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ENHANCED NATURAL CIRCULATION MODELING IN THE GNF BWR CORE SIMULATOR AETNA02 FOR ESBWR

机译:在GNF BWR核心模拟器AETNA02中增强自然循环建模,用于ESBWR

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GE Hitachi Nuclear Energy's (GEH) next evolution of Boiling Water Reactor (BWR) technology is the Economic Simplified Boiling Water Reactor (ESBWR). The ESBWR is a natural circulation reactor which employs numerous passive safety features while simultaneously offering a large power output for a relatively small plant footprint. The ESBWR is characterized with shortened fuel length and a tall, partitioned chimney region above the core to promote natural circulation core flow. The ESBWR is studied with Global Nuclear Fuel (GNF)'s advanced core-simulator AETNA02. AETNA02 is a static, three-dimensional coupled nuclear-thermal hydraulic computer program representing a BWR core. The new GNF lattice-physics core simulator package LANCR02/AETNA02 consists of the two-dimensional method of characteristics based lattice code, LANCR02, which generates cross sections over a range of plant conditions and passes them to the three neutron energy group coarse mesh nodal diffusion code AETNA02. For the thermal hydraulic solution, AETNA02 includes a model which explicitly solves for the flow in each channel, water rod, and bypass region which accompanies a fuel channel. For the solution of a natural circulation plant like the ESBWR, AETNA02 utilizes the Automatic Plant Thermal Hydraulics (APTH) model which includes models for the core, the chimney region, the separator, the dryer, and the downcomer. AETNA02 iterates on the fuel channel flow and the pressure drop by modeling each chimney partition explicitly with fuel channels and bypasses mapped to it in addition to a bypass mixing model for the chimneys. This is relevant because the peripheral channels (low power) will have a lower void fraction while the central channels (higher power) will have a higher void fraction. Thus, the chimneys connected to these channels will each have a different hydrostatic head. To verify and validate each of the APTH component models, code-to-code comparisons are performed with the GEH TRACG04 code as well as data comparisons with experiments. The TRACG04 computer program is a best-estimate two-fluid transient code. Code-to-code comparisons of the two different methods (two-fluid model in TRACG04 versus drift flux model in AETNA02) are made. In addition, this study attempts to quantify the impact on the core flow distribution that will affect the calculated thermal margins, including the Critical Power Ratio (CPR). The impact of the multiple chimney (MC) versus the single chimney (SC) model is studied. The multiple chimney partition modeling provides additional detail to the core flow distribution that is not considered in the single chimney model. The results confirm and add confidence that the multiple chimney partition modeling will provide improved accuracy in the ESBWR core design.
机译:GE Hitachi核能(GEH)下次沸水反应器(BWR)技术的演变是经济简化的沸水反应器(ESBWR)。 ESBWR是一种自然循环反应器,其采用多种被动安全性,同时为相对小的工厂占地面积提供大功率输出。 ESBWR的特征在于芯缩短的燃料长度和高于芯上方的高度分隔的烟囱区域,以促进自然循环芯流量。通过全球核燃料(GNF)先进的核心模拟器AETNA02研究了ESBWR。 Aetna02是表示BWR芯的静态三维耦合核 - 热液压计算机程序。新的GNF格子 - 物理核心模拟器包LANCR02 / AETNA02包括基于特性的晶格代码LANCR02的二维方法,它在一系列植物条件下产生横截面,并将其传递给三个中子能量组粗糙网格焦点扩散代码Aetna02。对于热液压解决方案,AETNA02包括模型,该模型明确地解决了伴随燃料通道的每个通道,水杆和旁路区域中的流动。对于像ESBWR自然循环植物的溶液,AETNA02利用自动植物热工水力(APTH)模型,它包括模型的核心,烟囱区域,分离器,干燥机,以及降液管。 AETNA02通过将每个烟囱分区建模,通过将每个烟囱分区建模,并且除了烟囱的旁路混合模型之外,通过模拟燃料通道和旁路映射到它来迭代燃料通道流量和压力下降。这是相关的,因为外围通道(低功率)将具有较低的空隙率,而中央通道(更高功率)将具有更高的空隙率。因此,连接到这些通道的烟囱各自具有不同的静水压头。为了验证和验证每个APTH组件模型,使用GEH TRACG04代码以及与实验进行数据比较来执行代码到码比较。 TRACG04计算机程序是最佳估计的两种流体瞬态码。制作了两种不同方法的代码码比较(TRACG04中的双流体模型,AETNA02中的TRACG04与漂移通量模型)。此外,本研究试图量化对核心流量分布的影响,这将影响计算出的热边缘,包括临界功率比(CPR)。研究了多个烟囱(MC)对单个烟囱(SC)模型的影响。多个烟囱分区建模提供了额外的细节,以在单个烟囱模型中不考虑的核心流量分布。结果确认并增添了多种烟囱分区建模的信心,在ESBWR核心设计中提供了提高的准确性。

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