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KEYWORD_EN:Fluid simulation 26 result(s) found
 
1. MODAL CHARACTERISTIC ANALYSIS OF THE APR1400 NUCLEAR REACTOR INTERNALS FOR SEISMIC ANALYSIS

Park, Jong-Beom;Choi, Youngin;Lee, Sang-Jeong;Park, No-Cheol;Park, Kyoung-Su;Park, Young-Pil;Park, Chan-Il;
Nuclear Engineering and Technology, vol. 46, iss. 5, 2014, pp. 689-698
 
2. 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
 
3. PUMP DESIGN AND COMPUTATIONAL FLUID DYNAMIC ANALYSIS FOR HIGH TEMPERATURE SULFURIC ACID TRANSFER SYSTEM

Choi, Jung-Sik;Shin, Young-Joon;Lee, Ki-Young;Yun, Yong-Sup;Choi, Jae-Hyuk;
Nuclear Engineering and Technology, vol. 46, iss. 3, 2014, pp. 363-372
 
4. NUMERICAL ANALYSIS OF THERMAL STRATIFICATION IN THE UPPER PLENUM OF THE MONJU FAST REACTOR

CHOI SEOK-KI ; LEE TAE-HO ; KIM YEONG-IL ; HAHN DOHEE
Nuclear Engineering and Technology, vol. 45, iss. 2, 2013, pp. 191-202
 
5. 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
 
6. 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
 
7. A COMPARATIVE STUDY OF LATTICE BOLTZMANN AND VOLUME OF FLUID METHOD FOR TWO-DIMENSIONAL MULTIPHASE FLOWS

Ryu, Seung-Yeob;Ko, Sung-Ho;
Nuclear Engineering and Technology, vol. 44, iss. 6, 2012, pp. 623-638
 
8. NUMERICAL ANALYSIS FOR PRANDTL NUMBER DEPENDENCY ON NATURAL CONVECTION IN AN ENCLOSURE HAVING A VERTICAL THERMAL GRADIENT WITH A SQUARE INSULATOR INSIDE

Lee, Jae-Ryong;Park, Il-Seouk;
Nuclear Engineering and Technology, vol. 44, iss. 3, 2012, pp. 283-296
 
9. THE CUPID CODE DEVELOPMENT AND ASSESSMENT STRATEGY

Jeong, J.J.;Yoon, H.Y.;Park, I.K.;Cho, H.K.;
Nuclear Engineering and Technology, vol. 42, iss. 6, 2010, pp. 636-655
 
10. DEVELOPMENT AND PRELIMINARY ASSESSMENT OF A THREE-DIMENSIONAL THERMAL HYDRAULICS CODE, CUPID

Jeong, Jae-Jun;Yoon, Han-Young;Park, Ik-Kyu;Cho, Hyoung-Kyu;Lee, Hee-Dong;
Nuclear Engineering and Technology, vol. 42, iss. 3, 2010, pp. 279-296