CAJ | 학술논문

根据核主泵的设计参数，采用正交试验对核主泵的主要参数进行了初步正交优化设计。根据正交优化结果，得到了1组最佳几何参数组合及各主要参数对核主泵性能影响的主次顺序，根据主次影响顺序对主要影响因素进行了进一步的多方案优化设计，进而得到能使核主泵具有更好性能的叶轮几何设计参数组合。根据最终的叶轮几何设计参数，建立了三维模型及对其内部流场进行了数值模拟计算，并用相似换算法，设计制造出对应的模型泵进行试验研究。结果显示：试验结果和模拟结果基本吻合，由此可证明叶轮优化设计的正确性。
근거핵주빙적설계삼수，채용정교시험대핵주빙적주요삼수진행료초보정교우화설계。근거정교우화결과，득도료1조최가궤하삼수조합급각주요삼수대핵주빙성능영향적주차순서，근거주차영향순서대주요영향인소진행료진일보적다방안우화설계，진이득도능사핵주빙구유경호성능적협륜궤하설계삼수조합。근거최종적협륜궤하설계삼수，건립료삼유모형급대기내부류장진행료수치모의계산，병용상사환산법，설계제조출대응적모형빙진행시험연구。결과현시：시험결과화모의결과기본문합，유차가증명협륜우화설계적정학성。
According to the design parameters of nuclear reactor coolant pump ,the pre‐liminary orthogonal optimization design for main parameters which had influence on the performance of nuclear reactor coolant pump were made by using orthogonal test . According to the results of orthogonal optimization design ,a set of the best combination of geometrical parameters and the primary and secondary influence order of the main parameters for the nuclear reactor coolant pump were got .According to the order ,the further optimization design of several main parameters was made ,and the combination of geometry design parameter for impeller was lastly achieved . The three‐dimensional model was established , the inner flow field was simulated , the model pump was designed and manufactured by using similar conversion method and the test research in normal temperature and pressure was done .The results show that the simulation results are similar to the test results ,so it shows that the orthogonal optimization design is right .