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CN107863162B - The method that reactor is transformed into critical state from subcritical state - Google Patents

The method that reactor is transformed into critical state from subcritical state Download PDF

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CN107863162B
CN107863162B CN201711220893.0A CN201711220893A CN107863162B CN 107863162 B CN107863162 B CN 107863162B CN 201711220893 A CN201711220893 A CN 201711220893A CN 107863162 B CN107863162 B CN 107863162B
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beam intensity
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CN107863162A (en
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詹文龙
杨磊
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Institute of Modern Physics of CAS
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/06Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • G21C7/12Means for moving control elements to desired position
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

本发明的实施例公开了一种将反应堆从次临界状态转换到临界状态的方法,所述方法包括:束流强度降低步骤:将用于次临界状态下的反应堆的加速器的束流强度降低预定束流强度;第一控制棒调节步骤:调节第一控制棒在反应堆的堆芯内的长度;以及稳定工作步骤:使反应堆稳定工作预定时间,其中循环执行束流强度降低步骤、第一控制棒调节步骤和稳定工作步骤直到束流强度降低至预定值,所述方法还包括:切断加速器的束流;以及逐渐拔出第二控制棒,使反应堆反应性逐渐提升至预定反应性。采用本发明的实施例的方法,在不停堆的情况下实现了反应堆从次临界状态到临界状态的转换。

An embodiment of the present invention discloses a method for converting a reactor from a subcritical state to a critical state, the method comprising: a beam intensity reducing step: reducing the beam intensity of an accelerator for a reactor in a subcritical state by a predetermined beam intensity; a first control rod adjustment step: adjusting the length of the first control rod in the reactor core; and a stable operation step: making the reactor work stably for a predetermined time, wherein the beam intensity reduction step, the first control rod The adjusting step and the stabilizing working step are until the beam intensity decreases to a predetermined value, and the method further includes: cutting off the accelerator beam; and gradually pulling out the second control rod, so that the reactor reactivity is gradually increased to the predetermined reactivity. By adopting the method of the embodiment of the present invention, the transition of the reactor from the subcritical state to the critical state is realized without stopping the reactor.

Description

将反应堆从次临界状态转换到临界状态的方法Method for transitioning a reactor from a subcritical state to a critical state

技术领域technical field

本发明的实施例涉及一种将反应堆从次临界状态转换到临界状态的方法。Embodiments of the invention relate to a method of transitioning a reactor from a subcritical state to a critical state.

背景技术Background technique

加速器驱动的先进核能系统由加速器提供外源性中子,驱动反应堆在次临界运行。The accelerator-driven advanced nuclear energy system provides exogenous neutrons from the accelerator to drive the reactor to operate at subcritical.

发明内容Contents of the invention

本发明的实施例的目的是提供一种将反应堆从次临界状态转换到临界状态的方法,由此例如,在不停堆的情况下实现反应堆从次临界状态到临界状态的转换。It is an object of embodiments of the present invention to provide a method for transitioning a reactor from a subcritical state to a critical state, whereby, for example, the transition of a reactor from a subcritical state to a critical state is achieved without shutting down the reactor.

本发明的实施例提供了一种将反应堆从次临界状态转换到临界状态的方法,所述反应堆包括具有第一横截面面积的第一控制棒和具有小于第一横截面面积的第二横截面面积的第二控制棒,所述方法包括:束流强度降低步骤:将用于次临界状态下的反应堆的加速器的束流强度降低预定束流强度;第一控制棒调节步骤:调节第一控制棒在反应堆的堆芯内的长度;以及稳定工作步骤:使反应堆稳定工作预定时间,其中循环执行束流强度降低步骤、第一控制棒调节步骤和稳定工作步骤直到束流强度降低至预定值,所述方法还包括:切断加速器的束流;以及逐渐拔出第二控制棒,使反应堆反应性逐渐提升至预定反应性。Embodiments of the present invention provide a method of transitioning a reactor from a subcritical state to a critical state, the reactor comprising first control rods having a first cross-sectional area and a second cross-sectional area smaller than the first cross-sectional area area of the second control rod, the method comprising: a beam intensity reducing step: reducing the beam intensity of an accelerator for a reactor in a subcritical state to a predetermined beam intensity; a first control rod adjusting step: adjusting the first control rod the length of the rods in the core of the reactor; and a stabilizing operation step: stabilizing the reactor for a predetermined time, wherein the beam intensity reducing step, the first control rod adjusting step and the stabilizing operation step are cyclically performed until the beam intensity is reduced to a predetermined value, The method further includes: cutting off the beam current of the accelerator; and gradually pulling out the second control rod, so that the reactor reactivity is gradually increased to a predetermined reactivity.

