CN110781593A - Characterization method of neutron-photon energy spectrum in self-powered neutron detector - Google Patents
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Abstract
Translated fromChinese
Description
Translated fromChinese技术领域technical field
本发明涉及核反应堆堆内检测系统的理论模拟领域，具体涉及一种自给能中子探测器内中子-光子能谱的表征方法。The invention relates to the field of theoretical simulation of a detection system in a nuclear reactor, in particular to a method for characterizing a neutron-photon energy spectrum in a self-sufficient neutron detector.
背景技术Background technique
为了保障反应堆堆芯的安全、提高反应堆的经济效益，需要对反应堆堆芯的安全指标进行模拟监测。其中中子通量密度是反应堆内一个重要参数指标，它能至关地反应反应堆的功率水平和反应堆的工作状态，也是反应堆控制的一个至关重要的指标。一般需要中子探测器来监测堆内的中子通量密度。In order to ensure the safety of the reactor core and improve the economic benefits of the reactor, it is necessary to simulate and monitor the safety indicators of the reactor core. Among them, the neutron flux density is an important parameter index in the reactor, which is related to the power level of the reactor and the working state of the reactor, and is also a crucial index of the reactor control. Neutron detectors are generally required to monitor the neutron flux density within the reactor.
根据探测器的原理和材料的不同，中子探测器有气体探测器、闪烁体探测器、半导体探测器和自给能中子探测器。反应堆堆内环境具有高温、高湿、高压、强腐蚀、强射线干扰等特征，这就要求堆内中子探测器必须适应这种环境才能正常和长期工作。自给能中子探测器是一种不需要外加偏压电源的中子探测器。该类型探测器的灵敏度相对其他类型探测器的灵敏度较低。但是，和其他类型探测器相比，该类型探测器更能适应强辐射的工作环境。在理论计算过程中，正确模拟获得堆内中子自给能探测器的电流响应就显得至关重要。According to the principle and material of the detector, neutron detectors include gas detectors, scintillator detectors, semiconductor detectors and self-sufficient neutron detectors. The internal environment of the reactor has the characteristics of high temperature, high humidity, high pressure, strong corrosion, strong ray interference, etc., which requires that the neutron detector in the reactor must adapt to this environment in order to work normally and for a long time. A self-sufficient neutron detector is a neutron detector that does not require an external bias power supply. The sensitivity of this type of detector is lower than that of other types of detectors. However, compared with other types of detectors, this type of detector is more suitable for the working environment of strong radiation. In the process of theoretical calculation, it is very important to correctly simulate and obtain the current response of the neutron self-sustaining detector in the reactor.
为了获得堆内自给能中子探测器的响应，需要根据堆芯状态提供自给能探测器附近的中子-光子信息用于自给能探测器的响应模拟。足够精细的能群结构可以充分描述自给能探测器附近的中子-光子信息，但是确定论方法只能提供多群能谱，无法得到连续能谱，同时由于蒙特卡洛方法的统计方差导致在统计方差范围内只能得到多群能谱，无法获得连续谱，因此为了获得足够精度的中子-光子能群结构同时用于确定论方法和蒙特卡洛方法以模拟堆内自给能探测器响应，就需要评估出合适的中子-光子能群结构。基于压水堆中常用的3类中子能群结构(69群、173群、361群)和3类光子能群结构(18群、20群、48群)，使用蒙特卡洛方法获得中子-光子能谱用于自给能探测器的中子灵敏度和光子灵敏度计算，并在统计方差范围内加密中子-光子能群结构获得足够精细的能群作为中子-光子灵敏度计算的参考值，从而确定同时适合确定论方法和蒙特卡洛方法的中子-光子能群结构。In order to obtain the response of the self-powered neutron detector in the stack, it is necessary to provide the neutron-photon information near the self-powered detector according to the core state for the response simulation of the self-powered detector. A sufficiently fine energy group structure can fully describe the neutron-photon information near the self-sufficient energy detector, but the deterministic method can only provide a multi-group energy spectrum and cannot obtain a continuous energy spectrum. At the same time, due to the statistical variance of the Monte Carlo method, the In the range of statistical variance, only multi-group energy spectrum can be obtained, and continuous spectrum cannot be obtained. Therefore, in order to obtain the neutron-photon energy group structure with sufficient accuracy, both deterministic method and Monte Carlo method are used to simulate the response of the self-sufficient energy detector in the stack. , it is necessary to evaluate the appropriate neutron-photon energy group structure. Based on three types of neutron energy group structures (69, 173, 361) and three types of photon energy groups (18, 20, 48) commonly used in pressurized water reactors, the Monte Carlo method is used to obtain neutrons - The photon energy spectrum is used for the calculation of neutron sensitivity and photon sensitivity of self-sufficient energy detectors, and the neutron-photon energy group structure is encrypted within the range of statistical variance to obtain a sufficiently fine energy group as a reference value for the calculation of neutron-photon sensitivity, Thus, the neutron-photon energy group structure suitable for both the deterministic method and the Monte Carlo method is determined.
