WO2009018757A1 - Procédé de mesure de la réactivité d'un réacteur - Google Patents

Procédé de mesure de la réactivité d'un réacteur Download PDF

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Publication number
WO2009018757A1
WO2009018757A1 PCT/CN2008/071821 CN2008071821W WO2009018757A1 WO 2009018757 A1 WO2009018757 A1 WO 2009018757A1 CN 2008071821 W CN2008071821 W CN 2008071821W WO 2009018757 A1 WO2009018757 A1 WO 2009018757A1
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WIPO (PCT)
Prior art keywords
reactivity
reactor
rpn
dynamic response
neutron flux
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Ceased
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PCT/CN2008/071821
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English (en)
Chinese (zh)
Inventor
Guangming Cai
Chunyan Sheng
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Individual
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Publication of WO2009018757A1 publication Critical patent/WO2009018757A1/fr
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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
    • G21C17/104—Measuring reactivity
    • 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 present invention relates to the measurement of reactivity of a nuclear reactor by which reactor reactivity or effective multiplication coefficient can be obtained.
  • the reactivity measurement of the existing nuclear reactor uses the point reactor dynamic equation to solve the reactivity or effective multiplication coefficient, also known as the inverse dynamic method.
  • the point reactor dynamics equation is as follows:
  • n (t) is the time-dependent neutron density
  • p is the reactivity of the core
  • ⁇ ieff is the effective delayed neutron share of the i-th group
  • P eff eff '' is the decay constant of the i-th group of delayed-neutron precursor nucleuses
  • C, (0 is the nuclear density of the first group of precursors; for heavy water reactors, 15 groups of delayed neutron precursors are used;
  • s is the source of the external neutron.
  • the reactivity meter (or the reactivity meter calculation program) obtains the reactivity of the reactor by solving the point reactor dynamic equation, that is, the inverse dynamic method.
  • the above inverse dynamic method is a widely used reactive measurement method of the reactor reactivity measuring instrument reactivity meter.
  • the neutron flux at a level PWR general requirements above in the intermediate range current ⁇ 10-8
  • the above can guarantee the measurement accuracy. Summary of the invention
  • the signal I RPN of the external nuclear test system contains not only the signal generated by the neutron but also the noise generated by the ⁇ and the noise of the measurement system.
  • the noise generated by ⁇ and the noise of the measurement system are collectively referred to as ⁇ noise, then
  • dCjt) p m ⁇ - ⁇ + s (5) dt dt dt dt I
  • the dynamic response reactivity measurement method comprises the following steps:
  • the reactor can obtain the desired result by moving the control rod, that is, continuously inserting or withdrawing the control rod, and then keeping the rod position unchanged. When the rod position is unchanged, the reactive disturbance ends. It can also be achieved by moving the fuel assembly or moving the reflective layer.
  • the dynamic response reactivity measurement method provided by the present invention is based on the mature inverse dynamic method. Since the external neutron source S and ⁇ current have been considered, there is no requirement for the critical state of the reactor and the neutron flux level. Not only can the measurement accuracy of the reactivity be improved in a critical state, but the sub-criticality can be measured even in a sub-critical state. The measured reactivity has taken into account the effects of the external neutron source S and gamma noise, so the measurement accuracy is high. It can be applied to various stack types, with fast measurement speed, high precision, good operability and simple data processing.
  • the dynamic response reactivity measurement method can perform the reactivity measurement in the subcritical state; therefore, the reactor physical test originally required to be performed after the criticality of the reactor can be moved to the critical point, thereby reducing the time taken to overhaul the critical path. Increase the economic efficiency of nuclear power plants;
  • the traditional method is to use the countdown method to achieve criticality.
  • the countdown rate method can only predict the critical point and cannot obtain the reactivity (or subcriticality) of the core. If the traditional countdown method is used in combination with the dynamic response reactivity measurement method in the critical process of the rod, the reactivity (or subcriticality) of the core can be determined, so that the critical process of the reactor is safer. faster.
  • Figure 1 shows the response curve of the source range detector after the sub-critical lower rod
  • Step 1 According to actual needs, give the reactor a faster reactive disturbance to obtain a set of dynamic response neutron flux level measurement data I R p N .
  • Figure 1 shows the response curve of the source range detector after the sub-critical lower rod.
  • Reactivity (sub-criticality) measurements in subcritical conditions have been a difficulty in reactor reactivity measurements.
  • the present invention is illustrated by taking the reactivity measurement in the subcritical state as an example.
  • the reactor is inserted into the control rod at a faster rate, achieving faster reactive perturbations and then maintaining the rod position unchanged. No other reactive introductions were made during this time.
  • it is better to maintain more than 2 minutes to obtain a set of dynamic response neutron flux level measurement data I RPN and to make the neutron flux level below the zero power Doppler fever point.
  • the data can also be more than 2 minutes.
  • the neutron flux horizontal dynamic response curve A, C after the subcritical lower insert as shown in Fig. 1 is the control rod position.
  • the invention is based on an inverse dynamic dynamic response reactivity measurement method, and the reactivity (or subcriticality) of the reactor can be obtained by simple mathematical processing, and the influence of the external neutron source and the gamma current is considered. In addition to improving the critical state