根据本发明的实施例,调节第一控制棒在反应堆的堆芯内的长度包括将第一控制棒拔出预定距离。According to an embodiment of the present invention, adjusting the length of the first control rod within the core of the reactor includes pulling out the first control rod by a predetermined distance.

根据本发明的实施例,束流强度降低至预定值包括将用于次临界状态下的反应堆的加速器的额定束流强度在预定的时间内成阶梯状降低至预定值。According to an embodiment of the present invention, reducing the beam intensity to the predetermined value includes reducing the rated beam intensity of the accelerator for the reactor in the subcritical state to the predetermined value stepwise within a predetermined time.

根据本发明的实施例,调节第一控制棒在反应堆内的长度使反应堆的堆芯的温度的变化小于±5℃,反应性变化小于50pcm/小时,以及有效增殖因子keff<0.98。According to an embodiment of the present invention, the length of the first control rod in the reactor is adjusted so that the temperature variation of the reactor core is less than ±5° C., the reactivity variation is less than 50 pcm/hour, and the effective multiplication factor keff<0.98.

根据本发明的实施例,第一控制棒和第二控制棒具有圆形的横截面,并且第一控制棒的直径是第二控制棒的直径的1.5-2.5倍。According to an embodiment of the present invention, the first control rod and the second control rod have circular cross-sections, and the diameter of the first control rod is 1.5-2.5 times the diameter of the second control rod.

根据本发明的实施例,第一控制棒和第二控制棒具有大致相同的长度。According to an embodiment of the invention, the first control rod and the second control rod have substantially the same length.

根据本发明的实施例,束流强度降低至预定值包括将用于次临界状态下的反应堆的加速器的额定束流强度在多个均等的时间段分别降低等比例的束流强度值。According to an embodiment of the present invention, reducing the beam intensity to a predetermined value includes reducing the rated beam intensity of the accelerator for the reactor in the subcritical state by a proportional beam intensity value in a plurality of equal time periods.

根据本发明的实施例,所述预定距离为需要调节的反应堆的反应性的变化量与第一控制棒每移动单位距离引起的反应堆的堆芯的反应性的变化量的比值。According to an embodiment of the present invention, the predetermined distance is a ratio of a change in reactivity of the reactor that needs to be adjusted to a change in reactivity of the reactor core caused by moving the first control rod per unit distance.

根据本发明的实施例,在反应堆的功率降低到次临界状态下的反应堆的功率的预定百分比时切断加速器的束流。According to an embodiment of the invention, the accelerator beam is switched off when the power of the reactor is reduced to a predetermined percentage of the power of the reactor in a subcritical state.

根据本发明的实施例,所述预定百分比的范围是50%至70%。According to an embodiment of the present invention, the predetermined percentage ranges from 50% to 70%.

采用根据本发明的实施例的将反应堆从次临界状态转换到临界状态的方法,例如,在不停堆的情况下实现反应堆从次临界状态到临界状态的转换。Using the method for converting a reactor from a subcritical state to a critical state according to an embodiment of the present invention, for example, realizes the conversion of a reactor from a subcritical state to a critical state without stopping the reactor.

附图说明Description of drawings

图1是根据本发明的实施例的将反应堆从次临界状态转换到临界状态的方法的流程图;1 is a flowchart of a method of transitioning a reactor from a subcritical state to a critical state according to an embodiment of the present invention;

图2是根据本发明的实施例的加速器驱动的反应堆运行的流程图;Figure 2 is a flowchart of the operation of an accelerator-driven reactor according to an embodiment of the present invention;

图3为根据本发明实施例的束流强度减小方式的示意图;以及3 is a schematic diagram of a beam intensity reduction method according to an embodiment of the present invention; and

图4是根据本发明的实施例的反应堆堆芯结构图。Fig. 4 is a structural diagram of a reactor core according to an embodiment of the present invention.

具体实施方式Detailed ways

下面结合附图及具体实施方式对本发明做进一步说明。The present invention will be further described below in conjunction with the accompanying drawings and specific embodiments.