发明内容SUMMARY OF THE INVENTION
为了克服上述现有技术存在的问题，本发明的目的在于提供一种自给能探测器内中子-光子能谱的表征方法，应用在堆内自给能探测器附近中子-光子能谱计算中，通过与加密后的中子-光子能谱模拟获得的中子-光子灵敏度进行对比获得最优的中子-光子能群结构，使得其同时适用于确定论方法和蒙特卡洛方法的自给能探测器响应模拟计算。In order to overcome the above-mentioned problems in the prior art, the purpose of the present invention is to provide a method for characterizing the neutron-photon energy spectrum in the self-sufficient energy detector, which is applied in the calculation of the neutron-photon energy spectrum near the self-sufficient energy detector in the stack. , the optimal neutron-photon energy group structure is obtained by comparing with the neutron-photon sensitivity obtained by the encrypted neutron-photon energy spectrum simulation, which makes it suitable for both the deterministic method and the self-sufficient Monte Carlo method. Detector response simulation calculations.
为了实现上述目的，本发明采用了以下技术方案予以实施：In order to achieve the above object, the present invention adopts the following technical solutions to be implemented:
一种自给能中子探测器内中子-光子能谱的表征方法，包括如下步骤：A method for characterizing a neutron-photon energy spectrum in a self-sufficient neutron detector, comprising the following steps:
步骤1：读取压水堆中含自给中子能探测器的燃料组件的几何尺寸、材料布置、自给能中子探测器结构及材料以获得自给能中子探测器灵敏度计算模型，其中自给能中子探测器电流与自给能中子探测器发射极中子通量密度的比值定义为自给能探测器的中子灵敏度，具体的公式如下：Step 1: Read the geometric size, material arrangement, structure and material of the self-sufficient neutron detector in the pressurized water reactor fuel assembly to obtain the self-sufficient neutron detector sensitivity calculation model, wherein the self-sufficient energy The ratio of the neutron detector current to the neutron flux density at the emitter of the self-powered neutron detector is defined as the neutron sensitivity of the self-powered neutron detector. The specific formula is as follows:
在中子探测器灵敏度计算模型中，通过自给能中子探测器中各种粒子的物理作用，分别统计自给能中子探测器的正向I+和反向电流I-，从而获得自给能中子探测器的静电流I＝I+-I-，同时统计发射极的中子通量密度φn，结合上式即可求得自给能探测器的中子灵敏度；根据计算模型在蒙特卡洛程序MCNP中使用几何模块描述真实的组件几何结构、自给能中子探测器几何结构以及各几何结构内填充的材料，最终建立含有自给能中子探测器的二维燃料组件模型，同时设置自给能中子探测器附近的中子-光子能谱统计区域，进行燃料组件的特征值计算，通过求解燃料组件的稳态中子输运方程进而获得自给能中子探测器附近的中光子能谱：In the neutron detector sensitivity calculation model, the forward I+ and reverse current I- of the self-sufficient neutron detector are calculated by the physical interaction of various particles in the self-sufficient neutron detector, so as to obtain the self-sufficient energy neutron detector. The electrostatic current I=I+ -I- of the sub-detector, and the neutron flux density φn of the emitter is counted, and the neutron sensitivity of the self-sufficient detector can be obtained by combining the above formula; In the program MCNP, the geometry module is used to describe the real assembly geometry, the self-sufficient neutron detector geometry, and the materials filled in each geometric structure, and finally a two-dimensional fuel assembly model containing a self-sufficient neutron detector is established. In the statistical region of neutron-photon energy spectrum near the neutron detector, the eigenvalues of the fuel assembly are calculated, and the neutron energy spectrum near the self-sufficient neutron detector is obtained by solving the steady-state neutron transport equation of the fuel assembly:
步骤2：根据步骤1中蒙特卡洛程序求解的燃料组件特征值，根据粒子在自给能中子探测器附近统计区内的径迹长度模拟得到自给能中子探测器附近的中子能谱和光子能谱，同时记录中子-光子能谱的统计方差；根据统计方差的大小对每个能群间隔以对数能降均分的方式进行加密，需要保证加密后的中子-光子能群结构对应的统计方差不超过10％，进而得到加密后的中子能群和光子能群；Step 2: According to the eigenvalues of the fuel assembly solved by the Monte Carlo program in
步骤3：根据步骤2中获得的加密后的中子能群和光子能群，再次计算燃料组件的特征值，获得自给能中子探测器附近的573群中子能谱和128群光子能谱，同时检验中子能谱和光子能谱的统计方差，保证统计方差均在10％以内；Step 3: According to the encrypted neutron energy group and photon energy group obtained in
步骤4：根据步骤3中获得的加密后的573群中子能谱和128群光子能谱，将573群中子能谱和128群光子能谱作为自给能中子探测器响应模拟的能谱输入，使用蒙特卡洛程序Geant4读取573群中子能谱和128群光子能谱分别模拟获得自给能中子探测器的中子灵敏度和光子灵敏度，并将573群中子能谱模拟获得的中子灵敏度和128群光子能谱模拟获得的光子灵敏度作为能群选择的参考值；Step 4: According to the encrypted 573 group neutron energy spectrum and 128 group photon energy spectrum obtained in
步骤5：分别计算压水堆燃料组件中常用的三类中子能群69群、173群、361群结构对应的中子能谱，三类光子能群18群、20群、48群结构对应的光子能谱，计算每种中子-光子能谱对应的中子灵敏度和光子灵敏度，并与步骤4给出的573群中子能谱模拟获得的中子灵敏度和128群光子能谱模拟获得的光子灵敏度进行对比分析，选取与中子灵敏度、光子灵敏度参考值的相对偏差最小的能群结构作为最优中子-光子能群结构。Step 5: Calculate the neutron energy spectrum corresponding to the three types of neutron energy groups commonly used in PWR fuel assemblies: 69 groups, 173 groups and 361 groups, and the three types of photon energy groups corresponding to 18 groups, 20 groups and 48 groups. The photon energy spectrum of the The photon sensitivities of neutron and photon sensitivity were compared and analyzed, and the energy group structure with the smallest relative deviation from the reference value of neutron sensitivity and photon sensitivity was selected as the optimal neutron-photon energy group structure.
与现有技术相比，本发明有如下突出优点：Compared with the prior art, the present invention has the following outstanding advantages:
考虑了同时适用于确定论方法和蒙特卡洛方法的中子-光子能群结构，并根据蒙特卡洛方法连续能量的优点建立了加密能群作为中子-光子能群选择的标准，使得最终获得的中子-光子能群在适用于两种方法的同时尽可能准确的为自给能探测器的响应模拟提供探测器附近的中子-光子信息。Considering the neutron-photon energy group structure suitable for both the deterministic method and the Monte Carlo method, and establishing the encryption energy group as the criterion for the selection of the neutron-photon energy group according to the advantages of the continuous energy of the Monte Carlo method, so that the final The obtained neutron-photon energy group provides the neutron-photon information near the detector as accurately as possible for the response simulation of the self-sufficient energy detector while being applicable to both methods.
附图说明Description of drawings
图1是中子-光子能群选择的流程图。Figure 1 is a flow chart of neutron-photon energy group selection.
