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CN113506646B - Method and device for judging geometric structure of reactor core node in reactor core melting process - Google Patents

Method and device for judging geometric structure of reactor core node in reactor core melting process Download PDF

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CN113506646B
CN113506646B CN202110568708.7A CN202110568708A CN113506646B CN 113506646 B CN113506646 B CN 113506646B CN 202110568708 A CN202110568708 A CN 202110568708A CN 113506646 B CN113506646 B CN 113506646B
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刘晓晶
罗跃建
许巍
柴翔
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Shanghai Jiao Tong University
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Abstract

The application relates to a method and a device for judging a core node geometric structure in a core fusion process, wherein the method comprises the following steps: obtaining initial porosity and critical porosity; the initial porosity is a calculated value of the porosity of the reactor core node in a complete state; acquiring the current porosity and the current melting share of each reactor core node; comparing the current porosity with the initial porosity and the critical porosity; and judging the geometric structure of the corresponding reactor core node according to the comparison result and the current melting share value. According to the scheme, the judgment criterion is established for the geometric structure of the reactor core nodes through the reactor core geometric parameters, so that the mass energy transfer between the reactor core nodes and the mass energy transfer between the reactor core nodes can be accurately calculated, and an analysis basis is provided for the numerical analysis of the reactor core melting process of the plate-shaped fuel element reactor.

Description

堆芯熔融进程中堆芯节点几何结构的判断方法和装置Method and device for judging the geometric structure of core nodes in the process of core fusion

技术领域technical field

本申请涉及核反应堆的安全分析技术领域,具体涉及一种堆芯熔融进程中堆芯节点几何结构的判断方法和装置。The application relates to the technical field of safety analysis of nuclear reactors, and in particular to a method and device for judging the geometric structure of core nodes in the process of core melting.

背景技术Background technique

自核能发展之初,核安全就一直是公众关注的焦点,安全分析一直以来都是核能科学研究的重点。核反应堆是核能利用的核心,反应堆堆芯丧失冷却后,在人因失误、设备失效等一系列风险叠加情况下,可能导致堆芯材料熔融,发生严重事故,造成放射性裂变产物外泄。燃料元件作为反应堆堆芯的主要部件,目前轻水堆燃料元件主要包括棒状燃料元件与板状燃料元件。棒状燃料元件主要应用在商用轻水堆、沸水堆中,板状燃料元件主要应用在研究堆、试验堆、核动力潜艇、核动力航母等特殊核动力装置中。严重事故下燃料元件熔融行为对反应堆堆芯熔融进程有重要影响,不同几何形式、材料类型燃料元件的熔融行为有显著不同,典型棒状燃料元件反应堆堆芯熔融进程如图1所示。开展反应堆严重事故下堆芯熔融进程数值研究,对反应堆严重事故分析、缓解措施制定具有一定意义。Since the beginning of the development of nuclear energy, nuclear safety has been the focus of public attention, and safety analysis has always been the focus of nuclear energy scientific research. Nuclear reactors are the core of nuclear energy utilization. After the reactor core loses cooling, under the superposition of a series of risks such as human error and equipment failure, it may lead to the melting of core materials, resulting in serious accidents, resulting in the leakage of radioactive fission products. Fuel elements are the main components of the reactor core. Currently, the fuel elements of light water reactors mainly include rod-shaped fuel elements and plate-shaped fuel elements. Rod fuel elements are mainly used in commercial light water reactors and boiling water reactors, and plate fuel elements are mainly used in research reactors, test reactors, nuclear powered submarines, nuclear powered aircraft carriers and other special nuclear power devices. The melting behavior of fuel elements in severe accidents has an important impact on the melting process of the reactor core. The melting behavior of fuel elements with different geometric forms and material types is significantly different. The melting process of a typical rod-shaped fuel element reactor core is shown in Figure 1. Carrying out numerical research on the core melting process under severe reactor accidents has certain significance for the analysis of severe reactor accidents and the formulation of mitigation measures.

许多机构均有开发严重事故分析程序,模拟堆芯熔融进程,典型有美国爱达荷国家工程与环境实验室的SCDAP/RELAP5程序、法国辐射防护与核安全研究所与德国核设备与反应堆安全协会的ASTEC程序、美国电力研究协会的MAAP程序、美国桑迪亚国家实验室的MELCOR程序、法国辐射防护与核安全研究所的CATHARE/ICARE程序、德国核设备与反应堆安全协会的ATHLET-CD程序等系统分析程序。以上严重事故分析程序对棒状元件反应堆堆芯熔融进程均具有良好模拟能力,仅SCDAP/RELAP5程序对板状燃料元件反应堆堆芯熔融进程能够进行简单数值分析。目前SCDAP/RELAP5程序对板状燃料元件反应堆堆芯熔融进程进行数值分析时,没有进行堆芯节点几何结构判断。Many institutions have developed severe accident analysis programs to simulate the core melting process. Typical examples include the SCDAP/RELAP5 program of the National Engineering and Environmental Laboratory in Idaho, the French Institute for Radiation Protection and Nuclear Safety, and the German Association for Nuclear Equipment and Reactor Safety. The ASTEC program of the American Electric Power Research Association, the MAAP program of the American Electric Power Research Association, the MELCOR program of the Sandia National Laboratory, the CATHARE/ICARE program of the French Institute of Radiation Protection and Nuclear Safety, the ATHLET-CD program of the German Association for Nuclear Equipment and Reactor Safety, etc. System analyzer. The above severe accident analysis programs all have good simulation capabilities for the core melting process of rod-shaped element reactors. Only the SCDAP/RELAP5 program can perform simple numerical analysis on the core melting process of plate-shaped fuel element reactors. At present, when the SCDAP/RELAP5 program numerically analyzes the core melting process of the plate fuel element reactor, it does not judge the core node geometry.