参见图1和图4,本发明的实施例提供了一种将反应堆从次临界状态转换到临界状态的方法。所述反应堆包括具有第一横截面面积的第一控制棒2和具有小于第一横截面面积的第二横截面面积的第二控制棒3。所述方法包括:束流强度降低步骤:将用于次临界状态下的反应堆的加速器的束流强度降低预定束流强度;第一控制棒2调节步骤:调节第一控制棒2在反应堆的堆芯1内的长度;以及稳定工作步骤:使反应堆稳定工作预定时间。循环执行束流强度降低步骤、第一控制棒2调节步骤和稳定工作步骤直到束流强度降低至预定值。即判断束流强度是否低于预定值,如果束流强度大于预定值,则返回到束流强度降低步骤,如果束流强度小于或等于预定值,则执行下面的步骤。所述方法还包括:切断加速器的束流;以及逐渐拔出第二控制棒3,使反应堆反应性逐渐提升至预定反应性。Referring to Figures 1 and 4, an embodiment of the present invention provides a method for transitioning a reactor from a subcritical state to a critical state. The reactor comprises first control rods 2 having a first cross-sectional area and second control rods 3 having a second cross-sectional area smaller than the first cross-sectional area. The method includes: a beam intensity reducing step: reducing the beam intensity of an accelerator for a reactor in a subcritical state to a predetermined beam intensity; a first control rod 2 adjusting step: adjusting the first control rod 2 in the reactor stack The length inside the core 1; and the step of stabilizing operation: making the reactor stably operate for a predetermined time. The step of reducing the beam current intensity, the step of adjusting the first control rod 2 and the step of stabilizing the work are executed cyclically until the beam current intensity is reduced to a predetermined value. That is, it is judged whether the beam intensity is lower than the predetermined value, if the beam intensity is greater than the predetermined value, then return to the beam intensity reduction step, and if the beam intensity is less than or equal to the predetermined value, then perform the following steps. The method further includes: cutting off the beam current of the accelerator; and gradually pulling out the second control rod 3 to gradually increase the reactor reactivity to a predetermined reactivity.

根据本发明的实施例,调节第一控制棒2在反应堆的堆芯1内的长度包括将第一控制棒2拔出预定距离。所述预定距离为需要调节的反应堆的反应性的变化量与第一控制棒2每移动单位距离引起的反应堆的堆芯1的反应性的变化量的比值。根据本发明的示例,调节第一控制棒2在反应堆内的长度使反应堆的堆芯1的温度的变化小于±5℃,反应性变化小于50pcm/小时,以及有效增殖因子keff<0.98。According to an embodiment of the present invention, adjusting the length of the first control rod 2 inside the reactor core 1 includes pulling out the first control rod 2 by a predetermined distance. The predetermined distance is a ratio of a change in reactivity of the reactor to be adjusted to a change in reactivity of the reactor core 1 caused by moving the first control rod 2 per unit distance. According to an example of the present invention, the length of the first control rod 2 in the reactor is adjusted so that the temperature variation of the reactor core 1 is less than ±5° C., the reactivity variation is less than 50 pcm/hour, and the effective multiplication factor keff<0.98.

根据本发明的实施例,束流强度降低至预定值包括将用于次临界状态下的反应堆的加速器的额定束流强度在预定的时间内成阶梯状降低至预定值。例如,束流强度降低至预定值包括将用于次临界状态下的反应堆的加速器的额定束流强度在多个均等的时间段分别降低等比例的束流强度值。根据本发明的实施例,在束流强度降低步骤中,将用于次临界状态下的反应堆的加速器的束流强度降低预定束流强度,并且循环执行束流强度降低步骤、第一控制棒调节步骤和稳定工作步骤直到束流强度降低至预定值。在循环执行束流强度降低步骤、第一控制棒调节步骤和稳定工作步骤时,预定束流强度所有循环中可以是不同的,也可以是相同的。例如,预定束流强度是成递减的方式或等比例地逐步降低的。According to an embodiment of the present invention, reducing the beam intensity to the predetermined value includes reducing the rated beam intensity of the accelerator for the reactor in the subcritical state to the predetermined value stepwise within a predetermined time. For example, reducing the beam intensity to a predetermined value includes reducing the rated beam intensity of the accelerator for the reactor in the subcritical state by a proportional beam intensity value respectively in a plurality of equal time periods. According to an embodiment of the present invention, in the beam intensity reducing step, the beam intensity of the accelerator for the reactor in the subcritical state is reduced by a predetermined beam intensity, and the beam intensity reducing step, the first control rod adjustment Steps and steady work steps until the beam intensity decreases to a predetermined value. When the beam current intensity reduction step, the first control rod adjustment step and the stable working step are cyclically executed, the predetermined beam current intensity can be different or the same in all cycles. For example, the predetermined beam intensity is gradually reduced in a decreasing manner or proportionally.

