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Featured researches published by Chang Keun Jo.


Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 1 | 2008

Development of the CAPP Code Based on the Finite Element Method for the Analysis of VHTR Cores

Hyun-Chul Lee; Chang Keun Jo; Jae Man Noh

In this study, we developed a neutron diffusion equation solver based on the finite element method for CAPP code. Three types of triangular finite elements and five types of rectangular depending on the order of the shape functions were implemented for 2-D application. Ten types of triangular prismatic finite elements and seventeen types of rectangular prismatic finite elements were also implemented for 3-D application. Two types of polynomial mapping from the master finite element to a real finite element were adopted for flexibility in dealing with complex geometry. They are linear mapping and iso-parametric mapping. In linear mapping, only the vertex nodes are used as the mapping points. In iso-parametric mapping, all the nodal points in the finite element are used as the mapping points, which enables the real finite elements to have curved surfaces. For the treatment of spatial dependency of cross-sections in the finite elements, three types of polynomial expansion of the cross-sections in the finite elements were implemented. They are constant, linear, and iso-parametric cross-section expansions. The power method with the Wielandt acceleration technique was adopted as the outer iteration algorithm. The BiCGSTAB algorithm with the ILU (Incomplete LU) decomposition preconditioner was used as the linear equation solver in the inner iteration. The neutron diffusion equation solver developed in this study was verified against two well known benchmark problems, IAEA PWR benchmark problem and OECD/NEA PBMR400 benchmark problem. Results of numerical tests showed that the solution converged to the reference solution as the finite elements are refined and as the order of the finite elements increases. Numerical tests also showed that the higher order finite element method is much efficient than lower order finite element method or finite difference method.Copyright


Annals of Nuclear Energy | 2010

Decay heat analysis of VHTR cores by Monte Carlo core depletion calculation

Hyun-Chul Lee; Chang Keun Jo; Hyung Jin Shim; Yonghee Kim; Jae Man Noh


Annals of Nuclear Energy | 2009

Burnable poison for reactivity management in a very high temperature reactor

Chang Keun Jo; Yonghee Kim; Jae Man Noh


Annals of Nuclear Energy | 2014

Development of the HELIOS/CAPP code system for the analysis of pebble type VHTR cores

Hyun-Chul Lee; Tae Young Han; Chang Keun Jo; Jae Man Noh


Transactions of the american nuclear society | 2007

Optimization of axial fuel shuffling strategy in a block-type VHTR

Yonghee Kim; Chang Keun Jo; Jae Man Noh


Transactions of the american nuclear society | 2009

Evaluations of HTGR Fuel Depletion Benchmarks with Monte Carlo and Deterministic Methods

Yonghee Kim; Chang Keun Jo; Hyun-Chul Lee; Jae Man Noh


Nuclear Engineering and Design | 2014

Homogenized cross section generation considering axial heterogeneity for VHTR fuel block

Tae Young Han; Hyun-Chul Lee; Chang Keun Jo; Jae Man Noh


Archive | 2013

Benchmark analysis of high temperature engineering test reactor core using McCARD code

Chang Joon Jeong; Chang Keun Jo; Hyun-Chul Lee; Jae Man Noh


Transactions of the american nuclear society | 2010

Minimization of the Decay Heat in an MHR for TRU Deep-Burn

Chang Keun Jo; Yonghee Kim; Francesco Venneri; Jae Man Noh


Transactions of the american nuclear society | 2009

Study on TRU Deep-Burn with a Silicon Carbide Inert Matrix Fuel in an MHR

Chang Keun Jo; Yonghee Kim; Francesco Venneri; Jae Man Noh

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Hyun-Chul Lee

Chonnam National University

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Tae Young Han

Seoul National University

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Francesco Venneri

Los Alamos National Laboratory

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Hyung Jin Shim

Seoul National University

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