Woosong Kim
Current Organizations / Institutes
The organizations/institutes from the scholar's latest article
Previous Organizations / Institutes
The organizations / institutes from the scholar's other articles in the past ten years
Woosong Kim has a total of 9 co-authors. Here are the top co-authors by number of shared publications:
- Yonghee Kim
Korea Advanced Institute of Science and Technology
5 shared publications Mohammad Abdul Motalab
Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology (KAIST), 291 Daehak-ro, Yuseong-gu, Daejeon 34141, Republic of Korea
2 shared publicationsYonghee Kim
2 shared publications- Donny Hartanto
ORNL
1 shared publication Hwanyeal Yu
1 shared publication- Hyeon Tae Kim
Korea Advanced Institute of Science and Technology (KAIST)
1 shared publication
Latest Publications
- 1 July 2019
- Published by Elsevier in Annals of Nuclear Energy
- Vol. 129, 30-55
A leakage correction with SPH factors for two-group constants in GET-based pin-by-pin reactor analyses
- 1 July 2019
- Published by Elsevier in Annals of Nuclear Energy
- Vol. 129, 30-55
A leakage correction with SPH factors for two-group constants in GET-based pin-by-pin reactor analyses
- 2 January 2019
- Published by Taylor & Francis in Nuclear Science and Engineering
- Vol. 193 (5) , 441-452
Generation of Exact Discontinuity Factors for NEM Calculations with Two-by-Two Division per Fuel Assembly
This paper suggests novel approaches to generate exact discontinuity factors (DFs) for transverse-integrated nodal analyses with a two-by-two node configuration in a homogenized fuel assembly (FA). We have shown that the conventional DF calculation scheme cannot generate exact DFs with the nodal expansion method (NEM) calculation when a FA is subdivided into two-by-two nodes due to the inherent discrepancy between the transport-based heterogeneous analysis and the diffusion-based NEM calculation. In order to overcome the difference, an iterative, two-node NEM sweeping method is proposed. In addition, three different formulations to define a single representative DF per assembly surface for the two-by-two NEM are suggested for convenient application for the existing nodal codes while maintaining enough accuracy. Numerical assessments with a colorset model and small modular reactor cores with 16 × by × 16 FAs show that the iterative two-node NEM sweep method successfully corrects the error caused by an inherent discrepancy between the transport and the diffusion method. Among the candidates of a single representative DF, the net current weighted average DFs are found to be the most adequate.
- 2 January 2019
- Published by Taylor & Francis in Nuclear Science and Engineering
- Vol. 193 (5) , 441-452
Generation of Exact Discontinuity Factors for NEM Calculations with Two-by-Two Division per Fuel Assembly
This paper suggests novel approaches to generate exact discontinuity factors (DFs) for transverse-integrated nodal analyses with a two-by-two node configuration in a homogenized fuel assembly (FA). We have shown that the conventional DF calculation scheme cannot generate exact DFs with the nodal expansion method (NEM) calculation when a FA is subdivided into two-by-two nodes due to the inherent discrepancy between the transport-based heterogeneous analysis and the diffusion-based NEM calculation. In order to overcome the difference, an iterative, two-node NEM sweeping method is proposed. In addition, three different formulations to define a single representative DF per assembly surface for the two-by-two NEM are suggested for convenient application for the existing nodal codes while maintaining enough accuracy. Numerical assessments with a colorset model and small modular reactor cores with 16 × by × 16 FAs show that the iterative two-node NEM sweep method successfully corrects the error caused by an inherent discrepancy between the transport and the diffusion method. Among the candidates of a single representative DF, the net current weighted average DFs are found to be the most adequate.
