings are installed on the sensors, the sensors are pressed to the casing opposite to each other, one from above and the other from below, heat-insulating pads are installed between the sensors and the temperature difference shown by the sensors is measured, then a thermal pulse is applied and after a certain time tl the temperature difference is measured again, after which the fuel element is turned together with the pads, sensors and induction heater by an angle of 180° and after the turn the temperature difference is measured after a certain time t2, then a second thermal pulse is applied and the temperature difference is measured after time tl, then the fuel element is turned together with the pads, temperature sensors and induction heater by an angle of 180° back to the original position, the temperature difference is measured again after time t2, the cycle is repeated several times, after which the obtained results are mathematically processed, as a result of which the value of the gas pressure inside the fuel element is determined (RU 2408098, published on 27.12.2010).
  • the disadvantage of this method is that the temperature is measured by temperature sensors pressed against the shell, which can lead to gradual heating of the shoes and couplings installed on the sensors due to the heat capacity of the materials during the cyclic supply of thermal pulses. to the fuel element cladding and, consequently, to an increase in the error in measuring the gas pressure.
  • a method for monitoring gas pressure in a fuel element of a nuclear reactor which consists in applying a thermal pulse to the fuel element cladding, exciting a convective gas flow, and using sensors, measuring the cladding temperature increment corresponding to the convective component of heat transfer in the region of developed convective flow of gas filling the fuel element, by which the gas pressure is determined. Additionally, the cladding heating temperature is measured simultaneously with the measurement of the cladding temperature increment corresponding to the convective component of heat transfer, wherein both measurements are performed by the same temperature sensors, and the value of the gas pressure is determined taking into account the correction of the measured cladding temperature increment based on the results of monitoring the cladding heating temperature (RU 2109259, published 20.04.1998).
  • the disadvantage of this method is the need to introduce compensating corrections to the temperature measurement due to the increment of the half-sum of the fuel element cladding temperatures due to the wear of the contact pads during industrial vibrations in production conditions.
  • the objective of the invention is to create a device for operational monitoring of gas pressure inside the sealed casing of a fuel element, allowing the temperature of the fuel element casing to be determined in a contactless manner to prevent damage to it.
  • the technical result of the invention is: increasing the efficiency of the technological process and increasing the accuracy of measuring the gas pressure inside the sealed shell of the fuel element.
  • a device for monitoring the gas pressure inside the sealed shell of a nuclear fuel element a reactor that contains rollers located on a fixed frame for moving a fuel element with a compression and release mechanism, a stop for stopping the fuel element, a measuring unit located in the housing and rotating relative to the longitudinal axis of the fuel element, fuel element position sensors, one of which is located in front of the measuring unit, the other is located after the measuring unit, a control and data processing system.
  • the measuring unit contains clamps with elastic elements for fixing and centering the fuel element, pyrometers for contactless measurement of the fuel element temperature, one of which is located above the fuel element and the other is located under the fuel element, an inductor for heating the fuel element, and a ventilation system for cooling the fuel element in the period between temperature measurements.
  • the pyrometers are equipped with special glasses.
  • the ventilation system consists of nozzles that form a directed air flow around the fuel element in the measurement zone.
  • the measuring unit rotates relative to the longitudinal axis of the fuel element using a pneumatic rotation drive.
  • As a control and data processing system it contains a controller, where, according to a special algorithm, the measured temperature values are converted into the value of gas pressure in the fuel element.
  • Figure 1 shows the general diagram of the device.
  • Figure 2 shows the arrangement of optical pyrometers.
  • the operation of the device for monitoring the gas pressure inside the fuel element shell is based on measuring the shell temperature using non-contact optical pyrometers with the conversion of the fuel element shell temperature to the ambient temperature.
  • the loaded and sealed fuel element 1 is fed to the loading position in the device.
  • the rotating rollers 3 compress the fuel element and move it to the measuring unit 4.
  • the fuel element moves to the stop 5.
  • the fuel element is fixed by the centering clamps 7 with elastic elements 13, which ensure the fixation and centering of the fuel element in the measuring unit, and also prevent damage to the sealed fuel element shell.
  • the compression rollers 3 are unclenched.
  • the temperature of the fuel element shell surface at a given position is determined by the pyrometers through the built-in special glasses 11.
  • the inductor 8 at the signal from the controller, heats up the annular area of the shell and measures the temperature with the pyrometers 9.
  • the proposed device provides operational control of the gas pressure inside the sealed shell of the fuel element of a nuclear reactor, and also increases the measurement accuracy.

