Browse by Subject HTGR

Showing results 1 to 11 of 11

1
A review of helium gas turbine technology for high-temperature gas-cooled reactors

No, Hee Cheon; Kim, Ji Hwan; Kim, Hyeun Min, NUCLEAR ENGINEERING AND TECHNOLOGY, v.39, no.1, pp.21 - 30, 2007-02

2
(A) gas turbine code for off-design performance and transient analysis of high-temperature gas-cooled reactors = 가스터빈 탈설계점 성능예측 및 고온가스로의 천이해석을 위한 코드 개발link

Kim, Ji-Hwan; 김지환; et al, 한국과학기술원, 2008

3
(A) study on transport behavior analysis of fission products in a VHTR = 초고온가스냉각로에서 핵분열생성물의 수송거동해석에 관한 연구link

Jeong, Hye-Dong; 정혜동; et al, 한국과학기술원, 2010

4
Effects of aging in high temperature helium environments on room temperature tensile properties of nickel-base superalloys

Kim, Daejong; Sah, Injin; Jang, Changheui, MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, v.528, no.3, pp.1713 - 1720, 2011-01

5
Estimation of graphite density and mechanical strength variation of VHTR during air-ingress accident

Kim, Eung Soo; No, Hee Cheon; Kim, Byung Joon; Oh, Chang H., NUCLEAR ENGINEERING AND DESIGN, v.238, no.4, pp.837 - 847, 2008-04

6
ESTIMATION OF THE FISSION PRODUCTS, ACTINIDES AND TRITIUM OF HTR-10

Jeong, Hyedong; Chang, Soon-Heung, NUCLEAR ENGINEERING AND TECHNOLOGY, v.41, no.5, pp.729 - 738, 2009-06

7
High Temperature Oxidation Behavior of Alloy 617 and Haynes 230 in Impurity-Controlled Helium Environments

Kim, Dae-Jong; Sah, In-Jin; Kim, Dong-Hoon; Ryu, Woo-Seog; Jang, Chang-Heui, OXIDATION OF METALS, v.75, no.1-2, pp.103 - 119, 2011-02

8
HORIZON EXPANSION OF THERMAL-HYDRAULIC ACTIVITIES INTO HTGR SAFETY ANALYSIS INCLUDING GAS-TURBINE CYCLE AND HYDROGEN PLANT

No, Hee Cheon; Yoon, Ho Joon; Kim, Seong Jun; Lee, Byeng Jin; Kim, Ji Hwan; Kim, Hyeun Min; Lim, Hong Sik, Nuclear Engineering and Technology, v.41, no.7, pp.875 - 884, 2009-09

9
Modeling of the thermal and mechanical fracture of the SiC layer in TRISO-coated particle fuel = TRISO 연료입자에서 SiC층의 열.기계적 파손 기제 모델링link

Jeong, Hye-Dong; 정혜동; et al, 한국과학기술원, 2006

10
Nuclear-thermal analysis of a unit fuel element in HTGRs based on two-temperature homogenized model = 두 온도 균질화법에 의한 고온가스로 핵연료요소체의 핵열해석link

Yu, Hui; 유휘; et al, 한국과학기술원, 2010

11
Safety analysis of LOCA, transients and tritium permeation in hydrogen production HTGR : 수소 생산 고온 가스로의 LOCA, 천이 및 삼중수소 투과에 대한 안전해석연구 = 수소 생산 고온 가스로의 LOCA, 천이 및 삼중수소 투과에 대한 안전해석연구link

, 한국과학기술원, 2012

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