Space and Angular Dependence of Interface Currents in the Multiband-CCCP Method
スポンサーリンク
概要
- 論文の詳細を見る
The present paper discusses the effect on accuracy of eigenvalue by the degree of discretization at the cell boundary within the framework of the multiband-CCCP, a combination of the multiband method and the CCCP method. A study on sensitivity of discretization has been done concerning the dependence of surface flux distribution in space and angular domain, or interface currents. It is found that appropriate discretization with more than five for both of segments and sectors is required to accurately calculate effective cross sections and eigenvalue in the multiband-CCCP method. However, in practice, discretization schemes with one segment and several sectors can be employed with some biases on eigenvalue.The distribution of surface flux at the boundary of a typical PWR-MOX cell has been studied. It is found that discontinuity and strong angular dependence in the distribution of surface flux on the off-centered segments have large influence in the multiband-CCCP method. An improved scheme of angular discretization has been examined for the feasibility to retain calculation accuracy with less degree of discretization in angular domain.
- 社団法人 日本原子力学会の論文
- 2000-07-25
著者
-
TAKEDA Toshikazu
Department of Urology, Keio University School of Medicine
-
Takeda T
Osaka Univ. Osaka
-
Takeda Toshikazu
Department Of Nuclear Engineering Graduate School Of Engineering Osaka University
-
TATSUMI Masahiro
Department of Nuclear Engineering,Graduate School of Engineering,Osaka University
-
GIHOU Akinori
Department of Nuclear Engineering,Graduate School of Engineering,Osaka University
-
Gihou Akinori
Department Of Nuclear Engineering Graduate School Of Engineering Osaka University
-
Tatsumi M
Nuclear Fuel Ind. Ltd. Osaka
-
Takeda Toshikazu
Department of Nuclear Energy, Graduate School of Engineering, Osaka University
関連論文
- Brain metastasis of a papillary renal cell carcinoma, identified as type 2
- Prediction Accuracy Improvement of Neutronic Characteristics of a Breeding Light Water Reactor Core by Extended Bias Factor Methods with Use of FCA-XXII-1 Critical Experiments
- Rapid Estimation of Core-Power Ratio in Coupled-Core System by Rod Drop Method
- Analysis of First-Harmonic Eigenvalue Separation Experiments on KUCA Coupled-Core
- Improvement of Fitting Method of Multiband Parameters for Cell Calculations
- Space and Angular Dependence of Interface Currents in the Multiband-CCCP Method
- Theoretical Study on New Bias Factor Methods to Effectively Use Critical Experiments for Improvement of Prediction Accuracy of Neutronic Characteristics
- Effect of Moderator Density Distribution of Annular Flow on Fuel Assembly Neutronic Characteristics in Boiling Water Reactor Cores
- Nonlinear Behavior under Regional Neutron Flux Oscillations in BWR Cores
- Spatial-harmonic Neutron Spectrum Effect on Frequency-domain Modal Analysis of Regional Stability in BWR
- Heat Transfer Study for Thermal-Hydraulic Design of the Soild-Target of Spallation Neutron Source
- Minor Actinides Incineration by Loading Moderated Targets in Fast Reactor
- Effective Convergence of Fission Source Distribution in Monte Carlo Simulation
- Effect of Radial Void Distribution within Fuel Assembly on Assembly Neutronic Characteristics
- Reaction Rate Calculation in Fast Reactor Blanket Using Multiband S_n Theory
- Effective Cross Section of ^U Samples for Analyzing Doppler Effect Measurements in Fast Critical Assembly
- Evaluation of Eigenvalue Separation by the Monte Carlo Method
- Neutron Anisotropic Scattering Effect in Heterogeneous Cell Calculations of Light Water Reactors
- Estimation of Error Propagation in Monte-Carlo Burnup Calculations
- Transport Calculations of MOX and UO_2 Pin Cells by the Method of Characteristics
- Parametric Study on Fast Reactors with Low Sodium Void Reactivity by the Use of Zirconium Hydride Layer in Internal Blanket
- Sensitivity Analysis for Multiplication Factor Change of LWR Cell Caused by the Differences between JENDL-3.2 and JENDL-3.3
- New Control Rod Homogenization Method for Fast Reactors
- An Improvement of the Transverse Leakage Treatment for the Nodal S_N Transport Calculation Method in Hexagonal-Z Geometry
- Effective Spatial Homogenization with Neutron Leakage Effect for FBR Control Rods
- Transumbilical approach for laparo-endoscopic single-site adrenalectomy : Initial experience and short-term outcome
- Extension of fission product model for use in lattice calculation of thorium fueled BWR.
- Neutron Anisotropic Scattering Effect in Heterogeneous Cell Calculations of Light Water Reactors
- Unified diffusion coefficient for analysis of sodium-void worth in fast critical assembly with control-rod channels.
- Effect of neutron leakage in cell calculations of fast critical assembly.
- Determination of effective diffusion parameters in thermal reactor assemblies.
- Monte-Carlo/Collision Probability Hybrid Method for LWR Fuel Assembly Burnup Calculations.
- Application of improved coarse mesh method to BWR core calculations.
- Application of depletion perturbation theory to fuel loading optimization.
- Approximate Calculation Method for Second Order Sensitivity Coefficient.
- Three-dimensional transport calculation method for eigenvalue problems using diffusion synthetic acceleration.
- Three-dimensional transport correction in fast reactor core analysis.
- Development of three-dimensional transport and diffusion codes based on nodal method.
- Fast Reactor of Negativ Na Void Reactiv and Its Transient Behavior.
- A New Nodal SN Transport Method for Three-Dimensional Hexagonal Geometry.
- Determination of cell averaged diffusion constants based on transport/diffusion perturbation theory.