TRACE (TRAC/RELAP Advanced Computational Engine) 是美國核管會近年發展最先進的熱水流安全分析程式，我們團隊使用TRACE程式在去年完成龍門電廠TRACE模式的建立。本論文內容將探討功率時間表、點中子動力法及結合PARCS (Purdue Advanced Reactor Core Simulator) 程式等三種不同中子動力源提供給龍門電廠TRACE模式進行兩個案例分析：反應器全隔離(Reactor Full Isolation)，起動測試案例；主蒸氣隔離閥關閉(Main Steam-line Isolation Valve closure, MSIV closure)暫態事故，FSAR案例。龍門電廠PARCS模式雖已初步建立完成，結合龍門電廠TRACE模式尚未成功，未來還有待突破。本論文成功利用功率時間表、點中子動力法等兩種中子動力源完成案例分析，分析結果與GE，RELAP5，FSAR，RETRAN等分析結果趨勢大致相同，唯獨龍門電廠點中子動力法之TRACE模式在主蒸氣隔離閥關閉案例中爐心功率模擬還有待改善，未來將會調整空泡反應度係數尤其是龍門電廠完成起動測試分析。

TRACE (TRAC/RELAP Advanced Computational Engine) code, developed by USNRC, is an advanced thermal hydraulic system code for nuclear power plant safety analysis. The TRACE whole plant model for Lungmen NPP (ABWR) has been developed last year. In this thesis, three different neutronic models, power table method, point kinetics method, and coupled with PARCS (Purdue Advanced Reactor Core Simulator) in TRACE, were adopted to generate or calculate the core power in Reactor Full Isolation transient and Main Steam-line Closure Direct Scram transient for Lungmen. Currently, PARCS model for Lungmen has been essentially completed except for the final coupling with TRACE. We have found from the results in the two transient analyses that both power table and point kinetics methods in TRACE provide predictions that are in good consistency with those from GE or RELAP5 and FSAR or RETRAN02. The only discrepancy is that the power level predicted by point kinetics method is smaller between the transient times from 1 to 2 seconds. Some tunings on void reactivity coefficients may have to be made in the future, especially when Lungmen completes its startup transient tests.

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