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Results 1-10 of 85 (Search time: 0.006 seconds).

NO Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date)
1
Long-cycle and high-burnup fuel assembly for the VHTR

Kim, Yongheeresearcher; Cho, C; Venneri, F, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.44, pp.294 - 302, 2007-03

2
Convergence analysis of the nonlinear coarse-mesh finite difference method for one-dimensional fixed-source neutron diffusion problem

Lee, DJ; Downar, TJ; Kim, Yongheeresearcher, NUCLEAR SCIENCE AND ENGINEERING, v.147, no.2, pp.127 - 147, 2004-06

3
A nodal and finite difference hybrid method for pin-by-pin heterogeneous three-dimensional light water reactor diffusion calculations

Lee, DJ; Downar, TJ; Kim, Yongheeresearcher, NUCLEAR SCIENCE AND ENGINEERING, v.146, no.3, pp.319 - 339, 2004-03

4
Renormalization of power and burnup independent shape annealing function for excore detectors

Park, Moon-Ghu; Shin, Ho-Cheol; Choi, Yu-Sun; Park, Dong-Hwan; Kim, Yongheeresearcher, ANNALS OF NUCLEAR ENERGY, v.36, no.11-12, pp.1753 - 1759, 2009-12

5
A neutronic feasibility study on Be-free He-cooled solid breeder blanket

Han, B; Kim, Yongheeresearcher; Hong, BG; Kim, CH, FUSION ENGINEERING AND DESIGN, v.81, no.1-7, pp.725 - 728, 2006-02

6
A neutronic investigation of He-cooled liquid Li-breeder blankets for fusion power reactor

Kim, Yongheeresearcher; Hong, BG; Kim, CH, FUSION ENGINEERING AND DESIGN, v.75-79, pp.1067 - 1070, 2005-11

7
SYSTEM DESIGN AND ANALYSIS OF A 900-MW(thermal) LEAD-COOLED FAST REACTOR

Kim, SJ; Kim, Yongheeresearcher; Hong, S; Cho, CH; Eoh, JH; Kim, JB; Wi, MH; Ha, KS; Kim, EK, NUCLEAR TECHNOLOGY, v.170, no.1, pp.148 - 158, 2010-04

8
Burnable poison for reactivity management in a very high temperature reactor

Jo, Chang Keun; Kim, Yongheeresearcher; Noh, Jae Man, ANNALS OF NUCLEAR ENERGY, v.36, no.3, pp.298 - 304, 2009-04

9
Development of a tokamak reactor system code and its application for concept development of a demo reactor

Hong, Bong Guen; Lee, Dong Won; Kim, Suk-Kwon; Kim, Yongheeresearcher, FUSION ENGINEERING AND DESIGN, v.83, no.10-12, pp.1615 - 1618, 2008-12

10
Thermo-fluid investigation on a double-side-cooled annular fuel for the prismatic very high temperature gas-cooled reactor

Tak, Nam-Il; Kim, Yongheeresearcher; Choi, Jae-Hyuk; Lee, Won Jae, NUCLEAR ENGINEERING AND DESIGN, v.238, no.10, pp.2821 - 2827, 2008-10

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