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Showing results 4 to 7 of 7

4
Experimental Study on Fracture of Oxidized Support Column in VHTR

No Hee Cheon; Park, Byung Ha, ANS, 2011-06

5
FEASIBILITY STUDY OF A DEDICATED NUCLEAR DESALINATION SYSTEM: LOW-PRESSURE INHERENT HEAT SINK NUCLEAR DESALINATION PLANT (LIND)

Kim, Ho Sik; No, Hee-Cheon; Jo, Yugwon; Wibisono, Andhika Feri; Park, Byung Ha; Choi, Jinyoung; Lee, Jeong-Ik; et al, NUCLEAR ENGINEERING AND TECHNOLOGY, v.47, no.3, pp.293 - 305, 2015-04

6
Recession of CVD silicon carbide in steam environment

Park, Byung Ha; No, Hee-Cheon, Transactions of the American Nuclear Society, ANS 2018, pp.959 - 961, American Nuclear Society, 2018-11

7
Strength Degradation of Oxidized Graphite Support Column in VHTR

Park, Byung Ha; No, Hee Cheon, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.47, no.11, pp.998 - 1004, 2010-11

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