Papers by Author: B.J. Min

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Authors: B.J. Min, W.Y. Kim
Abstract: An investigation on the effect of the neutronic behavior on the lattice for a Deuterium Critical Assembly (DCA) in JNC (Japan Nuclear Cycle Development Institute) has been performed. The DCA, the heavy water moderated and light water cooled pressure-tube type research facility, was designed not only for the core physics research, but also for the development of the core-related technology for the Advanced Thermal Reactor (ATR). The core structure of the ATR is highly heterogeneous and it is separated from the heavy water moderator by a calandria tube. Therefore, the neutron behavior is quite complicated and sensitive to a change of the core structure. In this study, the assessment of the core physics characteristics such as the multiplication factor and the void coefficient for the DCA was conducted using the WIMS-D5 code and the results were compared with those of both the experimental data and WIMS-AECL.
Authors: W.Y. Kim, B.J. Min
Abstract: The purpose of this study is to develop a WIMS/CANDU code for a lattice calculation on the basis of WIMS-D5 code for the safety analysis of CANDU reactors. To assess WIMS-D5 applicability to a CANDU reactor, a lattice model was developed for CANDU-6 reactors at the Wolsong site. As for the benchmark of the code validation, a code-to-code comparison was performed between the WIMS-D5 code with both the 69- and 172-energy groups of ENDF/B-VI nuclear data library and the WIMS-AECL code with the 89-energy group. The comparison studies of the reactor physics parameters such as the void reactivity and the coolant/fuel/moderator temperature coefficients were conducted with a change of the internal isotopic composition due to the fuel burning-up using both WIMS-AECL and POWDERPUFS-V (PPV) codes. The results show that the present results from WIMS-D5 code and WIMS-AECL code agreed well with those of the PPV at the beginning of the fuel burn-up phase. As the burning-up progresses, the results of WIMS-D5 show a large deviation from those of PPV for the CANDU 6 reactors.
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