严重事故下堆芯熔融进程数值研究中将堆芯划分为轴向径向节点,如图2所示,堆芯节点几何结构对堆芯节点间、节点内质量能量守恒具有重要影响,进而影响整个堆芯熔融进程,准确判断堆芯节点几何结构,是开展堆芯熔融进程数值研究的关键。在进行板状燃料元件堆芯熔融进程数值分析时,需要进行堆芯节点几何结构的判断,对开展板状燃料元件堆芯熔融进程精确数值分析具有重要意义。In the numerical study of the core melting process under severe accident, the core is divided into axial and radial nodes, as shown in Fig. 2, the core node geometry has an important influence on the conservation of mass and energy between the core nodes and within the nodes, which in turn affects the entire core node. The core melting process and accurate determination of the core node geometry are the keys to numerical research on the core melting process. When carrying out the numerical analysis of the core melting process of the plate fuel element, it is necessary to judge the geometric structure of the core node, which is of great significance for the accurate numerical analysis of the core melting process of the plate fuel element.

相关技术中,目前板状燃料元件反应堆堆芯熔融进程数值分析中,没有对堆芯节点几何结构进行详细划分。In the related art, in the numerical analysis of the core melting process of the plate-shaped fuel element reactor, the geometric structure of the core node is not divided in detail.

发明内容SUMMARY OF THE INVENTION

为至少在一定程度上克服相关技术中存在的问题,本申请提供一种堆芯熔融进程中堆芯节点几何结构的判断方法和装置。In order to overcome the problems existing in the related art at least to a certain extent, the present application provides a method and apparatus for judging the geometric structure of a core node during a core fusion process.

根据本申请实施例的第一方面,提供一种堆芯熔融进程中堆芯节点几何结构的判断方法,包括:According to a first aspect of the embodiments of the present application, a method for judging the geometric structure of a core node during a core fusion process is provided, including:

获取初始孔隙率、临界孔隙率;所述初始孔隙率是堆芯节点完整状态下孔隙率的计算值;Obtain the initial porosity and critical porosity; the initial porosity is the calculated value of the porosity in the intact state of the core node;

获取各个堆芯节点的当前孔隙率、当前熔融份额;Obtain the current porosity and current melting share of each core node;

将当前孔隙率与初始孔隙率、临界孔隙率进行对比;Compare the current porosity with the initial porosity and critical porosity;

根据对比结果和当前熔融份额的值判断对应的堆芯节点的几何结构。Determine the geometry of the corresponding core node according to the comparison result and the value of the current melting share.

进一步地,所述孔隙率为堆芯节点的流通横截面积与总横截面积的比值;所述熔融份额为堆芯节点的熔化材料质量与材料总质量的比值。Further, the porosity is the ratio of the flow cross-sectional area of the core node to the total cross-sectional area; the melting share is the ratio of the mass of the melted material of the core node to the total mass of the material.

进一步地,所述获取各个堆芯节点的当前孔隙率、当前熔融份额,包括:Further, the obtaining the current porosity and the current melting share of each core node includes:

根据预设的时间步长,在不同时刻分别获取各个堆芯节点的当前孔隙率、当前熔融份额。According to the preset time step, the current porosity and current melting share of each core node are obtained at different times.

进一步地,堆芯节点的几何结构的类型至少包括:完整状燃料元件、加厚状燃料元件、堆芯硬壳、堆芯熔融池。Further, the types of the geometric structures of the core nodes include at least: intact fuel elements, thickened fuel elements, core monocoques, and core molten pools.

进一步地,所述根据对比结果和当前熔融份额的值判断对应的堆芯节点的几何结构,包括:Further, judging the geometric structure of the corresponding core node according to the comparison result and the value of the current melting share includes:

如果堆芯节点的孔隙率大于预设的临界孔隙率且大于等于初始孔隙率,则该堆芯节点的几何结构的类型为完整状燃料元件;If the porosity of the core node is greater than the preset critical porosity and greater than or equal to the initial porosity, the type of the geometric structure of the core node is a complete fuel element;

如果堆芯节点的孔隙率大于预设的临界孔隙率且小于初始孔隙率,则该堆芯节点的几何结构的类型为加厚状燃料元件。If the porosity of the core node is greater than the preset critical porosity and less than the initial porosity, the type of the geometry of the core node is a thickened fuel element.

进一步地,所述根据对比结果和当前熔融份额的值判断对应的堆芯节点的几何结构,包括:Further, judging the geometric structure of the corresponding core node according to the comparison result and the value of the current melting share includes:

如果堆芯节点的孔隙率小于预设的临界孔隙率,则根据当前熔融份额的值判断几何结构。If the porosity of the core node is less than the preset critical porosity, the geometry is judged according to the value of the current melt fraction.

进一步地,所述根据当前熔融份额的值判断几何结构,包括:Further, judging the geometric structure according to the value of the current melting share includes:

如果当前熔融份额的值大于99%,则堆芯节点的几何结构的类型为堆芯熔融池;If the value of the current melt share is greater than 99%, the type of core node geometry is core melt pool;

否则该堆芯节点的几何结构的类型为堆芯硬壳。Otherwise the core node geometry is of the core monocoque type.

