Development and Verification of HLPS Software for LOCA Hydraulics Load Analysis
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摘要: 为分析核电厂反应堆一回路系统发生假想断裂时冷却剂从破口喷放以及卸压波在一回路系统中传播引起的水力载荷特性，采用C++程序开发语言，自主研发了压水堆一回路冷却剂丧失事故（LOCA）水力载荷计算软件HLPS。以M310反应堆冷却剂系统为对象，将HLPS软件计算结果与工程数据进行对比验证，结果表明：HLPS软件的计算结果与工程数据符合良好，载荷力峰值基本包络工程数据；同时HLPS软件采取隐式求解以及更高的收敛标准，计算结果更加准确，可用于一回路系统LOCA分析。
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关键词:
- 冷却剂丧失事故（LOCA） /
- 一回路系统 /
- 水力载荷 /
- 自主研发 /
- HLPS
Abstract: In order to analyze the hydrodynamic loading characteristics caused by coolant jetting and pressure relief wave propagating in the reactor primary system of the nuclear power plant during a hypothetical fracture of the reactor primary system, HLPS, a software to calculate the hydraulic load in the loss of coolant accident (LOCA) in PWR primary circuit, is developed on self-reliance using C++ programming language. Taking M310 reactors coolant as the object, the results of HLPS software are compared with engineering data. The results show that the calculated results of HLPS software are in good agreement with engineering data, at the same time, HLPS adopts implicit solution and higher convergence standard, and the result is more accurate. It can be used for the analysis of the primary circuit system coolant loss accident. -
图 4 连接点示意图
点A—无局部阻力的双通连接点；点B—有局部阻力的双通连接点；点C—无局部阻力的多通连接点；点D—有局部阻力的多通连接点
Figure 4. Schematic Diagram of Connection Points
表 1 对流换热系数计算公式
Table 1. Calculation Formula of Convection Heat Transfer Coefficient
换热分类 公式 单相对流 Churchill & Bernstein 两相对流 核态沸腾换热（Chen公式） 大容积饱和沸腾换热（米海耶夫公式） 
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表 2 不同连接类型收敛对比
Table 2. Convergence of Different Connection Types
连接点对比 HLPS 工程数据 压力偏差/Pa 点A 1.01×10−11 6.44×10−4 点B 8.12×10−3 5.39×10−2 点C 1.20×10−2 1.68×10−2 点D 1.35×10−2 6.51×10−3 质量流量之和/(kg·s−1) 点A 1.01×10−11 1.01×10−11 点B 3.06×10−5 −2.70×10−4 点C −8.60×10−4 −22.35 点D 1.32 3.59
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表 4 反应堆压力容器最大载荷力
Table 4. Maximum Load of Reactor Pressure Vessel
对比位置 堆芯吊
篮底部堆芯下
支撑板燃料组件
下管座堆芯上
支撑板燃料元
件组件HLPS/106N −9.14551 1.16772 −9.93703×10−5 4.13134 1.47685 工程数据/106N −8.85011 0.99998 −1.04001×10−4 3.94081 1.51212 相对偏差/% 3.34 16.78 −4.45 4.83 2.39
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