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Analytic Modeling of the Xenon Oscillation Due to Control Rod Movement
Song, Jae-Seung,Cho, Nam-Zin,Zee, Sung-Quun Korean Nuclear Society 1999 Nuclear Engineering and Technology Vol.31 No.1
An analytic axial xenon oscillation model was developed for pressurized water reactor analysis. The model employs an equation system for axial difference parameters that was derived from the two-group one-dimensional diffusion equation with control rod modeling and coupled with xenon and iodine balance equations. The spatial distributions of nu, xenon, and iodine were expanded by the Fourier sine series, resulting in cancellation of the flux-xenon coupled non-linearity. An inhomogeneous differential equation system for the axial difference parameters, which gives the relationship between power, iodine and xenon axial differences in the case of control rod movement, was derived and solved analytically. The analytic solution of the axial difference parameters can directly provide with the variation of axial power difference during xenon oscillation. The accuracy of the model is verified by benchmark calculations with one-dimensional reference core calculations.
Assessment of RANS Models for 3-D Flow Analysis of SMART
Chun Kun Ho,Hwang Young Dong,Yoon Han Young,Kim Hee Chul,Zee Sung Quun Korean Nuclear Society 2004 Nuclear Engineering and Technology Vol.36 No.3
Turbulence models are separately assessed for a three dimensional thermal-hydraulic analysis of the integral reactor SMART. Seven models (mixing length, k-l, standard $k-{\epsilon},\;k-{\epsilon}-f{\mu},\;k-{\epsilon}-v2$, RRSM, and ERRSM) are investigated for flat plate channel flow, rotating channel flow, and square sectioned U-bend duct flow. The results of these models are compared to the DNS data and experiment data. The results are assessed in terms of many aspects such as economical efficiency, accuracy, theorization, and applicability. The standard $k-{\epsilon}$ model (high Reynolds model), the $k-{\epsilon}-v2$ model, and the ERRSM (low Reynolds models) are selected from the assessment results. The standard $k-{\epsilon}$ model using small grid numbers predicts the channel flow with higher accuracy in comparison with the other eddy viscosity models in the logarithmic layer. The elliptic-relaxation type models, $k-{\epsilon}-v2$, and ERRSM have the advantage of application to complex geometries and show good prediction for near wall flows.
Monte Carlo Resonance Treatment for the Deterministic Transport Lattice Codes
Kim Kang-Seog,Lee Chung Chan,Chang Moon Hee,Zee Sung Quun Korean Nuclear Society 2003 Nuclear Engineering and Technology Vol.35 No.6
Transport lattice codes require the resonance integral tables for the resonant nuclides where the resonance integral is a function of the background cross section and can be prepared through a special program solving the slowing down equation. In case the cross section libraries do not include the resonance integral table for the resonant nuclides, the computational prediction produces a large error. We devised a new method using a Monte Carlo calculation for the effective resonance cross sections to solve this problem provisionally. We extended this method to obtain the resonance integral table for general purpose. The MCNP code is used for the effective resonance integrals and the LIBERTE code for the effective background cross sections. We modified the HELIOS library with the effective cross sections and the resonance integral tables obtained by the newly developed Monte Carlo method, and performed sample calculations using HELIOS and LIBERTE. The results showed that this method is very effective for the resonance treatment.
SMART - P 안전해석 전산 코드인 TASS / SMR 의 HLA 적용에 관한 연구
김희경(Hee-Kyung Kim),김희철(Hee-Cheol Kim),지성균(Sung-Quun Zee),김현수(Hyeon-Soo Kim) 한국정보과학회 2005 한국정보과학회 학술발표논문집 Vol.32 No.1
본 논문에서는 최근에 각광을 받고 있는 HLA의 연구 현황을 파악하고 HLA의 기본 개념, 구성 요소, HLA를 이용한 시뮬레이션의 개발 방법 등에 대하여 조사하였다. 그리고 SMART-P 안전해석 전산코드인 TASS/SMR을 HLA에 적용하기 위한 방법에 대하여 기술하였으며 랩퍼 (Wrapper)를 사용하여 TASS/SMR을 HLA에 적용하여 보았다. 이러한 연구 결과로 TASS/SMR을 HLA에 적용, 구현하여 실행됨을 확인하였으며 그 결과로 레거 시 코드를 HLA에 적용할 수 있는 방향을 제시하였다.
SHIELDING DESIGN ANALYSES FOR SMART CORE WITH 49-CEDM
Kim, Kyo-Youn,Kim, Ha-Yong,Cho, Byung-Oh,Zee, Sung-Quun,Chang, Moon-Hee 대한방사선 방어학회 2001 방사선방어학회지 Vol.26 No.3
In Korea, an advanced reactor system of 330MWt power called SMART (System integrated Modular Advanced ReacTor) is being developed by KAERI to supply energy for seawater desalination as well as electricity generation. A shielding design of the SMART core with 49 CEDM is established by a two-dimensional discrete ordinates radiation transport analyses. The DORT two-dimensional discrete ordinates transport code is used to evaluate the SMART shielding designs. Three axial regions represent the SMART reactor assembly, each of which is modeled in the R-Z geometry. The BUGLE-96 library is used in the analyses, which consists of 47 neutron and 20 gamma energy groups. The results indicate that the maximum neutron fluence at the bottom of reactor vessel is 5.89 × 1017 n/cm2 and that on the radial surface of reactor vessel is 4.49×1016 n/cm2. These results meet the requirement, 1.0×1020 n/cm2, in 10 CFR 50.61 and the integrity of SMART reactor vessel during the lifetime of the reactor is confirmed.
Current Conservation Factors for Consistent One-Dimensional Neutronics Modeling
Lee, Kibog,Joo, Han-Gyu,Cho, Byung-Oh,Zee, Sung-Quun Korean Nuclear Society 2000 Nuclear Engineering and Technology Vol.32 No.3
A one-dimensional neutronics formulation is established within the framework of the nonlinear analytic nodal method such that it can result in consistent one-dimensional models that produce the same axial information as their corresponding reference three-dimension81 models. Consistency is achieved by conserving axial interface currents as well as the planar reaction rates of the three-dimensional case. For current conservation, flux discontinuity is introduced in the solution of the two-node problem. The degree of discontinuity, named the current conservation factor, is determined such that the surface averaged axial current of the reference three-dimensional case can be retrieved from the two-node calculation involving the radially collapsed group constants and the discontinuity factor. The current conservation factors are derived from the analytic nodal method and various core configurations are analyzed to show that the errors in K-eff and power distributions can be reduced by a order of magnitude by the use of the current conservation factor with no significant computational overhead.