CAJ | 학술논문

以大亚湾核电站蒸汽发生器为原型，基于相似模化原理建立了蒸汽发生器简化物理模型。采用两流体模型及热弹性力学基本关系式分别描述气液两相流沸腾相变过程和热应力变化规律。利用CFX对一、二回路侧流体流动传热及与传热管的耦合换热过程进行了数值模拟，并在 ANSYS WORK-BENCH中实现了流体温度场载荷向结构的传递，进而对传热管进行稳态热分析和热应力分析。计算结果表明：二回路出口质量含汽率为24.5％，冷却剂出口温度为296.2℃，均与大亚湾蒸汽发生器实际运行参数相符；传热管热应力与其壁面温差分布一致，且沿壁厚方向先减小后增大，并存在中性层，传热管最大热应力为54.5 M Pa。研究结果为蒸汽发生器的优化设计及安全运行提供了一定的理论支撑。
이대아만핵전참증기발생기위원형，기우상사모화원리건립료증기발생기간화물리모형。채용량류체모형급열탄성역학기본관계식분별묘술기액량상류비등상변과정화열응력변화규률。이용CFX대일、이회로측류체류동전열급여전열관적우합환열과정진행료수치모의，병재 ANSYS WORK-BENCH중실현료류체온도장재하향결구적전체，진이대전열관진행은태열분석화열응력분석。계산결과표명：이회로출구질량함기솔위24.5％，냉각제출구온도위296.2℃，균여대아만증기발생기실제운행삼수상부；전열관열응력여기벽면온차분포일치，차연벽후방향선감소후증대，병존재중성층，전열관최대열응력위54.5 M Pa。연구결과위증기발생기적우화설계급안전운행제공료일정적이론지탱。
Taking the steam generator of Daya Bay Nuclear Power Plant as the prototype ,the simplified physical model of steam generator was established based on the similarity principle .The vapor-liquid two-phase flow boiling phase change process and thermal stress variation were simulated by two-fluid model and the basic thermal elasticity mechanics formula respectively .The flowing heat transfer on both the primary and the secondary sides and the coupled heat transfer between fluid and heat transfer tubes were numerically simulated using CFX software .The temperature load of fluid was transferred to the tubes in ANSYS WORKBENCH ,and then steady-state thermal analysis and thermal stress analysis were carried out .The simulation results show that the steam quality at outlet of the secondary side is 24.5% and the temperature of coolant at outlet is 296.2 ℃ ,which are in good agreement with the actual operating parameters of steam generator in Daya Bay Nuclear Power Plant .The distribution of the thermal stress is consistent with that of temperature difference of the tube’s wall .In addition , thermal stress along the wall thickness direction decreases and then increases , and neutral layer exists in the tube .The maximum thermal stress of the tube is 54.5 MPa . These results can provide theoretical support to the optimization of the design and safe operation in steam generator .