根据本发明的实施例,第一控制棒2和第二控制棒3具有圆形的横截面,并且第一控制棒2的直径是第二控制棒3的直径的1.5-2.5倍。第一控制棒2和第二控制棒3可以具有大致相同的长度。According to an embodiment of the present invention, the first control rod 2 and the second control rod 3 have a circular cross-section, and the diameter of the first control rod 2 is 1.5-2.5 times the diameter of the second control rod 3 . The first control rod 2 and the second control rod 3 may have approximately the same length.

根据本发明的实施例,在反应堆的功率降低到次临界状态下的反应堆的功率的预定百分比时切断加速器的束流。所述预定百分比的范围可以是50%至70%。According to an embodiment of the invention, the accelerator beam is switched off when the power of the reactor is reduced to a predetermined percentage of the power of the reactor in a subcritical state. The predetermined percentage may range from 50% to 70%.

根据本发明的实施例提供了一种反应堆从次临界状态到临界状态转换的方法,可以用于先进核能系统中燃烧器子系统(包括反应堆)在不停堆的情况下从次临界状态向临界状态的转换。该转换方法包括以下步骤:(1)减小束流,(2)调节控制棒。控制棒分为第一控制棒2和第二控制棒3,两种控制棒的移动策略与束流的减少策略可以根据以下几点确定:(1)次临界堆反应性限制(转换期内,反应堆的反应性变化小于50pcm/小时);(2)堆芯功率的稳定性限制(在转换期内堆的功率变化小于5%初始功率);(3)结构材料与燃料的热冲击限制(温度变化速率小于60℃/小时)。According to an embodiment of the present invention, a method for transitioning a reactor from a subcritical state to a critical state is provided, which can be used for a burner subsystem (including a reactor) in an advanced nuclear energy system to go from a subcritical state to a critical state without shutting down the reactor. State transitions. The conversion method includes the following steps: (1) reducing the beam current, (2) adjusting the control rod. The control rods are divided into the first control rod 2 and the second control rod 3. The moving strategies of the two control rods and the beam current reduction strategies can be determined according to the following points: (1) The reactivity limit of the subcritical reactor (during the transition period, The reactivity change of the reactor is less than 50pcm/hour); (2) the stability limit of the core power (the power change of the reactor during the conversion period is less than 5% of the initial power); (3) the thermal shock limit of the structural material and fuel (temperature The rate of change is less than 60°C/hour).

根据本发明的实施例,加速器驱动的先进核能系统由加速器提供外源性中子,驱动反应堆在次临界运行,运行3-5年后在不停堆的情况下切断其外部驱动,反应堆过渡成临界状态运行。According to an embodiment of the present invention, the accelerator-driven advanced nuclear energy system provides exogenous neutrons from the accelerator to drive the reactor to operate at subcriticality. After 3-5 years of operation, the external drive is cut off without stopping the reactor, and the reactor transitions to critical state operation.

根据本发明的实施例的反应堆从次临界状态到临界状态转换的方法主要用于解决加速器驱动先进核能系统中燃烧器子系统在不停堆的情况下从次临界状态向临界状态转换的问题。The method for transitioning a reactor from a subcritical state to a critical state according to an embodiment of the present invention is mainly used to solve the problem that a burner subsystem in an accelerator-driven advanced nuclear energy system transitions from a subcritical state to a critical state without stopping the reactor.

根据本发明的实施例,加速器驱动的先进核能系统主要包括:燃烧器子系统(包括反应堆)和核燃料再生后处理子系统。燃烧器子系统包括强流超导直线加速器、高功率散裂中子靶及高温快反应堆等。初装堆时,整个核能系统需要利用超导直线强流质子加速器对反应堆进行外源性驱动,燃烧器进行燃烧增殖,并产能,此时本系统运行在次临界状态下;在此状态下运行3~5年后,在不停堆的情况下切断超导直线强流质子加速器,停止燃烧器的外部中子源驱动,燃烧器此后转变为自持燃烧状态,本系统即在临界状态下运行。According to an embodiment of the present invention, the accelerator-driven advanced nuclear energy system mainly includes: a burner subsystem (including a reactor) and a nuclear fuel regenerative post-processing subsystem. The burner subsystem includes a high-current superconducting linear accelerator, a high-power spallation neutron target, and a high-temperature fast reactor. When the reactor is first installed, the entire nuclear energy system needs to use the superconducting linear strong current proton accelerator to drive the reactor exogenously, and the burner to burn and proliferate to increase production capacity. At this time, the system operates in a subcritical state; it operates in this state After 3 to 5 years, the superconducting linear high-current proton accelerator is cut off under the condition of non-stop stacking, and the drive of the external neutron source of the burner is stopped. After that, the burner turns into a self-sustained combustion state, and the system operates in a critical state.