图2是自给能探测器几何模型示意图。Figure 2 is a schematic diagram of the geometric model of the self-sufficient energy detector.
图3是不同中子能群结构与573群中子灵敏度的相对偏差。Fig. 3 is the relative deviation of different neutron energy group structure and 573 group neutron sensitivity.
图4是不同光子能群结构与128群光子灵敏度的相对偏差。Fig. 4 is the relative deviation of different photon energy group structure and 128 group photon sensitivity.
具体实施方式Detailed ways
下面将结合附图和具体实施方式对本发明做进一步详细说明。The present invention will be further described in detail below with reference to the accompanying drawings and specific embodiments.
具体步骤如图1所示。本发明自给能中子探测器内中子-光子能谱的表征方法，主要包括不同能群结构的中子-光子能谱计算、在中子-光子能谱的统计方差范围内对中子能群-光子能群进行加密、不同中子-光子能谱下自给能探测器的灵敏度计算，其具体的步骤如下：The specific steps are shown in Figure 1. The characterization method of the neutron-photon energy spectrum in the self-sufficient neutron detector of the present invention mainly includes the calculation of the neutron-photon energy spectrum of different energy group structures, and the calculation of the neutron energy within the statistical variance range of the neutron-photon energy spectrum. The group-photon energy group is used to encrypt and calculate the sensitivity of self-sufficient energy detectors under different neutron-photon energy spectra. The specific steps are as follows:
步骤1：读取压水堆中含自给能中子探测器的燃料组件的几何尺寸、材料布置、自给能中子探测器结构及材料以获得自给能中子探测器灵敏度计算模型，其中自给能中子探测器电流与自给能中子探测器发射极中子通量密度的比值定义为自给能探测器的中子灵敏度，具体的公式如下：Step 1: Read the geometric size, material arrangement, structure and material of the self-powered neutron detector of the fuel assembly containing the self-powered neutron detector in the pressurized water reactor to obtain the self-powered neutron detector sensitivity calculation model, wherein the self-powered neutron detector The ratio of the neutron detector current to the neutron flux density at the emitter of the self-powered neutron detector is defined as the neutron sensitivity of the self-powered neutron detector. The specific formula is as follows:
在中子探测器灵敏度计算模型中，通过自给能中子探测器中各种粒子的物理作用，分别统计自给能中子探测器的正向I+和反向电流I-，从而获得自给能中子探测器的静电流I＝I+-I-，同时统计发射极的中子通量密度φn，结合上式即可求得自给能探测器的中子灵敏度；根据计算模型在蒙特卡洛程序(MCNP)中使用几何模块描述真实的组件几何结构、自给能中子探测器几何结构以及各几何结构内填充的材料，最终建立含有自给能中子探测器的二维燃料组件模型，同时设置自给能探测器附近的中子-光子能谱统计区域，进行燃料组件的特征值计算，通过求解燃料组件的稳态中子输运方程进而获得自给能中子探测器附近的中光子能谱：In the neutron detector sensitivity calculation model, the forward I+ and reverse current I- of the self-sufficient neutron detector are calculated by the physical interaction of various particles in the self-sufficient neutron detector, so as to obtain the self-sufficient energy neutron detector. The electrostatic current I=I+ -I- of the sub-detector, and the neutron flux density φn of the emitter is counted, and the neutron sensitivity of the self-sufficient detector can be obtained by combining the above formula; In the program (MCNP), the geometry module is used to describe the real assembly geometry, the self-powered neutron detector geometry and the materials filled in each geometric structure, and finally a two-dimensional fuel assembly model containing the self-powered neutron detector is established. In the statistical region of the neutron-photon energy spectrum near the self-powered neutron detector, the eigenvalues of the fuel assembly are calculated, and the neutron energy spectrum near the self-powered neutron detector is obtained by solving the steady-state neutron transport equation of the fuel assembly:
步骤2：根据步骤1中蒙特卡洛程序求解的燃料组件特征值，根据粒子在自给能中子探测器附近统计区内的径迹长度模拟得到自给能中子探测器附近的中子能谱和光子能谱同时记录中子-光子能谱的统计方差。根据统计方差的大小对每个能群间隔以对数能降均分的方式进行加密，需要保证加密后的中子-光子能群结构对应的统计方差不超过10％，进而得到加密后的中子能群和光子能群。Step 2: According to the eigenvalues of the fuel assembly solved by the Monte Carlo program in
步骤3：根据步骤2中获得的加密后的中子能群和光子能群，再次计算燃料组件的特征值，获得自给能中子探测器附近的573群中子能谱和128群光子能谱，同时检验中子能谱和光子能谱的统计方差，保证统计方差均在10％以内。Step 3: According to the encrypted neutron energy group and photon energy group obtained in
步骤4：根据步骤3中获得的加密后的573群中子能谱和128群光子能谱，将573群中子能谱和128群光子能谱作为自给能中子探测器响应模拟的能谱输入，使用蒙特卡洛程序Geant4读取573群中子能谱和128群光子能谱分别模拟获得自给能中子探测器的中子灵敏度和光子灵敏度，并将573群中子能谱模拟获得的中子灵敏度和128群光子能谱模拟获得的光子灵敏度作为能群选择的参考值。Step 4: According to the encrypted 573 group neutron energy spectrum and 128 group photon energy spectrum obtained in
步骤5：分别计算压水堆燃料组件中常用的三类中子能群结构(69群、173群、361群)对应的中子能谱，三类光子能群结构(18群、20群、48群)对应的光子能谱，计算每种中子-光子能谱对应的中子灵敏度和光子灵敏度，并与步骤4给出的573群中子能谱模拟获得的中子灵敏度和128群光子能谱模拟获得的光子灵敏度进行对比分析，选取与中子灵敏度、光子灵敏度参考值的相对偏差最小的能群结构作为最优中子-光子能群结构。Step 5: Calculate the neutron energy spectrum corresponding to the three types of neutron energy group structures (69 groups, 173 groups, and 361 groups) commonly used in PWR fuel assemblies, and the three types of photon energy group structures (18 groups, 20 groups, 48 groups) corresponding photon energy spectrum, calculate the neutron sensitivity and photon sensitivity corresponding to each neutron-photon energy spectrum, and compare the neutron sensitivity and 128 group photon sensitivity obtained by simulation with the 573 group neutron energy spectrum given in
为验证本发明对于选择自给能探测器附近中子-光子能群结构的能力，设计如图2所示的算例，算例中为钒自给能探测器，探测器结构由外向内依次是慢化剂、铝外壳、收集极、绝缘层、发射极，使用蒙特卡洛程序Geant4分别计算4套中子能群结构(69群、172群、361群、573群)以及4套光子能群结构(18群、20群、48群、128群)下中子-光子正向电流的灵敏度、反向电流的灵敏度和净电流的灵敏度。根据数值结果可以发现：In order to verify the ability of the present invention to select the neutron-photon energy group structure near the self-sufficient energy detector, a calculation example as shown in Figure 2 is designed. In the calculation example, a vanadium self-sufficient energy detector is used, and the detector structure is slow from outside to inside. Using the Monte Carlo program Geant4 to calculate 4 sets of neutron energy group structures (69 groups, 172 groups, 361 groups, 573 groups) and 4 sets of photon energy group structures respectively (Group 18,
1)由图3可知，四种中子能谱结构的净电流和正向电流的灵敏度均小于2％，且361群中子能群结构和573群中子能群结构的反向电流的灵敏度均小于2％。考虑到与压水堆常用能群结构以及与确定论程序的衔接，选取361群中子能群结构作为自给能探测器响应计算程序的中子能谱输入。1) It can be seen from Figure 3 that the net current and forward current sensitivities of the four neutron spectrum structures are both less than 2%, and the reverse current sensitivities of the 361 group neutron energy group structure and the 573 group neutron energy group structure are both lower than 2%. less than 2%. Considering the common energy group structure of PWR and the connection with the deterministic program, the neutron energy group structure of group 361 is selected as the neutron energy spectrum input of the response calculation program of the self-sufficient energy detector.
