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采用模块式结构建立了钠冷快堆主回路系统的数学模型，选用端点浮动法有效克服了点堆方程的刚性问题。堆芯热工和ＩＨＸ计算采用稳定性良好的全稳二阶迎风差分格式。编制了钠冷快堆失热阱瞬态仿真程序ＬＯＨＳ。该程序可在微机环境下运行，模型简单、速度快。用ＬＯＨＳ对ＥＢＲ－Ⅱ失热阱瞬态实验的计算结果与安全分析程序ＮＡＴＤＥＭＯ的计算结果符合良好。依据计算结果对快堆固有安全特性进行了分析
The mathematic model of the sodium-cooled fast reactor main circuit system is established by the modular structure. End-point float method is adopted to overcome the rigidity problem of the point reactor. Core thermal and IHX calculations use the well-established, fully-stabilized second-order upwind difference format. The LOHS transient transient simulation program for sodium-cooled fast reactor was developed. The program can run in the computer environment, the model is simple, fast. The results of the transient experiments of EBR-Ⅱ heat sink with LOHS are in good agreement with those of NATDEMO. Based on the calculation results, the inherent safety characteristics of the fast reactor are analyzed