根据本发明的实施例,加速器驱动的先进核能系统中燃烧器子系统运行的大致过程如图2所示:(1)颗粒注入,流动预热。初装堆时,作为中子靶、冷却剂的固体颗粒需要从外界注入反应堆内部,在注入过程中颗粒一边流动一边预热,预热的工作在颗粒存储装置中完成,预热后的颗粒将热量传递给反应堆,当反应堆内部温度平衡时停止预热。(2)控制棒就位,使反应堆初始反应性控制在0.96~0.98之间。第一控制棒2完全拔出,第二控制棒3部分插入,第二控制棒3插入部分的价值为βeff~2βeffeff为缓发中子份额)。第一控制棒2用于:1、反应堆次临界运行阶段的反应性控制;2、联合第二控制棒3在反应堆次临界到临界过程中进行转换;3、反应堆临界运行时用作安全棒。第二控制棒3用于:1、控制反应堆次临界到临界的转换;2、控制反应堆在临界状态下的反应性。(3)加束流。一切准备就绪后,超导直线强流质子加速器开始产生质子束,产生的束流轰击在颗粒靶上,驱动燃烧器进行燃烧。(4)正常次临界反应堆工况。反应堆启动后,由于反应堆的反应性存在阶段变化,此时需要交替调节第一控制棒2和束流强度,使反应堆反应性及功率维持在安全阈值内,系统稳定运行在正常的次临界反应堆工况下。此时第一控制棒2已插入反应堆中一定距离。(5)次临界——临界转换。当反应堆运行3至5年,反应堆的反应性达到一定的阈值且运行稳定后,超导直线强流质子加速器切断其对燃烧器的外部中子源驱动,第一控制棒2和第二控制棒3配合作用使得反应堆的反应性处于临界状态。(6)正常临界反应堆工况运行。燃烧器完全转变为自持燃烧状态后,本系统即为在临界状态下运行,临界状态完全由反应堆中的第二控制棒3对反应性进行控制,第一控制棒2的功能则变为安全棒。(7)停堆。当反应堆运行30-50年后,核燃料燃烧到一定程度反应堆需要停堆处理,即将堆芯内的燃料组件拆卸出来,运送至核燃料再生后处理子系统进行核燃料的处理。(8)冷却剂停止与排出。虽然反应堆停止工作,但其内部的温度还是非常高,冷却剂颗粒仍需要循环流动将热量带走,当反应堆内部温度达到指定值后颗粒冷却剂才能停止流动并排出至指定的容器。According to the embodiment of the present invention, the general operation process of the burner subsystem in the accelerator-driven advanced nuclear energy system is shown in Figure 2: (1) Particle injection, flow preheating. When the reactor is initially installed, solid particles used as neutron targets and coolant need to be injected into the reactor from the outside. During the injection process, the particles flow while being preheated. The preheating work is completed in the particle storage device. The preheated particles will Heat is transferred to the reactor, and the preheating is stopped when the temperature inside the reactor equilibrates. (2) The control rods are in place, so that the initial reactivity of the reactor is controlled between 0.96 and 0.98. The first control rod 2 is completely pulled out, the second control rod 3 is partially inserted, and the value of the inserted part of the second control rod 3 is β eff ~ 2β effeff is the proportion of delayed neutrons). The first control rod 2 is used for: 1. Reactivity control during the subcritical operation stage of the reactor; 2. Combined with the second control rod 3 to switch from the subcritical to critical process of the reactor; 3. Used as a safety rod during the critical operation of the reactor. The second control rod 3 is used for: 1. controlling the transition of the reactor from subcritical to critical; 2. controlling the reactivity of the reactor in the critical state. (3) Add beam current. After everything is ready, the superconducting linear high-current proton accelerator starts to generate proton beams, and the generated beams bombard the particle targets to drive the burners for combustion. (4) Normal subcritical reactor operating conditions. After the reactor is started, due to the staged changes in the reactivity of the reactor, it is necessary to alternately adjust the first control rod 2 and the beam intensity at this time, so that the reactivity and power of the reactor can be maintained within the safety threshold, and the system can operate stably under normal subcritical reactor conditions Down. At this moment, the first control rod 2 has been inserted into the reactor for a certain distance. (5) Subcritical-critical transition. When the reactor has been in operation for 3 to 5 years, and the reactivity of the reactor reaches a certain threshold and the operation is stable, the superconducting linear high-current proton accelerator cuts off its external neutron source drive to the burner, and the first control rod 2 and the second control rod 3 Synergy makes the reactivity of the reactor critical. (6) Operation of normal critical reactor conditions. After the burner is completely transformed into a self-sustained combustion state, the system operates in a critical state, and the critical state is completely controlled by the second control rod 3 in the reactor, and the function of the first control rod 2 becomes a safety rod . (7) shutdown. After the reactor has been in operation for 30-50 years, when the nuclear fuel burns to a certain extent, the reactor needs to be shut down for processing, that is, the fuel assembly in the core is disassembled and transported to the nuclear fuel regeneration post-processing subsystem for nuclear fuel processing. (8) The coolant is stopped and discharged. Although the reactor stops working, the internal temperature is still very high, and the coolant particles still need to circulate to take away the heat. When the internal temperature of the reactor reaches the specified value, the particle coolant can stop flowing and be discharged to the designated container.