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  • 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)

Abstract

La présente invention concerne un procédé de mesure de la réactivité d'un réacteur, comprenant les étapes suivantes : acquisition d'un jeu de données de mesure IRPN d'un niveau de flux neutronique à réponse dynamique ; calcul de dynamique inverse pour la mesure des données IRPN de ce niveau de flux neutronique sur la base de l'équation de la cinétique du cœur à base de points, et obtention d'une réactivité ρm ; ajustement linéaire ρm(IRPN-γ0)=f(IRPN) des données de réponse dynamique IRPN quand la réactivité se maintient à un état constant. La pente est la réactivité ρ.
PCT/CN2008/071821 2007-08-03 2008-07-30 Procédé de mesure de la réactivité d'un réacteur Ceased WO2009018757A1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
CN2007100940017A CN101105986B (zh) 2007-08-03 2007-08-03 反应堆反应性测量方法
CN200710094001.7 2007-08-03

Publications (1)

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WO2009018757A1 true WO2009018757A1 (fr) 2009-02-12

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PCT/CN2008/071821 Ceased WO2009018757A1 (fr) 2007-08-03 2008-07-30 Procédé de mesure de la réactivité d'un réacteur

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CN (1) CN101105986B (fr)
WO (1) WO2009018757A1 (fr)

Cited By (7)

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CN108198639A (zh) * 2017-12-13 2018-06-22 中国船舶重工集团公司第七〇九研究所 一种船用小堆堆外复用探测器、核测量系统和控制系统
CN111446014A (zh) * 2020-04-07 2020-07-24 中国核动力研究设计院 利用源量程探测器信号作为信号源的次临界刻棒方法
CN113161029A (zh) * 2021-03-19 2021-07-23 中国核动力研究设计院 一种基于采样信号变频分析的反应性测量方法
CN113161028A (zh) * 2021-03-19 2021-07-23 中国核动力研究设计院 一种基于修正信号优化处理的反应性测量方法
CN114242280A (zh) * 2021-11-17 2022-03-25 华能核能技术研究院有限公司 反应堆反应性测量方法、装置、设备及存储介质
CN116189941A (zh) * 2022-11-25 2023-05-30 中国核动力研究设计院 一种基于脉冲源的反应性参数的在线测量方法及系统
CN118942748A (zh) * 2023-05-11 2024-11-12 福建福清核电有限公司 使用堆外核仪表系统中间量程进行零功率物理试验的方法

