Reaction Rate Calculation in Fast Reactor Blanket Using Multiband S_n Theory
スポンサーリンク
概要
- 論文の詳細を見る
A new method was applied to calculation of reaction rates in blanket of LMFBR using the multiband Sn theory. This procedure leads to the use of direction dependent total micro cross sections, which advances the penetration of neutrons into the blanket.Test calculation with RZ model of a prototype fast reactor shows that reaction rates tend to rise with the penetration into blanket compared to the conventional multigroup calculation: the maximum difference was about 3% for 238U capture, 4% for 235U fission, 4% for 239Pu fission, and less than 1% for 238U fission. This tendency shows the same direction as the difference observed between the continuous energy Monte Carlo method and the conventional method.
- 社団法人 日本原子力学会の論文
著者
-
TAKEDA Toshikazu
Department of Urology, Keio University School of Medicine
-
YAMAMOTO Toshihisa
Department of Nuclear Engineering, Graduate School of Engineering, Osaka University
-
Takeda Toshikazu
Department Of Nuclear Engineering Graduate School Of Engineering Osaka University
-
Takeda T
Division Of Sustainable Energy And Environmental Engineering Graduate School Of Engineering Osaka Un
-
Yamamoto Toshihisa
Department Of Nuclear Engineering 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
- Evaluation of Prediction Error Reduction for Breeding Ratio by Bias Factor Method with Use of Experimental Result on Basic Reaction Rate Ratio
- 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
- Three Year Experimental Study on Leaching Behavior from Low Level Radioactive Plastic-Based Waste
- 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
- Production of Pure ^Pu Tracer for the Assessment of Plutonium in the Environment
- Sensitivity Analysis for Multiplication Factor Change of LWR Cell Caused by the Differences between JENDL-3.2 and JENDL-3.3
- Correlation between Cumulative Leaching Ratio and pH of Leachate from Cementation and Plastic Solidified Radwaste Form.
- An Improvement of the Transverse Leakage Treatment for the Nodal S_N Transport Calculation Method in Hexagonal-Z Geometry
- Background-Cross-Section-Dependent Subgroup Parameters
- A Generalized Approach to Optimize Subgroup Parameters
- 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
- Background-Cross-Section-Dependent Subgroup Parameters
- Three-dimensional transport calculation method for eigenvalue problems using diffusion synthetic acceleration.