反应堆次临界到临界的转换需要一个过程,本发明的一个示例提出了一种转换的方法,具体步骤为:Reactor subcritical to critical conversion needs a process, an example of the present invention proposes a method for conversion, the specific steps are:

(1)减小束流:将次临界反应堆中加速器额定束流强度I0在h时间内(h≤30天)成阶梯状降低至I0倍,50≤Z≤100,即如图3所示,前后时间段束流下降强度存在如下关系:其中W为划分的时间段数,即设定将束流强度从I0降低到需要W次完成,W≥15,每段时间均等,时长均为t,Ikt为kt时刻的束流强度,I(k-1)t为(k-1)t时刻的束流强度,(k=1,2,3……W),其单位均为mA。(1) Reduce the beam current: reduce the rated beam intensity I 0 of the accelerator in the subcritical reactor to I 0 in a stepwise manner within h (h ≤ 30 days) times, 50≤Z≤100, that is, as shown in Figure 3, there is the following relationship between the beam current drop intensity before and after the time period: Where W is the number of divided time periods, that is, it is set to reduce the beam intensity from I 0 to It needs W times to complete, W≥15, each period is equal, and the duration is t, I kt is the beam intensity at time kt, I (k-1)t is the beam intensity at time (k-1)t, (k=1, 2, 3...W), and the unit is mA.

(2)调节第一控制棒2:如图4所示,反应堆堆芯1中的第一控制棒2与第二控制棒3的长度相同,与反应堆堆芯1高度一致,第一控制棒2的直径约是第二控制棒3的1.5-2.5倍,二者可以使用相同的材料,如碳化硼、镉、银铟镉等。当束流减小时,散裂靶产生的中子会减少,反应堆的反应性、温度等参数会降低,但实际情况必须保证反应堆的反应性维持在正常工况,即反应堆内部的温度基本保持在小范围内波动,其温度变化波动小于±5℃,反应性变化小于50pcm/小时,有效增殖因子keff<0.98。这就需要在减小束流的同时,缓慢调节第一控制棒2,第一控制棒2的抽出会提高反应性,插入会抑制反应性。(2) Adjust the first control rod 2: as shown in Figure 4, the length of the first control rod 2 in the reactor core 1 is the same as that of the second control rod 3, which is consistent with the height of the reactor core 1, and the first control rod 2 The diameter of the second control rod 3 is about 1.5-2.5 times, and both can use the same material, such as boron carbide, cadmium, silver indium cadmium and the like. When the beam current decreases, the neutrons produced by the spallation target will decrease, and the reactor's reactivity, temperature and other parameters will decrease. Fluctuates within a small range, the temperature fluctuation is less than ±5°C, the reactivity change is less than 50pcm/hour, and the effective proliferation factor keff is less than 0.98. This requires slowly adjusting the first control rod 2 while reducing the beam current, the withdrawal of the first control rod 2 will increase the reactivity, and the insertion will inhibit the reactivity.

每次束流下降完成后,系统会实时测得并计算出反应堆内的实际反应性与设定的安全阈值的差值ρx,之后对第一控制棒2进行调节,以做出相当于ρx反应性变化量的控制。第一控制棒2的移动距离可根据以下公式计算得出:其中,HX为第一控制棒2需要移动的距离;ρx为实际需要调节的反应堆内反应性的变化量;ρ0为实验测得参数,代表该类型控制棒每移动单位距离(每厘米)引起的反应堆内反应性的变化量;H0为初始基准距离(根据实际需求,人为在第一控制棒2上设定一个位置为初始位置,在计算时各参数以这一初始位置为基准进行计算)。计算出第一控制棒2移动的距离后,对第一控制棒2进行调节,将反应堆内部的反应性、温度等参数调节到正常范围内。After each beam descent is completed, the system will measure and calculate the difference ρ x between the actual reactivity in the reactor and the set safety threshold in real time, and then adjust the first control rod 2 to make a value equivalent to ρ Control of the amount of change in x reactivity. The moving distance of the first control rod 2 can be calculated according to the following formula: Among them, HX is the distance that the first control rod 2 needs to move; ρ x is the amount of change in reactivity in the reactor that actually needs to be adjusted; ρ 0 is the parameter measured by the experiment, representing the unit distance (per centimeter) of movement of this type of control rod The amount of change in reactivity in the reactor caused by H0 is the initial reference distance (according to actual needs, a position is artificially set on the first control rod 2 as the initial position, and each parameter is based on this initial position during calculation. calculate). After the moving distance of the first control rod 2 is calculated, the first control rod 2 is adjusted to adjust the parameters such as reactivity and temperature inside the reactor within the normal range.