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CN101105986B (zh) * 2007-08-03 2010-08-25 蔡光明 反应堆反应性测量方法
CN101252026B (zh) * 2008-03-25 2014-11-26 蔡光明 反应堆中子源和伽马噪声测量法
US7894565B2 (en) * 2008-12-11 2011-02-22 Westinghouse Electric Company Llc Subcritical reactivity measurement method
CN102800372B (zh) * 2012-08-17 2015-03-11 中国原子能科学研究院 一种反应堆反应性测量值的外源修正方法
CN105788666A (zh) * 2014-12-23 2016-07-20 福建福清核电有限公司 一种核反应堆临界过程控制方法
CN104934083A (zh) * 2015-04-27 2015-09-23 中国原子能科学研究院 一种测量缓发中子有效份额的方法
CN104898155B (zh) * 2015-05-26 2018-03-27 中国科学院合肥物质科学研究院 一种基于中子平均能量的次临界系统次临界度测量方法
CN105512386B (zh) * 2015-12-03 2018-08-07 中国原子能科学研究院 一种带有本底电流与源项电流修正的反应性测量方法
CN107688112B (zh) * 2016-08-05 2020-05-22 中核核电运行管理有限公司 一种快速测量压水堆动态刻棒修正电流的方法
CN107169207B (zh) * 2017-05-18 2020-06-23 中国工程物理研究院核物理与化学研究所 基于有限元理论的反应堆中子噪声频谱计算方法
CN107887043B (zh) * 2017-10-10 2019-09-17 福建福清核电有限公司 一种反应堆功率系数测量方法
CN109273119B (zh) * 2018-09-13 2022-02-11 中国核动力研究设计院 在临界装置上测量大反应性时优化中子探测器位置的方法
CN112687411B (zh) * 2020-12-24 2022-06-24 中国核动力研究设计院 一种基于多探测器接力信号的反应性测量方法
CN113241204A (zh) * 2021-05-19 2021-08-10 核星核电科技(海盐)有限公司 一种用于测试反应堆反应性仪的专用系统
CN113871040A (zh) * 2021-09-29 2021-12-31 福州奇正谷科技有限公司 一种带本底电流修正的反应性仪和系统
CN113936824B (zh) * 2021-10-12 2025-01-10 中国原子能科学研究院 反应堆反应性及次临界度的测量方法
CN114743701B (zh) * 2022-04-19 2025-03-18 华能山东石岛湾核电有限公司 一种高温气冷堆控制棒反应性价值测量的方法
CN117198573B (zh) * 2023-11-07 2024-03-01 福建福清核电有限公司 堆芯次临界度的修正方法、堆芯次临界刻棒方法及装置

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CN101105986A (zh) * 2007-08-03 2008-01-16 蔡光明 反应堆反应性测量方法
CN101252026A (zh) * 2008-03-25 2008-08-27 蔡光明 反应堆中子源和伽马噪声测量法

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Cited By (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108198639A (zh) * 2017-12-13 2018-06-22 中国船舶重工集团公司第七〇九研究所 一种船用小堆堆外复用探测器、核测量系统和控制系统
CN111446014A (zh) * 2020-04-07 2020-07-24 中国核动力研究设计院 利用源量程探测器信号作为信号源的次临界刻棒方法
CN113161029A (zh) * 2021-03-19 2021-07-23 中国核动力研究设计院 一种基于采样信号变频分析的反应性测量方法
CN113161028A (zh) * 2021-03-19 2021-07-23 中国核动力研究设计院 一种基于修正信号优化处理的反应性测量方法
CN114242280A (zh) * 2021-11-17 2022-03-25 华能核能技术研究院有限公司 反应堆反应性测量方法、装置、设备及存储介质
CN116189941A (zh) * 2022-11-25 2023-05-30 中国核动力研究设计院 一种基于脉冲源的反应性参数的在线测量方法及系统
CN118942748A (zh) * 2023-05-11 2024-11-12 福建福清核电有限公司 使用堆外核仪表系统中间量程进行零功率物理试验的方法
CN118942748B (zh) * 2023-05-11 2025-11-14 福建福清核电有限公司 使用堆外核仪表系统中间量程进行零功率物理试验的方法

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