Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author Park, Byung Ha

Showing results 1 to 7 of 7

1
A unified model for strength degradation of oxidized IG-430 graphite column in VHTR

Park, Byung Ha; No, Hee Cheon, JOURNAL OF NUCLEAR MATERIALS, v.424, no.1-3, pp.132 - 137, 2012-05

2
Design of a Dedicated Nuclear Desalination System: Low Pressure Inherent Heat Sink Nuclear Desalination Plant(LIND)

Kim, Ho Sik; NO, Hee Cheon; Jo, Yugwon; Park, Byung Ha; Choi, Jinyoung; Lee, Jeong Ik; Jeong, Yong Hoon; et al, The 15th International Topical Meeting on Nuclear Reactor Thermalhydraulics(NURETH-15), N.IN.E, 2013-05-13

3
DEVELOPMENT OF CONCRETE ABLATION MODELS FOR GAMMA ASSESSMENT OF TOTAL RCCS FAILURE WITH AN AIR-INGRESS ACCIDENT IN HTGRS

Yoon, Seung Hyun; No, Hee-Cheon; Park, Byung Ha, European Nuclear Conferece 2014 (ENC2014), European Nuclear Society, 2014-05-13

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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