(3)稳定降低堆芯功率。当减小束流、调节第一控制棒2后,系统需要进行一定时间的稳定工作,当各项参数均处于正常工况后,才能再次减小束流,并重复上述对第一控制棒2的调节过程,即循环执行步骤(1)、(2)、(3),直至束流强度降低至此时反应堆进入亚临界状态,堆芯功率降低到次临界功率的60%左右。(3) Decrease the core power steadily. After reducing the beam current and adjusting the first control rod 2, the system needs to work stably for a certain period of time. When all parameters are in normal working conditions, the beam current can be reduced again, and repeat the above-mentioned adjustment of the first control rod 2 The adjustment process, that is, the steps (1), (2), and (3) are executed cyclically until the beam intensity is reduced to At this time, the reactor enters a subcritical state, and the core power is reduced to about 60% of the subcritical power.

(4)调节第二控制棒3。亚临界状态是处于次临界与临界之间的短暂过渡状态,此时堆芯反应性约为1-βeff,待堆芯状态稳定之后,切断加速器束流,束流强度由立刻降至0;随后,第二控制棒3开始拔出,在2小时内使反应堆反应性慢慢从1-βeff提升至1~1+βeff。堆芯自此进入临界模式运行,当堆芯功率由60%左右的额定功率升至100%额定功率时,堆芯完全过渡到正常临界运行状态。在临界状态下,反应堆反应性的调节由第二控制棒3来完成,第一控制棒2的功能则变为安全棒。(4) Adjust the second control rod 3 . The subcritical state is a short transition state between subcritical and critical. At this time, the core reactivity is about 1-β eff . After the core state is stable, the accelerator beam is cut off, and the beam intensity is determined by It immediately dropped to 0; then, the second control rod 3 began to be pulled out, and the reactor reactivity was slowly increased from 1-β eff to 1~1+β eff within 2 hours. Since then, the core has entered critical mode operation, and when the power of the core rises from about 60% of the rated power to 100% of the rated power, the core completely transitions to the normal critical operating state. In the critical state, the adjustment of reactor reactivity is accomplished by the second control rod 3, and the function of the first control rod 2 becomes a safety rod.

本发明的实施例提出的转换方法,能够安全有效地实现先进核能系统中燃烧器子系统从次临界状态向临界状态的转换,使反应堆内部处于正常工况。The conversion method proposed by the embodiment of the present invention can safely and effectively realize the conversion of the burner subsystem in the advanced nuclear energy system from the subcritical state to the critical state, so that the inside of the reactor is in a normal working condition.

尽管描述了上述的各种实施例,但是本发明的实施例的方法可以用于任何合适的加速器驱动的次临界状态下的反应堆向临界状态的转换。此外,尽管描述了各种数值范围以及指定值,但是这些数值范围以及指定值可以根据实际的条件进行调整。While various embodiments have been described above, the methods of embodiments of the present invention may be used for any suitable accelerator-driven transition of a subcritical to critical state reactor. Furthermore, although various numerical ranges and specified values are described, these numerical ranges and specified values may be adjusted according to actual conditions.

Claims (10)

