TRACE是一個強而有力的核電廠安全分析程式，目前的金山核電廠TRACE模式，經驗證後已可應用於相當多的安全分析上，但是主要都是在爐心熱流的安全分析。因此，本論文的研究方向是將目前金山核電廠TRACE模式分析計算發展至下游的圍阻體系統分析及上游的中子動力學計算。
下游方向發展至圍阻體分析方面，發展金山核電廠TRACE/CONTAN模式，將爐心熱流分析的TRACE結合圍阻體分析的組件CONTAN，以進行爐心熱流及圍阻體系統同步計算分析。本研究已應用TRACE/CONTAN模式進行LOCA、SBO 24小時及URG的分析。其中LOCA事故分析顯示TRACE/CONTAN模式與FSAR及GOTHIC程式分析結果比較，可以獲得令人滿意的分析結果。SBO 24小時事故分析顯示，比較TRACE/CONTAN模式與RETRAN-02加上SHEX的分析結果，兩者也十分吻合。金山核電廠的TRACE/CONTAN模式進行URG分析的結果顯示，URG的兩階段降壓策略，較直接作緊急降壓，可更有效降低事故過程的燃料護套尖峰溫度，所需的最小替代注水量也遠低於直接作緊急降壓。
上游方向拓展至中子動力學計算方面，發展金山核電廠TRACE/PARCS模式，將爐心熱流分析的TRACE結合反應爐爐心模擬器PARCS，以進行爐心熱流及爐心中子熱力學同步計算分析，本研究已利用電廠啟動測試資料的暫態案例，進行金山核電廠TRACE/PARCS模式的驗證，驗證分析包括六項啟動測試暫態分析，模擬結果顯示TRACE/PARCS模式可以良好的分析金山核電廠的啟動測試暫態，並且具備一定的準確度。金山核電廠TRACE/PARCS模式進一步應用於控制棒擾動穩定性模擬上，由模擬的結果可明顯的觀察到功率以及燃料組件內流量的震盪，並驗證爐心系統的穩定性。

TRACE is a thermal-hydraulic analysis code for reactor safety. The current Chinshan NPP TRACE model has been verified and can be applied to safety analysis for the reactor coolant system. Therefore, this research attempts to extend the applications of the Chinshan NPP TRACE model to the containment system analysis and the neutron kinetic calculation.
The downstream direction is extended to the analysis of the containment system, so the TRACE/CONTAN model of Chinshan NPP was developed. The TRACE, a reactor coolant system analysis code, was combined with the CONTAN, a special module for the containment system analysis, to perform the real-time calculation. In this study, the TRACE/CONTAN model has been used to analyze LOCA, SBO 24 hours, and URG. The result of LOCA accident analysis shows that the TRACE/CONTAN mode can obtain satisfactory analysis results. The result of the SBO 24 hours accident analysis showed that comparing the TRACE/CONTAN with the analysis results of RETRAN/SHEX is also very consistent. The results of URG analysis in the TRACE/CONTAN model of Chinshan NPP show that URG’s two-stage depressurization strategy is safer than one-stage emergency depressurization, which can more effectively reduce the peak temperature of the fuel cladding during the accident and the minimum requirement of alternative water injection.
The upstream direction is extended to the calculation of neutron kinetics, the TRACE/PARCS model of Chinshan NPP is developed, and the TRACE of the reactor coolant system analysis is combined with the reactor core simulator PARCS to perform real-time calculation and analysis of the reactor coolant system and the neutron kinetics of the reactor core. This study has used the transient case of power plant start-up test data to verify the TRACE/PARCS model of Chinshan NPP. The verification analysis includes six transient analyses of start-up tests. The simulation results show that the TRACE/PARCS model can well analyze the transients of start-up test in Chinshan NPP’s, and achieve a certain degree of accuracy. The TRACE/PARCS model of Chinshan Nuclear Power Plant is further applied to the simulation of control rod perturbance stability. In the results of the simulation, the oscillation of power and flow in the fuel assembly can be observed, and the stability of core system could be approved.

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