Landscapes

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

Abstract

L'invention concerne des dispositifs de contrôle de la pression de gaz dans l'enceinte étanche de pastilles de combustible, et peut notamment être utilisée dans la production de pastilles de combustible d'assemblages de réacteurs nucléaires. L'invention concerne un dispositif de contrôle de la pression de gaz dans l'enceinte étanche d'une pastille de combustible de réacteur nucléaire, qui comprend, disposés sur un cadre fixe, des galets de déplacement des pastilles de combustible avec un mécanisme de serrage et de relâchement, une butée d'arrêt des pastilles de combustible, une unité de mesure disposée dans le corps et tournant par rapport à l'axe longitudinal de la pastille de combustible, des capteurs de position de la pastille de combustible dont un est situé en amont de l'unité de mesure et l'autre est situé en aval de l'unité de mesure, et un système de commande et de traitement de données. L'unité de mesure comprend des pinces avec des éléments élastiques de fixation et de centrage de la pastille de combustible, des pyromètres pour la mesure sans contact de la température de la pastille de combustible dont un est disposé au-dessus de la pastille de combustible et l'autre en dessous de la pastille de combustible, un inducteur pour chauffer la pastille de combustible, un système de ventilation pour refroidir la pastille de combustible pendant une période entre les mesures de température. Le résultat technique de l'invention consiste en une augmentation de la capacité opérationnelle pour effectuer un processus industriel, et une augmentation de la précision de mesure de la pression de gaz dans l'enceinte étanche de la pastille de combustible.
PCT/RU2023/000386 2023-12-18 2023-12-18 Dispositif de contrôle de pression dans une pastille de combustible d'un réacteur nucléaire Pending WO2025136137A1 (fr)

Priority Applications (1)

Application Number Priority Date Filing Date Title
PCT/RU2023/000386 WO2025136137A1 (fr) 2023-12-18 2023-12-18 Dispositif de contrôle de pression dans une pastille de combustible d'un réacteur nucléaire

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
PCT/RU2023/000386 WO2025136137A1 (fr) 2023-12-18 2023-12-18 Dispositif de contrôle de pression dans une pastille de combustible d'un réacteur nucléaire

Publications (1)

Publication Number Publication Date
WO2025136137A1 true WO2025136137A1 (fr) 2025-06-26

Family

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Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/RU2023/000386 Pending WO2025136137A1 (fr) 2023-12-18 2023-12-18 Dispositif de contrôle de pression dans une pastille de combustible d'un réacteur nucléaire

Country Status (1)

Country Link
WO (1) WO2025136137A1 (fr)

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2109259C1 (ru) * 1996-03-27 1998-04-20 Акционерное общество открытого типа "Машиностроительный завод" Способ контроля давления газа в тепловыделяющем элементе ядерного реактора
RU2399970C2 (ru) * 2008-10-17 2010-09-20 Федеральное государственное унитарное предприятие "Всероссийский научно-исследовательский институт технической физики и автоматизации" Устройство контроля давления газа в тепловыделяющем элементе ядерного реактора
RU2401468C1 (ru) * 2009-11-24 2010-10-10 Открытое акционерное общество "Машиностроительный завод" Автоматизированная установка непрерывного контроля герметичности тепловыделяющих элементов специальной геометрии
RU2552526C1 (ru) * 2013-11-19 2015-06-10 Федеральное государственное унитарное предприятие "Российский федеральный ядерный центр-Всероссийский научно-исследовательский институт технической физики имени академика Е.И. Забабахина" Способ контроля тепловыделяющих элементов
CN109978866A (zh) * 2019-03-28 2019-07-05 中国核电工程有限公司 燃料芯块周面缺陷的在线检测装置和方法
RU2728013C1 (ru) * 2017-04-07 2020-07-28 Филип Моррис Продактс С.А. Система и способ проверки уровня заполнения части для хранения жидкости

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2109259C1 (ru) * 1996-03-27 1998-04-20 Акционерное общество открытого типа "Машиностроительный завод" Способ контроля давления газа в тепловыделяющем элементе ядерного реактора
RU2399970C2 (ru) * 2008-10-17 2010-09-20 Федеральное государственное унитарное предприятие "Всероссийский научно-исследовательский институт технической физики и автоматизации" Устройство контроля давления газа в тепловыделяющем элементе ядерного реактора
RU2401468C1 (ru) * 2009-11-24 2010-10-10 Открытое акционерное общество "Машиностроительный завод" Автоматизированная установка непрерывного контроля герметичности тепловыделяющих элементов специальной геометрии
RU2552526C1 (ru) * 2013-11-19 2015-06-10 Федеральное государственное унитарное предприятие "Российский федеральный ядерный центр-Всероссийский научно-исследовательский институт технической физики имени академика Е.И. Забабахина" Способ контроля тепловыделяющих элементов
RU2728013C1 (ru) * 2017-04-07 2020-07-28 Филип Моррис Продактс С.А. Система и способ проверки уровня заполнения части для хранения жидкости
CN109978866A (zh) * 2019-03-28 2019-07-05 中国核电工程有限公司 燃料芯块周面缺陷的在线检测装置和方法

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