1.一种将反应堆从次临界状态转换到临界状态的方法,所述反应堆包括具有第一横截面面积的第一控制棒和具有小于第一横截面面积的第二横截面面积的第二控制棒,1. A method of transitioning a reactor from a subcritical state to a critical state, the reactor comprising first control rods having a first cross-sectional area and second control rods having a second cross-sectional area less than the first cross-sectional area Great, 所述方法包括:The methods include: 束流强度降低步骤:将用于次临界状态下的反应堆的加速器的束流强度降低预定束流强度;A beam intensity reducing step: reducing the beam intensity of the accelerator for the reactor in the subcritical state by a predetermined beam intensity; 第一控制棒调节步骤:调节第一控制棒在反应堆的堆芯内的长度;以及The first control rod adjusting step: adjusting the length of the first control rod in the core of the reactor; and 稳定工作步骤:使反应堆稳定工作预定时间,Stable work steps: make the reactor work stably for a predetermined time, 其中循环执行束流强度降低步骤、第一控制棒调节步骤和稳定工作步骤直到束流强度降低至预定值,wherein the beam intensity reduction step, the first control rod adjustment step and the stabilization work step are executed cyclically until the beam intensity is reduced to a predetermined value, 所述方法还包括:The method also includes: 切断加速器的束流;以及cut off the accelerator beam; and 逐渐拔出第二控制棒,使反应堆反应性逐渐提升至预定反应性。Gradually pull out the second control rod to gradually increase the reactor reactivity to the predetermined reactivity. 2.根据权利要求1所述的将反应堆从次临界状态转换到临界状态的方法,其中2. The method of transitioning a reactor from a subcritical state to a critical state according to claim 1, wherein 调节第一控制棒在反应堆的堆芯内的长度包括将第一控制棒拔出预定距离。Adjusting the length of the first control rod within the core of the reactor includes pulling out the first control rod by a predetermined distance. 3.根据权利要求1所述的将反应堆从次临界状态转换到临界状态的方法,其中3. The method of transitioning a reactor from a subcritical state to a critical state according to claim 1, wherein 束流强度降低至预定值包括将用于次临界状态下的反应堆的加速器的额定束流强度在预定的时间内成阶梯状降低至预定值。Decreasing the beam intensity to a predetermined value includes decreasing the rated beam intensity of the accelerator for the reactor in the subcritical state stepwise to the predetermined value within a predetermined time. 4.根据权利要求1所述的将反应堆从次临界状态转换到临界状态的方法,其中4. The method of transitioning a reactor from a subcritical state to a critical state according to claim 1 , wherein 调节第一控制棒在反应堆内的长度使反应堆的堆芯的温度的变化小于±5℃,反应性变化小于50pcm/小时,以及有效增殖因子keff<0.98。Adjusting the length of the first control rod in the reactor makes the change of the core temperature of the reactor less than ±5°C, the change of reactivity less than 50 pcm/hour, and the effective multiplication factor keff<0.98. 5.根据权利要求1所述的将反应堆从次临界状态转换到临界状态的方法,其中5. The method of transitioning a reactor from a subcritical state to a critical state according to claim 1, wherein 第一控制棒和第二控制棒具有圆形的横截面,并且第一控制棒的直径是第二控制棒的直径的1.5-2.5倍。The first control rod and the second control rod have circular cross-sections, and the diameter of the first control rod is 1.5-2.5 times the diameter of the second control rod. 6.根据权利要求1或5所述的将反应堆从次临界状态转换到临界状态的方法,其中6. A method of transitioning a reactor from a subcritical state to a critical state according to claim 1 or 5, wherein 第一控制棒和第二控制棒具有大致相同的长度。The first control rod and the second control rod have approximately the same length. 7.根据权利要求1所述的将反应堆从次临界状态转换到临界状态的方法,其中7. The method of transitioning a reactor from a subcritical state to a critical state according to claim 1, wherein 束流强度降低至预定值包括将用于次临界状态下的反应堆的加速器的额定束流强度在多个均等的时间段分别降低等比例的束流强度值。Reducing the beam intensity to a predetermined value includes reducing the rated beam intensity of the accelerator for the reactor in the subcritical state by a proportional beam intensity value respectively in a plurality of equal time periods. 8.根据权利要求2所述的将反应堆从次临界状态转换到临界状态的方法,其中8. The method of transitioning a reactor from a subcritical state to a critical state according to claim 2, wherein 所述预定距离为需要调节的反应堆的反应性的变化量与第一控制棒每移动单位距离引起的反应堆的堆芯的反应性的变化量的比值。The predetermined distance is a ratio of a change in reactivity of the reactor that needs to be adjusted to a change in reactivity of the reactor core caused by moving the first control rod per unit distance. 9.根据权利要求1所述的将反应堆从次临界状态转换到临界状态的方法,其中9. The method of transitioning a reactor from a subcritical state to a critical state according to claim 1, wherein 在反应堆的功率降低到次临界状态下的反应堆的功率的预定百分比时切断加速器的束流。The accelerator beam is switched off when the power of the reactor is reduced to a predetermined percentage of the power of the reactor in subcritical conditions. 10.根据权利要求9所述的将反应堆从次临界状态转换到临界状态的方法,其中10. The method of transitioning a reactor from a subcritical state to a critical state according to claim 9, wherein 所述预定百分比的范围是50%至70%。The predetermined percentage ranges from 50% to 70%.
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