根据本申请实施例的第二方面,提供一种堆芯熔融进程中堆芯节点几何结构的判断装置,包括:According to a second aspect of the embodiments of the present application, there is provided a device for judging the geometric structure of a core node during a core fusion process, including:

初始化模块,用于获取初始孔隙率、临界孔隙率;所述初始孔隙率是堆芯节点完整状态下孔隙率的计算值;The initialization module is used to obtain the initial porosity and the critical porosity; the initial porosity is the calculated value of the porosity in the intact state of the core node;

监测模块,用于获取各个堆芯节点的当前孔隙率、当前熔融份额;The monitoring module is used to obtain the current porosity and current melting share of each core node;

判断模块,用于将当前孔隙率与初始孔隙率、临界孔隙率进行对比,根据对比结果和当前熔融份额的值判断对应的堆芯节点的几何结构。The judgment module is used to compare the current porosity with the initial porosity and the critical porosity, and judge the geometric structure of the corresponding core node according to the comparison result and the value of the current melting share.

根据本申请实施例的第三方面,提供一种计算机设备,包括:According to a third aspect of the embodiments of the present application, a computer device is provided, including:

存储器,用于存储计算机程序;memory for storing computer programs;

处理器,用于执行所述存储器中的计算机程序,以实现如上任意一种实施例所述方法的操作步骤。The processor is configured to execute the computer program in the memory to implement the operation steps of the method described in any one of the above embodiments.

根据本申请实施例的第四方面,提供一种计算机可读存储介质,其上存储有计算机程序,所述计算机程序被处理器执行时实现如上任意一种实施例所述方法的操作步骤。According to a fourth aspect of the embodiments of the present application, there is provided a computer-readable storage medium on which a computer program is stored, and when the computer program is executed by a processor, implements the operation steps of the method described in any one of the above embodiments.

本申请的实施例提供的技术方案具备以下有益效果:The technical solutions provided by the embodiments of the present application have the following beneficial effects:

本申请的方案通过堆芯几何参数对堆芯节点几何结构建立判断准则,有利于准确计算堆芯节点内、节点间质量能量传递,为板状燃料元件反应堆堆芯熔融进程数值分析提供分析基础。The solution of the present application establishes a judgment criterion for the geometric structure of the core node through the core geometric parameters, which is beneficial to accurately calculate the mass energy transfer within the core node and between the nodes, and provides an analysis basis for the numerical analysis of the core melting process of the plate fuel element reactor.

应当理解的是,以上的一般描述和后文的细节描述仅是示例性和解释性的,并不能限制本申请。It is to be understood that both the foregoing general description and the following detailed description are exemplary and explanatory only and are not limiting of the present application.

附图说明Description of drawings

此处的附图被并入说明书中并构成本说明书的一部分,示出了符合本申请的实施例,并与说明书一起用于解释本申请的原理。The accompanying drawings, which are incorporated in and constitute a part of this specification, illustrate embodiments consistent with the application and together with the description serve to explain the principles of the application.

图1是堆芯熔融进程示意图。Figure 1 is a schematic diagram of the core melting process.

图2(a)~(b)分别是堆芯节点的径向节点、轴向节点的划分示意图。Figures 2(a)-(b) are schematic diagrams of division of radial nodes and axial nodes of core nodes, respectively.

图3是根据一示例性实施例示出的一种堆芯熔融进程中堆芯节点几何结构的判断方法的流程图。FIG. 3 is a flow chart of a method for judging a core node geometry in a core fusion process according to an exemplary embodiment.

图4(a)~(d)分别是四种堆芯节点的几何结构类型示意图。Figures 4(a)-(d) are schematic diagrams of the geometrical structure types of the four core nodes, respectively.

图5是根据一示例性实施例示出的一种堆芯节点几何结构分布。FIG. 5 shows a core node geometry distribution according to an exemplary embodiment.

图6是根据一示例性实施例示出的一种堆芯节点几何结构判断准则。FIG. 6 shows a criterion for determining a core node geometry according to an exemplary embodiment.

图7(a)是SPERT实验堆算例中,中心通道再定位前的堆芯节点几何结构分布示意图。Figure 7(a) is a schematic diagram of the distribution of the core node geometry before the center channel repositioning in the SPERT experimental reactor example.

图7(b)是SPERT实验堆算例中,边通道再定位前的堆芯节点几何结构分布示意图。Figure 7(b) is a schematic diagram of the core node geometry distribution before the side channel repositioning in the SPERT experimental reactor example.

具体实施方式Detailed ways

这里将详细地对示例性实施例进行说明,其示例表示在附图中。下面的描述涉及附图时,除非另有表示,不同附图中的相同数字表示相同或相似的要素。以下示例性实施例中所描述的实施方式并不代表与本申请相一致的所有实施方式。相反,它们仅是与如所附权利要求书中所详述的、本申请的一些方面相一致的方法和装置的例子。Exemplary embodiments will be described in detail herein, examples of which are illustrated in the accompanying drawings. Where the following description refers to the drawings, the same numerals in different drawings refer to the same or similar elements unless otherwise indicated. The implementations described in the illustrative examples below are not intended to represent all implementations consistent with this application. Rather, they are merely examples of methods and apparatus consistent with some aspects of the present application as recited in the appended claims.

