CAJ | 학술논문

由于NOTRUMP-AP600程序的动量守恒方程缺少动量通量项，在分析用于模拟AP600核电厂的A PEX试验台架小破口事故时，安全壳内置换料水箱注射流量和稳压器混合水位等参数的预测值和实验值有较大偏离。本文对此进行评估：1）采用均相流和分相流模型计算动量通量项对A P600核电厂自动卸压系统（ADS）管路压降的影响；2）采用FLOAD4程序对需修正的第4级ADS（ADS4）管路的两相流压降进行计算，预测ADS4管路内的压力分布，并用作修正NOTRUMP-AP600程序 ADS4管路压降的基准。结果表明，对于A P600核电厂ADS4管路，输入阻力系数需增加60％。
유우NOTRUMP-AP600정서적동량수항방정결소동량통량항，재분석용우모의AP600핵전엄적A PEX시험태가소파구사고시，안전각내치환료수상주사류량화은압기혼합수위등삼수적예측치화실험치유교대편리。본문대차진행평고：1）채용균상류화분상류모형계산동량통량항대A P600핵전엄자동사압계통（ADS）관로압강적영향；2）채용FLOAD4정서대수수정적제4급ADS（ADS4）관로적량상류압강진행계산，예측ADS4관로내적압력분포，병용작수정NOTRUMP-AP600정서 ADS4관로압강적기준。결과표명，대우A P600핵전엄ADS4관로，수입조력계수수증가60％。
The momentum flux terms are not included in the momentum equations for NOTRUMP-AP600 code .The predicted injection mass flow rate of IRWST and pres-surizer level deviate test results largely when NOTRUMP-AP600 code is used to analyze SBLOCA for APEX-600 test facility . The impact of neglecting the momentum flux terms in the NOTRUMP-AP600 was evaluated ,including the following contents :The impact of neglecting momentum flux terms for the pressure drop of ADS line was calcu-lated using homogenous model and separated flow model ;the detailed two-phase pres-sure drop was calculated using FLOAD4 code for the ADS4 line ,and the result was used to benchmark the ADS4 pressure drop for NOTRUMP-AP600 .The results show that the input resistance coefficient should be increased by 60% for AP600 ADS4 line .