TRACE是由美國核管會所發展的最先進熱水流安全分析程式，設計目的在整合了包含RAMONA、RELAP5、TRAC-PWR以及TRAC-BWR的功能，主要應用於輕水式核能電廠的各種暫態與冷卻水流失事故的分析評估，TRACE的特色也包含能模擬一維或三維熱水流現象。本篇論文目的在敘述如何建立台電核二廠TRACE熱水流安全分析程式，模式建立是以電廠設計資料為基礎，並參考核二廠RETRAN安全分析模式資料。模式建立後進行穩態分析研究，接著作暫態摸擬，根據核二廠啟動測試的資料，針對100%功率負載棄載測試作驗證。

The TRACE (TRAC/RELAP Advanced Computational Engine) is a modernized thermal-hydraulics code developed by the NRC (U.S. Nuclear Regulatory Commission). It is designed to encompass all of the capabilities of RAMONA, RELAP5, TRAC-PWER, TRAC-BWR. The TRACE is able to analyze large or small break LOCA, accidents up to the point of significant fuel damage, and reactor transients in both PWRs and BWRs. The capability also exists to model thermal hydraulic phenomena in both 1-D and 3-D space. This is NRC's flagship thermal-hydraulics analysis tool. This paper is to build up the TRACE thermal-hydraulic analysis model of the Kuosheng BWR6 NPP (Nuclear Power Plant). The model is based on benchmark analysis against RETRAN analysis and the plant startup test data. The startup test is 100% power load rejection test. This test can provide valuable information for the benchmark studies of Kuosheng TRACE model. Furthermore the TRACE model can be applied to transient analysis and safety estimate in order to support the operation of power plant.

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