图3是根据一示例性实施例示出的一种堆芯熔融进程中堆芯节点几何结构的判断方法的流程图。该方法可以包括以下步骤:FIG. 3 is a flow chart of a method for judging a core node geometry in a core fusion process according to an exemplary embodiment. The method may include the following steps:

步骤S1:获取初始孔隙率、临界孔隙率;所述初始孔隙率是堆芯节点完整状态下孔隙率的计算值;Step S1: obtaining the initial porosity and the critical porosity; the initial porosity is the calculated value of the porosity in the intact state of the core node;

步骤S2:获取各个堆芯节点的当前孔隙率、当前熔融份额;Step S2: obtaining the current porosity and current melting share of each core node;

步骤S3:将当前孔隙率与初始孔隙率、临界孔隙率进行对比;Step S3: comparing the current porosity with the initial porosity and the critical porosity;

步骤S4:根据对比结果和当前熔融份额的值判断对应的堆芯节点的几何结构。Step S4: Determine the geometric structure of the corresponding core node according to the comparison result and the value of the current melting share.

本申请的方案通过堆芯几何参数对堆芯节点几何结构建立判断准则,有利于准确计算堆芯节点内、节点间质量能量传递,为板状燃料元件反应堆堆芯熔融进程数值分析提供分析基础。The solution of the present application establishes a judgment criterion for the geometric structure of the core node through the core geometric parameters, which is beneficial to accurately calculate the mass energy transfer within the core node and between the nodes, and provides an analysis basis for the numerical analysis of the core melting process of the plate fuel element reactor.

应当理解的是,虽然图3的流程图中的各个步骤按照箭头的指示依次显示,但是这些步骤并不是必然按照箭头指示的顺序依次执行。除非本文中有明确的说明,这些步骤的执行并没有严格的顺序限制,这些步骤可以以其它的顺序执行。而且,图3中的至少一部分步骤可以包括多个子步骤或者多个阶段,这些子步骤或者阶段并不必然是在同一时刻执行完成,而是可以在不同的时刻执行,这些子步骤或者阶段的执行顺序也不必然是依次进行,而是可以与其它步骤或者其它步骤的子步骤或者阶段的至少一部分轮流或者交替地执行。It should be understood that although the various steps in the flowchart of FIG. 3 are shown in sequence according to the arrows, these steps are not necessarily executed in the sequence shown by the arrows. Unless explicitly stated herein, the execution of these steps is not strictly limited to the order, and these steps may be performed in other orders. Moreover, at least a part of the steps in FIG. 3 may include multiple sub-steps or multiple stages. These sub-steps or stages are not necessarily executed at the same time, but may be executed at different times. The execution of these sub-steps or stages The sequence is also not necessarily sequential, but may be performed alternately or alternately with other steps or sub-steps of other steps or at least a portion of a phase.

为进一步详述本申请的技术方案,首先具体解释反应堆堆芯熔融进程中节点几何结构的划分依据。In order to further describe the technical solution of the present application, firstly, the basis for dividing the node geometry in the process of reactor core fusion is explained in detail.

如图4所示,在板状燃料元件反应堆堆芯熔融进程中,根据板状燃料元件具有不同几何结构与材料类型的特点,本方案将板状燃料元件反应堆堆芯熔融进程中节点几何结构划分为:完整状燃料元件a、加厚状燃料元件b、堆芯硬壳c、堆芯熔融池d、空节点e等五种结构类型。As shown in Fig. 4, in the core melting process of the plate-shaped fuel element reactor, according to the characteristics of the plate-shaped fuel element with different geometric structures and material types, this scheme divides the node geometry in the core melting process of the plate-shaped fuel element reactor. There are five structural types: complete fuel element a, thickened fuel element b, core hard shell c, core melting pool d, and empty node e.

当燃料板保持完整时,定义成几何结构a;当燃料包壳破损后,芯体熔融物沿裂缝流出,或上部节点熔融物迁移到当前节点,造成当前节点燃料板厚度增加,定义成几何结构b;向下迁移再凝固熔融物与向下迁移氧化物,在堆芯下部区域形成堆芯硬壳结构,严重堵塞流道,定义成几何结构c;下部区域堆芯硬壳支撑堆芯结构材料,形成堆芯熔融池,定义成几何结构d;当节点内没有任何堆芯材料时,定义成几何结构e。由各节点几何结构组成的堆芯节点几何结构分布示意图如图5所示,堆芯熔融池依次相邻堆芯硬壳、加厚状燃料元件、完整状燃料元件。When the fuel plate remains intact, it is defined as geometric structure a; when the fuel cladding is damaged, the core melt flows out along the crack, or the upper node melt migrates to the current node, resulting in an increase in the thickness of the fuel plate at the current node, which is defined as geometric structure b; Downward migration of the resolidified melt and downward migration of oxides forms a core hard shell structure in the lower region of the core, which seriously blocks the flow channel, which is defined as geometric structure c; The core hard shell in the lower region supports the core structural material , forming the core melting pool, which is defined as geometric structure d; when there is no core material in the node, it is defined as geometric structure e. Figure 5 shows a schematic diagram of the distribution of the core node geometry composed of each node geometry. The core molten pool is adjacent to the core hard shell, thickened fuel elements, and complete fuel elements in sequence.

