DEVELOPMENT OF PIN-LEVEL NEUTRONICS/THERMAL-FLUID ANALYSIS COUPLED CODE SYSTEM FOR A BLOCK-TYPE HTGR CORE

by Seungsu Yuk, Nam-il Tak, Jo Keun Chang
Published 2021-01-01

POSCA: A computer code for fission product plateout and circulating coolant activities within the primary circuit of a high temperature gas-cooled reactor

by Nam-il Tak, Jeong-Hun Lee, Sung Nam Lee, Chang Keun Jo
Published 2020-09-01

DEVELOPMENT OF A CORE THERMO-FLUID ANALYSIS CODE FOR PRISMATIC GAS COOLED REACTORS

by NAM-IL TAK, SUNG NAM LEE, MIN-HWAN KIM, HONG SIK LIM, JAE MAN NOH
Published 2014-10-01

VALIDATION OF NUMERICAL METHODS TO CALCULATE BYPASS FLOW IN A PRISMATIC GAS-COOLED REACTOR CORE

by NAM-IL TAK, MIN-HWAN KIM, HONG-SIK LIM, JAE MAN NOH, TIMOTHY J. DRZEWIECKI, VOLKAN SEKER, THOMAS J. DOWNAR, JOSEPH KELLY
Published 2013-11-01