1. “Standard Safety Analysis Report for Korean Next Generation Reactor,” Korea Electric Power Corp (1999).
2. Y. J. CHUNG and S. K. SIM, “Test Requirements for the KNGR DVI ECCS Performance Test,” SA-DVI-99008, Korea Atomic Energy Research Institute (1999) (in Korean).
3. The three-level scaling approach with application to the Purdue University Multi-Dimensional Integral Test Assembly (PUMA)
4. C.H. SONG, S.J. LEE, T. S. KWON, S.K. MOON, B.J. YUN, S. CHO, K.Y. CHOI, and H.S. PARK, “Scaling Analysis of the Integral Test Loop to Simulate Korean PWR Plants,” KAERI/TR-1783/2001, Korea Atomic Energy Research Institute (2001) (in Korean).