Authors: Liang, TKS Hung, HJ Chang, CJ

Citation: Tks. Liang et al., Development and application of the reactor coolant on-line leakage evaluation model for pressurized water reactors, NUCL TECH, 136(3), 2001, pp. 292-300

Authors: Liang, TKS Ko, FK Dai, LC

Citation: Tks. Liang et al., Assessment and application of the ROSE code for reactor outage thermal-hydraulic and safety analysis, NUCL TECH, 136(1), 2001, pp. 37-49

Authors: Liang, TKS Schultz, RR

Citation: Tks. Liang et Rr. Schultz, Development program of LOCA licensing calculation capability with RELAP5-3D in accordance with appendix K of 10 CFR 50.46, NUCL TECH, 133(3), 2001, pp. 355-358

Authors: Liang, TKS Ko, FK

Citation: Tks. Liang et Fk. Ko, Code development and assessment for reactor outage thermal-hydraulic and safety analysis-midloop operation with loss of residual heat removal, NUCL TECH, 129(1), 2000, pp. 13-25