节点几何结构与孔隙率密切相关,具体判断流程如图6所示。图中:POR为节点孔隙率,POR0为堆芯初始孔隙率,PORC为设定临界孔隙率,fmelt为节点材料熔融份额。其中,孔隙率为堆芯节点的流通横截面积与总横截面积的比值;熔融份额为堆芯节点的熔化材料质量与材料总质量的比值。初始孔隙率为堆芯节点完整时的计算值。临界孔隙率为预先设定的数值,根据反应堆的实际情况进行设定,在一些实施例中可以取0.1。The node geometry is closely related to the porosity, and the specific judgment process is shown in Figure 6. In the figure: POR is the nodal porosity, POR0 is the initial porosity of the core, PORC is the set critical porosity, and fmelt is the melting fraction of the nodal material. Among them, the porosity is the ratio of the flow cross-sectional area of the core node to the total cross-sectional area; the melting share is the ratio of the mass of the molten material at the core node to the total mass of the material. The initial porosity is the calculated value when the core nodes are complete. The critical porosity is a preset value, which is set according to the actual situation of the reactor, and may be 0.1 in some embodiments.

一些实施例中,所述步骤S2中,获取各个堆芯节点的当前孔隙率、当前熔融份额,具体包括:根据预设的时间步长,在不同时刻分别获取各个堆芯节点的当前孔隙率、当前熔融份额。也即是,在每个时间步长,都会计算一次每个节点当前的孔隙率与熔融份额。In some embodiments, in the step S2, obtaining the current porosity and the current melting share of each core node specifically includes: according to a preset time step, respectively obtaining the current porosity, Current melt share. That is, at each time step, the current porosity and melt fraction for each node is calculated.

在获取到上述的几种堆芯几何参数之后,通过孔隙率与设定临界孔隙率、初始孔隙率关系判断节点几何结构:如果孔隙率大于设定临界孔隙率,大于等于初始孔隙率,说明燃料元件维持板状结构a;如果孔隙率大于设定临界孔隙率,小于初始孔隙率,说明上部节点熔融物向下迁移至当前节点,燃料元件呈加厚状结构b;如果孔隙率小于设定临界孔隙率,需要判断节点材料熔融份额,节点材料熔融份额超过99%时,则呈堆芯熔融池结构d,反之则呈堆芯硬壳结构c。After obtaining the above several core geometric parameters, the node geometry is judged by the relationship between the porosity, the set critical porosity, and the initial porosity: if the porosity is greater than the set critical porosity and greater than or equal to the initial porosity, it means that the fuel The element maintains the plate-like structure a; if the porosity is greater than the set critical porosity and less than the initial porosity, it means that the upper node melt migrates down to the current node, and the fuel element has a thickened structure b; if the porosity is less than the set critical porosity For the porosity, it is necessary to judge the melting share of the node material. When the melting share of the node material exceeds 99%, it is the core melting pool structure d, otherwise it is the core hard shell structure c.

堆芯熔融进程中节点几何结构演化过程受相邻节点与当前节点几何结构综合影响,由最初节点结构c或结构节点d向下部节点逐渐演化,最终形成如图5所示堆芯节点几何结构分布。During the core melting process, the evolution process of the node geometry is affected by the adjacent nodes and the current node geometry. .

下面结合具体的反应堆实验场景,对本申请的方案进行拓展说明。In the following, the solution of the present application will be expanded and explained in conjunction with the specific reactor experiment scenario.

SPERT-Ⅰ反应堆中D-12/25板状燃料元件使用铝合金包壳、U-Al合金芯体,开展过大量研究,具有详实研究基础,采用SPERT-ⅠD-12/25实验作为研究对象,对其开展严重事故下堆芯熔融进程数值分析,展示堆芯熔融进程中堆芯节点几何结构判断方法的技术效果。The D-12/25 plate-shaped fuel element in the SPERT-I reactor uses aluminum alloy cladding and U-Al alloy core. A large number of studies have been carried out and have a detailed research basis. The SPERT-ID-12/25 experiment is used as the research object. Numerical analysis of the core melting process under severe accident is carried out, and the technical effect of the method for judging the core node geometry during the core melting process is shown.

堆芯材料再定位至下封头前堆芯几何结构分布如7所示:堆芯材料在再定位至下封头前发生广泛迁移再定位。图中,channel为中心通道,channel2为边通道。The core geometry distribution before the core material is relocated to the lower head is shown in Figure 7: the core material undergoes extensive migration and repositioning before being repositioned to the lower head. In the figure, channel is the central channel, and channel2 is the side channel.

中心通道中堆芯材料再定位至下封头前,堆芯上部区域节点维持完整板状几何结构,下部节点过渡到加厚状几何结构,其中中心通道最底部节点孔隙率低于临界孔隙率0.1,形成硬壳结构,堆芯温度没有超过氧化铝熔点,所有氧化铝维持固态,没有堆芯节点过渡到堆芯熔融池结构。边通道中堆芯材料再定位至下封头前,中心通道中没有堆芯材料存在,堆芯上部区域节点维持完整板状几何结构,下部节点过渡到加厚状几何结构,其中节点3中堆芯材料最多,节点孔隙率最低。Before the core material in the central channel is relocated to the lower head, the nodes in the upper region of the core maintain a complete plate-like geometry, and the lower nodes transition to a thickened geometry. The porosity of the bottom node of the central channel is lower than the critical porosity of 0.1 , forming a hard shell structure, the core temperature does not exceed the melting point of alumina, all alumina remains solid, and no core node transitions to the core melting pool structure. The core material in the side channel is relocated to the lower head, and there is no core material in the central channel. The nodes in the upper region of the core maintain a complete plate-like geometry, and the lower nodes transition to a thickened geometry. The core material is the most and the nodal porosity is the lowest.

