Abstract
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.