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KEYWORD_EN:Flow 91 result(s) found
 
1. DEVELOPMENT OF A CORE THERMO-FLUID ANALYSIS CODE FOR PRISMATIC GAS COOLED REACTORS

Tak, Nam-Il;Lee, Sung Nam;Kim, Min-Hwan;Lim, Hong Sik;Noh, Jae Man;
Nuclear Engineering and Technology, vol. 46, iss. 5, 2014, pp. 641-654
 
2. ELECTRICAL RESISTANCE IMAGING OF TWO-PHASE FLOW WITH A MESH GROUPING TECHNIQUE BASED ON PARTICLE SWARM OPTIMIZATION

Lee, Bo An;Kim, Bong Seok;Ko, Min Seok;Kim, Kyung Youn;Kim, Sin;
Nuclear Engineering and Technology, vol. 46, iss. 1, 2014, pp. 109-116
 
3. VALIDATION OF NUMERICAL METHODS TO CALCULATE BYPASS FLOW IN A PRISMATIC GAS-COOLED REACTOR CORE

TAK NAM-IL ; KIM MIN-HWAN ; LIM HONG-SIK ; NOH JAE MAN ; DRZEWIECKI TIMOTHY J. ; SEKER VOLKAN ; DOWNAR THOMAS J. ; KELLY JOSEPH
Nuclear Engineering and Technology, vol. 45, iss. 6, 2013, pp. 745-752
 
4. IDENTIFICATION OF TWO-DIMENSIONAL VOID PROFILE IN A LARGE SLAB GEOMETRY USING AN IMPEDANCE MEASUREMENT METHOD

EUH D.J. ; KIM S. ; KIM B.D. ; PARK W.M. ; KIM K.D. ; BAE J.H. ; LEE J.Y. ; YUN B.J.
Nuclear Engineering and Technology, vol. 45, iss. 5, 2013, pp. 613-624
 
5. DEVELOPMENT AND VALIDATION OF A NUCLEAR FUEL CYCLE ANALYSIS TOOL: A FUTURE CODE

KIM S. K. ; KO W. I. ; LEE YOON HEE
Nuclear Engineering and Technology, vol. 45, iss. 5, 2013, pp. 665-674
 
6. FACTORS OF GROUNDWATER FLUCTUATION IN SHIN KORI NUCLEAR POWER PLANTS IN KOREA

HYUN SEUNG GYU ; WOO NAM C. ; KIM KUE-YOUNG ; LEE HYUN-A
Nuclear Engineering and Technology, vol. 45, iss. 4, 2013, pp. 539-552
 
7. DEVELOPMENT OF AN IMPROVED FARE TOOL WITH APPLICATION TO WOLSONG NUCLEAR POWER PLANT

LEE SUN KI ; HONG SUNG YULL
Nuclear Engineering and Technology, vol. 45, iss. 2, 2013, pp. 257-264
 
8. NUMERICAL INVESTIGATION OF THE SPREADING AND HEAT TRANSFER CHARACTERISTICS OF EX-VESSEL CORE MELT

YE IN-SOO ; KIM JEONGEUN ALICE ; RYU CHANGKOOK ; HA KWANG SOON ; KIM HWAN YEOL ; SONG JINHO
Nuclear Engineering and Technology, vol. 45, iss. 1, 2013, pp. 21-28
 
9. ASSESSMENT OF THERMAL FATIGUE IN MIXING TEE BY FSI ANALYSIS

JHUNG MYUNG JO
Nuclear Engineering and Technology, vol. 45, iss. 1, 2013, pp. 99-106
 
10. MULTI-SCALE THERMAL-HYDRAULIC ANALYSIS OF PWRS USING THE CUPID CODE

Yoon, Han Young;Cho, Hyoung Kyu;Lee, Jae Ryong;Park, Ik Kyu;Jeong, Jae Jun;
Nuclear Engineering and Technology, vol. 44, iss. 8, 2012, pp. 831-846