- 21 August 2018
- Published by Taylor & Francis in Nuclear Science and Engineering
- Vol. 192 (1) , 1-20
Functionalization of the Discontinuity Factor in the Albedo-Corrected Parameterized Equivalence Constants (APEC) Method
The Albedo-corrected Parameterized Equivalence Constants (APEC) method, a new leakage correction method for two-group nodal analysis of light water reactors, has been extended to discontinuity factor (DF) correction. First, the error of nodal calculations induced by an inaccurate assembly discontinuity factor (ADF) is evaluated using the reference two-group cross section (XS) and DF calculated from heterogeneous core transport calculations. Functionalization of DF is performed by finding relationships between surfacewise current-to-flux ratio and change of DF from ADF. The least-squares method is used to fit several candidate functions to various core calculation results. The coefficients of APEC XS and DF correction functions are determined considering several color-set models. In this work, the two-dimensional method of characteristics–based lattice code DeCART2D is used for reference core calculations and lattice calculations. The extended APEC method is implemented in an in-house NEM nodal code using the partial-current coarse mesh finite difference acceleration. A small modular reactor (SMR) initial core benchmark is analyzed to evaluate the performance of the extended APEC method. In addition, the extended APEC method is applied to several variants of the SMR core and large variants to assess its general applicability.
- 21 August 2018
- Published by Taylor & Francis in Nuclear Science and Engineering
- Vol. 192 (1) , 1-20
Functionalization of the Discontinuity Factor in the Albedo-Corrected Parameterized Equivalence Constants (APEC) Method
The Albedo-corrected Parameterized Equivalence Constants (APEC) method, a new leakage correction method for two-group nodal analysis of light water reactors, has been extended to discontinuity factor (DF) correction. First, the error of nodal calculations induced by an inaccurate assembly discontinuity factor (ADF) is evaluated using the reference two-group cross section (XS) and DF calculated from heterogeneous core transport calculations. Functionalization of DF is performed by finding relationships between surfacewise current-to-flux ratio and change of DF from ADF. The least-squares method is used to fit several candidate functions to various core calculation results. The coefficients of APEC XS and DF correction functions are determined considering several color-set models. In this work, the two-dimensional method of characteristics–based lattice code DeCART2D is used for reference core calculations and lattice calculations. The extended APEC method is implemented in an in-house NEM nodal code using the partial-current coarse mesh finite difference acceleration. A small modular reactor (SMR) initial core benchmark is analyzed to evaluate the performance of the extended APEC method. In addition, the extended APEC method is applied to several variants of the SMR core and large variants to assess its general applicability.
- 18 August 2017
- Published by Taylor & Francis in Nuclear Science and Engineering
- Vol. 188 (3) , 207-245
Improvement of Nodal Accuracy by Using Albedo-Corrected Parameterized Equivalence Constants
- 18 August 2017
- Published by Taylor & Francis in Nuclear Science and Engineering
- Vol. 188 (3) , 207-245
Improvement of Nodal Accuracy by Using Albedo-Corrected Parameterized Equivalence Constants
- 1 August 2016
- Published by Elsevier in Annals of Nuclear Energy
- Vol. 94, 793-801
Improvement of CANDU safety parameters by using the CANFLEX fuel
- 1 August 2016
- Published by Elsevier in Annals of Nuclear Energy
- Vol. 94, 793-801
Improvement of CANDU safety parameters by using the CANFLEX fuel
- Open Access
- 1 June 2016
- Published by Elsevier in Nuclear Engineering and Technology
- Vol. 48 (3) , 642-649
A Lattice-Based Monte Carlo Evaluation of Canada Deuterium Uranium-6 Safety Parameters
- 1 June 2016
- Published by Elsevier in Nuclear Engineering and Technology
- Vol. 48 (3) , 642-649
Open AccessA Lattice-Based Monte Carlo Evaluation of Canada Deuterium Uranium-6 Safety Parameters
- 1 December 2015
- Published by Elsevier in Nuclear Engineering and Design
- Vol. 295, 127-137
Evaluation of CANDU6 PCR (power coefficient of reactivity) with a 3-D whole-core Monte Carlo Analysis
- 1 December 2015
- Published by Elsevier in Nuclear Engineering and Design
- Vol. 295, 127-137
Evaluation of CANDU6 PCR (power coefficient of reactivity) with a 3-D whole-core Monte Carlo Analysis