2)由图4可知，四种光子能群结构的净电流、正向电流和反向电流的灵敏度随光子能群的增多而降低。并且48群和128群的正向电流和反向电流的相对偏差均小于1％。为了保证光子模拟的准确性，最终选取128群光子能群结构作为自给能探测器响应计算程序的光子能谱输入。2) It can be seen from Fig. 4 that the sensitivities of the net current, forward current and reverse current of the four photon energy group structures decrease with the increase of photon energy groups. And the relative deviation of forward current and reverse current of 48 groups and 128 groups is less than 1%. In order to ensure the accuracy of photon simulation, 128 photon energy group structures are finally selected as the photon energy spectrum input of the self-sufficient energy detector response calculation program.
本发明在选择自给能探测器附近中子-光子能群结构方面，不受具体的反应堆堆型、燃料组件类型、自给能探测器类型的限制，基于蒙特卡洛方法可以建立精确的几何模型，同时具有连续能量的优势，可以给出统计方差范围内足够精细的能群结构作为参考能群，并能实现压水堆常用中子-光子能群结构的验证分析，从而选择出同时适合确定论方法和蒙特卡洛方法的中子-光子能群结构。In the aspect of selecting the neutron-photon energy group structure near the self-sufficient energy detector, the invention is not limited by the specific reactor type, fuel assembly type and self-sufficient energy detector type, and can establish an accurate geometric model based on the Monte Carlo method, At the same time, it has the advantage of continuous energy. It can give a sufficiently fine energy group structure within the range of statistical variance as a reference energy group, and can realize the verification analysis of the neutron-photon energy group structure commonly used in pressurized water reactors. method and the Monte Carlo method for the neutron-photon energy group structure.
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Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111931356A (en)* | 2020-07-22 | 2020-11-13 | 上海核工程研究设计院有限公司 | Combined analysis method for response current of reactor core self-powered detector |
| CN113435096A (en)* | 2021-06-23 | 2021-09-24 | 兰州大学 | High-precision numerical model calculation method and system for steady-state response of self-powered detector |
| CN120577851A (en)* | 2025-08-04 | 2025-09-02 | 西安交通大学 | Calculation and fitting method of sensitivity coefficient of self-powered neutron detector in nuclear reactor |
| CN120577851B (en)* | 2025-08-04 | 2025-10-10 | 西安交通大学 | Calculation and fitting method of sensitivity coefficient of self-powered neutron detector in nuclear reactor |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105426659A (en)* | 2015-10-30 | 2016-03-23 | 西安交通大学 | Method for obtaining sensitivity coefficients of effective multiplication factor to section under different burnups |
- 2019
- 2019-10-28CNCN201911028352.7Apatent/CN110781593B/enactiveActive
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105426659A (en)* | 2015-10-30 | 2016-03-23 | 西安交通大学 | Method for obtaining sensitivity coefficients of effective multiplication factor to section under different burnups |
Non-Patent Citations (2)
| Title |
|---|
| HYUNSUK LEE等: "New calculational model for self-powered neutron detector based on Monte Carlo simulation", 《JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY》* |
| 李捷等: "求解中子动力学方程的加权蒙特卡罗方法", 《强激光与粒子束》* |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111931356A (en)* | 2020-07-22 | 2020-11-13 | 上海核工程研究设计院有限公司 | Combined analysis method for response current of reactor core self-powered detector |
| CN111931356B (en)* | 2020-07-22 | 2023-08-04 | 上海核工程研究设计院股份有限公司 | A combined analysis method for the response current of self-powered detectors in the core |
| CN113435096A (en)* | 2021-06-23 | 2021-09-24 | 兰州大学 | High-precision numerical model calculation method and system for steady-state response of self-powered detector |
| CN120577851A (en)* | 2025-08-04 | 2025-09-02 | 西安交通大学 | Calculation and fitting method of sensitivity coefficient of self-powered neutron detector in nuclear reactor |
| CN120577851B (en)* | 2025-08-04 | 2025-10-10 | 西安交通大学 | Calculation and fitting method of sensitivity coefficient of self-powered neutron detector in nuclear reactor |
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