本申请还提供如下实施例:The application also provides the following examples:

一种堆芯熔融进程中堆芯节点几何结构的判断装置,包括:A device for judging the geometric structure of a core node in a core melting process, comprising:

初始化模块,用于获取初始孔隙率、临界孔隙率;所述初始孔隙率是堆芯节点完整状态下孔隙率的计算值;The initialization module is used to obtain the initial porosity and the critical porosity; the initial porosity is the calculated value of the porosity in the intact state of the core node;

监测模块,用于获取各个堆芯节点的当前孔隙率、当前熔融份额;The monitoring module is used to obtain the current porosity and current melting share of each core node;

判断模块,用于将当前孔隙率与初始孔隙率、临界孔隙率进行对比,根据对比结果和当前熔融份额的值判断对应的堆芯节点的几何结构。The judgment module is used to compare the current porosity with the initial porosity and the critical porosity, and judge the geometric structure of the corresponding core node according to the comparison result and the value of the current melting share.

关于该装置,其中各个模块执行操作的具体步骤已经在有关该方法的实施例中进行了详细描述,此处不再详细阐述说明。上述判断装置中的各个模块可全部或部分通过软件、硬件及其组合来实现。上述各模块可以硬件形式内嵌于或独立于计算机设备中的处理器中,也可以以软件形式存储于计算机设备中的存储器中,以便于处理器调用执行以上各个模块对应的操作。Regarding the device, the specific steps in which each module performs operations have been described in detail in the embodiments of the method, and will not be described in detail here. All or part of each module in the above judgment device can be implemented by software, hardware and combinations thereof. The above modules can be embedded in or independent of the processor in the computer device in the form of hardware, or stored in the memory in the computer device in the form of software, so that the processor can call and execute the operations corresponding to the above modules.

本申请还提供如下实施例:The application also provides the following examples:

一种计算机设备,包括:A computer device comprising:

存储器,用于存储计算机程序;memory for storing computer programs;

处理器,用于执行所述存储器中的计算机程序,以实现一种堆芯熔融进程中堆芯节点几何结构的判断方法:获取初始孔隙率、临界孔隙率;所述初始孔隙率是堆芯节点完整状态下孔隙率的计算值;获取各个堆芯节点的当前孔隙率、当前熔融份额;将当前孔隙率与初始孔隙率、临界孔隙率进行对比;根据对比结果和当前熔融份额的值判断对应的堆芯节点的几何结构。The processor is used for executing the computer program in the memory, so as to realize a method for judging the geometric structure of the core node during the core melting process: obtaining the initial porosity and the critical porosity; the initial porosity is the core node Calculated value of porosity in the complete state; obtain the current porosity and current melting share of each core node; compare the current porosity with the initial porosity and critical porosity; judge the corresponding Core node geometry.

本申请还提供如下实施例:The application also provides the following examples:

一种计算机可读存储介质,其上存储有计算机程序,所述计算机程序被处理器执行时实现一种堆芯熔融进程中堆芯节点几何结构的判断方法:获取初始孔隙率、临界孔隙率;所述初始孔隙率是堆芯节点完整状态下孔隙率的计算值;获取各个堆芯节点的当前孔隙率、当前熔融份额;将当前孔隙率与初始孔隙率、临界孔隙率进行对比;根据对比结果和当前熔融份额的值判断对应的堆芯节点的几何结构。A computer-readable storage medium on which a computer program is stored, and when the computer program is executed by a processor, realizes a method for judging the geometric structure of a core node in a core melting process: obtaining an initial porosity and a critical porosity; The initial porosity is the calculated value of the porosity in the complete state of the core node; the current porosity and the current melting share of each core node are obtained; the current porosity is compared with the initial porosity and the critical porosity; according to the comparison result and the value of the current melting share to determine the corresponding core node geometry.

可以理解的是,上述各实施例中相同或相似部分可以相互参考,在一些实施例中未详细说明的内容可以参见其他实施例中相同或相似的内容。It can be understood that, the same or similar parts in the above embodiments may refer to each other, and the content not described in detail in some embodiments may refer to the same or similar content in other embodiments.

需要说明的是,在本申请的描述中,术语“第一”、“第二”等仅用于描述目的,而不能理解为指示或暗示相对重要性。此外,在本申请的描述中,除非另有说明,“多个”的含义是指至少两个。It should be noted that, in the description of the present application, the terms "first", "second" and the like are only used for the purpose of description, and should not be construed as indicating or implying relative importance. Also, in the description of this application, unless otherwise specified, the meaning of "plurality" means at least two.

流程图中或在此以其他方式描述的任何过程或方法描述可以被理解为,表示包括一个或更多个用于实现特定逻辑功能或过程的步骤的可执行指令的代码的模块、片段或部分,并且本申请的优选实施方式的范围包括另外的实现,其中可以不按所示出或讨论的顺序,包括根据所涉及的功能按基本同时的方式或按相反的顺序,来执行功能,这应被本申请的实施例所属技术领域的技术人员所理解。Any description of a process or method in the flowcharts or otherwise described herein may be understood to represent a module, segment or portion of code comprising one or more executable instructions for implementing a specified logical function or step of the process , and the scope of the preferred embodiments of the present application includes alternative implementations in which the functions may be performed out of the order shown or discussed, including performing the functions substantially concurrently or in the reverse order depending upon the functions involved, which should It is understood by those skilled in the art to which the embodiments of the present application belong.

应当理解,本申请的各部分可以用硬件、软件、固件或它们的组合来实现。在上述实施方式中,多个步骤或方法可以用存储在存储器中且由合适的指令执行系统执行的软件或固件来实现。例如,如果用硬件来实现,和在另一实施方式中一样,可用本领域公知的下列技术中的任一项或他们的组合来实现:具有用于对数据信号实现逻辑功能的逻辑门电路的离散逻辑电路,具有合适的组合逻辑门电路的专用集成电路,可编程门阵列(PGA),现场可编程门阵列(FPGA)等。It should be understood that various parts of this application may be implemented in hardware, software, firmware, or a combination thereof. In the above-described embodiments, various steps or methods may be implemented in software or firmware stored in memory and executed by a suitable instruction execution system. For example, if implemented in hardware, as in another embodiment, it can be implemented by any one or a combination of the following techniques known in the art: Discrete logic circuits, application specific integrated circuits with suitable combinational logic gates, Programmable Gate Arrays (PGA), Field Programmable Gate Arrays (FPGA), etc.

本技术领域的普通技术人员可以理解实现上述实施例方法携带的全部或部分步骤是可以通过程序来指令相关的硬件完成,所述的程序可以存储于一种计算机可读存储介质中,该程序在执行时,包括方法实施例的步骤之一或其组合。Those skilled in the art can understand that all or part of the steps carried by the methods of the above embodiments can be completed by instructing the relevant hardware through a program, and the program can be stored in a computer-readable storage medium, and the program can be stored in a computer-readable storage medium. When executed, one or a combination of the steps of the method embodiment is included.

此外,在本申请各个实施例中的各功能单元可以集成在一个处理模块中,也可以是各个单元单独物理存在,也可以两个或两个以上单元集成在一个模块中。上述集成的模块既可以采用硬件的形式实现,也可以采用软件功能模块的形式实现。所述集成的模块如果以软件功能模块的形式实现并作为独立的产品销售或使用时,也可以存储在一个计算机可读取存储介质中。In addition, each functional unit in each embodiment of the present application may be integrated into one processing module, or each unit may exist physically alone, or two or more units may be integrated into one module. The above-mentioned integrated modules can be implemented in the form of hardware, and can also be implemented in the form of software function modules. If the integrated modules are implemented in the form of software functional modules and sold or used as independent products, they may also be stored in a computer-readable storage medium.

上述提到的存储介质可以是只读存储器,磁盘或光盘等。The above-mentioned storage medium may be a read-only memory, a magnetic disk or an optical disk, and the like.

在本说明书的描述中,参考术语“一个实施例”、“一些实施例”、“示例”、“具体示例”、或“一些示例”等的描述意指结合该实施例或示例描述的具体特征、结构、材料或者特点包含于本申请的至少一个实施例或示例中。在本说明书中,对上述术语的示意性表述不一定指的是相同的实施例或示例。而且,描述的具体特征、结构、材料或者特点可以在任何的一个或多个实施例或示例中以合适的方式结合。In the description of this specification, description with reference to the terms "one embodiment," "some embodiments," "example," "specific example," or "some examples", etc., mean specific features described in connection with the embodiment or example , structure, material or feature is included in at least one embodiment or example of the present application. In this specification, schematic representations of the above terms do not necessarily refer to the same embodiment or example. Furthermore, the particular features, structures, materials or characteristics described may be combined in any suitable manner in any one or more embodiments or examples.

尽管上面已经示出和描述了本申请的实施例,可以理解的是,上述实施例是示例性的,不能理解为对本申请的限制,本领域的普通技术人员在本申请的范围内可以对上述实施例进行变化、修改、替换和变型。Although the embodiments of the present application have been shown and described above, it should be understood that the above embodiments are exemplary and should not be construed as limitations to the present application. Embodiments are subject to variations, modifications, substitutions and variations.

Claims (6)

1.一种堆芯熔融进程中堆芯节点几何结构的判断方法,其特征在于,包括:1. A method for judging the geometric structure of a core node in a core fusion process, characterized in that, comprising: 获取初始孔隙率、临界孔隙率;所述初始孔隙率是堆芯节点完整状态下孔隙率的计算值;Obtain the initial porosity and critical porosity; the initial porosity is the calculated value of the porosity in the intact state of the core node; 获取各个堆芯节点的当前孔隙率、当前熔融份额;Obtain the current porosity and current melting share of each core node; 将当前孔隙率与初始孔隙率、临界孔隙率进行对比;Compare the current porosity with the initial porosity and critical porosity; 根据对比结果和当前熔融份额的值判断对应的堆芯节点的几何结构,该步骤包括:如果堆芯节点的孔隙率大于预设的临界孔隙率且大于等于初始孔隙率,则该堆芯节点的几何结构的类型为完整状燃料元件;如果堆芯节点的孔隙率大于预设的临界孔隙率且小于初始孔隙率,则该堆芯节点的几何结构的类型为加厚状燃料元件;如果堆芯节点的孔隙率小于预设的临界孔隙率,则根据当前熔融份额的值判断几何结构;如果当前熔融份额的值大于99%,则堆芯节点的几何结构的类型为堆芯熔融池;否则该堆芯节点的几何结构的类型为堆芯硬壳;Determine the geometric structure of the corresponding core node according to the comparison result and the value of the current melting share. The step includes: if the porosity of the core node is greater than a preset critical porosity and greater than or equal to the initial porosity, then the The type of the geometry is the intact fuel element; if the porosity of the core node is greater than the preset critical porosity and less than the initial porosity, the type of the geometry of the core node is the thickened fuel element; If the porosity of the node is less than the preset critical porosity, the geometry is judged according to the value of the current melting share; if the value of the current melting share is greater than 99%, the type of the geometry of the core node is the core melting pool; otherwise, the The type of core node geometry is core hard shell; 其中,所述孔隙率为堆芯节点的流通横截面积与总横截面积的比值;所述熔融份额为堆芯节点的熔化材料质量与材料总质量的比值。Wherein, the porosity is the ratio of the flow cross-sectional area of the core node to the total cross-sectional area; the melting fraction is the ratio of the mass of the melted material of the core node to the total mass of the material. 2.根据权利要求1所述的方法,其特征在于,所述获取各个堆芯节点的当前孔隙率、当前熔融份额,包括:2 . The method according to claim 1 , wherein the acquiring the current porosity and the current melting share of each core node comprises: 2 . 根据预设的时间步长,在不同时刻分别获取各个堆芯节点的当前孔隙率、当前熔融份额。According to the preset time step, the current porosity and current melting share of each core node are obtained at different times. 3.根据权利要求1或2所述的方法,其特征在于:堆芯节点的几何结构的类型至少包括:完整状燃料元件、加厚状燃料元件、堆芯硬壳、堆芯熔融池。3. The method according to claim 1 or 2, wherein the types of the geometry of the core nodes include at least: integral fuel elements, thickened fuel elements, core monocoque, and core molten pool. 4.一种堆芯熔融进程中堆芯节点几何结构的判断装置,应用于权利要求1-3任一项所述的堆芯熔融进程中堆芯节点几何结构的判断方法,其特征在于,所述判断装置包括:4. A device for judging the geometric structure of a core node in the process of core fusion, which is applied to the method for judging the geometric structure of a core node in the process of core fusion according to any one of claims 1-3, wherein the The judging device includes: 初始化模块,用于获取初始孔隙率、临界孔隙率;所述初始孔隙率是堆芯节点完整状态下孔隙率的计算值;The initialization module is used to obtain the initial porosity and the critical porosity; the initial porosity is the calculated value of the porosity in the intact state of the core node; 监测模块,用于获取各个堆芯节点的当前孔隙率、当前熔融份额;The monitoring module is used to obtain the current porosity and current melting share of each core node; 判断模块,用于将当前孔隙率与初始孔隙率、临界孔隙率进行对比,根据对比结果和当前熔融份额的值判断对应的堆芯节点的几何结构。The judgment module is used to compare the current porosity with the initial porosity and the critical porosity, and judge the geometric structure of the corresponding core node according to the comparison result and the value of the current melting share. 5.一种计算机设备,其特征在于,包括:5. A computer equipment, characterized in that, comprising: 存储器,用于存储计算机程序;memory for storing computer programs; 处理器,用于执行所述存储器中的计算机程序,以实现权利要求1-3任一项所述方法的操作步骤。A processor for executing the computer program in the memory to implement the operation steps of the method of any one of claims 1-3. 6.一种计算机可读存储介质,其上存储有计算机程序,其特征在于,所述计算机程序被处理器执行时实现权利要求1-3任一项所述方法的操作步骤。6. A computer-readable storage medium on which a computer program is stored, characterized in that, when the computer program is executed by a processor, the operation steps of the method of any one of claims 1-3 are implemented.
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Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3993542A (en) * 1974-02-28 1976-11-23 Pechiney Ugine Kuhlmann Process and apparatus for extraction of gases produced during operation of a fused-salt nuclear reactor
US6236698B1 (en) * 1998-03-17 2001-05-22 Kabushiki Kaisha Toshiba Nuclear reactor power distribution monitoring system and method including nuclear reactor instrumentation system
JP2014071017A (en) * 2012-09-28 2014-04-21 Toshiba Corp Fuel element and core fuel assembly
CN105374405A (en) * 2014-08-22 2016-03-02 国家核电技术有限公司 Reactor melt retention apparatus
CN105427900A (en) * 2015-12-11 2016-03-23 中国核电工程有限公司 Out-of-pile retention system for reaction pile melt after occurrence of severe accident
CN107451398A (en) * 2017-07-07 2017-12-08 西安交通大学 PWR nuclear power plant major accident analysis method

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110289111B (en) * 2019-07-09 2020-11-13 上海交通大学 Flow rate determination method, device and server for natural circulation loop

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3993542A (en) * 1974-02-28 1976-11-23 Pechiney Ugine Kuhlmann Process and apparatus for extraction of gases produced during operation of a fused-salt nuclear reactor
US6236698B1 (en) * 1998-03-17 2001-05-22 Kabushiki Kaisha Toshiba Nuclear reactor power distribution monitoring system and method including nuclear reactor instrumentation system
JP2014071017A (en) * 2012-09-28 2014-04-21 Toshiba Corp Fuel element and core fuel assembly
CN105374405A (en) * 2014-08-22 2016-03-02 国家核电技术有限公司 Reactor melt retention apparatus
CN105427900A (en) * 2015-12-11 2016-03-23 中国核电工程有限公司 Out-of-pile retention system for reaction pile melt after occurrence of severe accident
CN107451398A (en) * 2017-07-07 2017-12-08 西安交通大学 PWR nuclear power plant major accident analysis method

Non-Patent Citations (3)

* Cited by examiner, † Cited by third party
Title
SCDAP/RELAP5与MELCOR程序对堆芯损伤过程预测的比较;付霄华;《核动力工程》;20031028(第05期);430-434 *
基于RELAP5与MELCOR联合分析方法的压水堆严重事故研究;王珏等;《核科学与工程》;20160215(第01期);125-133 *
小型核热推进反应堆概念设计;柴翔;《核科学与工程》;20210430;223-229 *

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