Evaluation of Prediction Error Reduction for Breeding Ratio by Bias Factor Method with Use of Experimental Result on Basic Reaction Rate Ratio
スポンサーリンク
概要
- 論文の詳細を見る
The evaluation technique of prediction error reduction by the bias factor method is extended to the cases where the neutronic property of a target core is related to the properties in critical experiments. This extended procedure can utilize several experimental results, although the conventional procedure utilizes only one experimental result. Calculations were performed where the measured property is the reaction rate ratio of 238U capture to 239Pu fission (C28/F49) in FCA XXII-1 cores and the target core property is C28/F49 or breeding ratio in a breeding light water reactor (BLWR). The prediction error of the breeding ratio in BLWR is reduced from 0.57 to 0.43%, whereas the error of C28/F49 is reduced from 0.72 to 0.19%.
- 社団法人 日本原子力学会の論文
- 2008-03-25
著者
-
TAKEDA Toshikazu
Division of Sustainable Energy and Environmental Engineering, Graduate School of Engineering, Osaka
-
SANO Tadafumi
Nuclear Engineering Science Division, Research Reactor Institute, Kyoto University
-
KITADA Takanori
Division of Sustainable Energy and Environmental Engineering, Graduate School of Engineering, Osaka
-
Takeda Toshikazu
Division Of Sustainable Energy And Environment Engineering Graduate School Of Engineering Osaka Univ
-
Nonaka Nobuhito
Division Of Sustainable Energy And Environmental Engineering Graduate School Of Engineering Osaka Un
-
SANO Tadafumi
Division of Sustainable Energy and Environmental Engineering, Graduate School of Engineering, Osaka
-
Takeda T
Division Of Sustainable Energy And Environmental Engineering Graduate School Of Engineering Osaka Un
-
Sano Tadafumi
Division Of Sustainable Energy And Environmental Engineering Graduate School Of Engineering Osaka Un
-
Sano Tadafumi
Division Of Sustainable Energy And Environment Engineering Graduate School Of Engineering Osaka Univ
-
Kitada T
Division Of Sustainable Energy And Environmental Engineering Graduate School Of Engineering Osaka Un
-
Kitada Takanori
Division Of Sustainable Energy And Environmental Engineering Graduate School Of Engineering Osaka Un
関連論文
- Simple and Efficient Parallelization Method for MOC Calculation
- Determination of Lambda-Mode Eigenvalue Separation of a Thermal Accelerator-Driven System from Pulsed Neutron Experiment
- Measurement and Analysis of ^Am Fission Rate Ratio Relative to ^U Fission Rate in Thermal Neutron Systems Using Kyoto University Critical Assembly
- Measurement of^ Np Fission Rate Ratio Relative to ^U Fission Rate in Cores with Various Thermal Neutron Spectrum at the Kyoto University Critical Assembly
- 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
- Applicability of Constant Flux Approximation in Method of Characteristics with Filtering to Tiny Regions
- 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
- Sensitivity Analysis based on Transport Theory
- Evaluation of Prediction Error Reduction for Breeding Ratio by Bias Factor Method with Use of Experimental Result on Basic Reaction Rate Ratio
- Generalized Bias Factor Method for Accurate Prediction of Neutronics Characteristics
- 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
- A New Uncertainty Reduction Method for Fuel Fabrication Process with Erbia-Bearing Fuel
- Extension of Effective Cross Section Calculation Method for Neutron Transport Calculations in Particle-dispersed Media
- A Complement Proposal for Optimization of Subgroup Parameters
- Parametric Study on Fast Reactors with Low Sodium Void Reactivity by the Use of Zirconium Hydride Layer in Internal Blanket
- Correlation between Cumulative Leaching Ratio and pH of Leachate from Cementation and Plastic Solidified Radwaste Form.
- Determination of Subcritical Reactivity of a Thermal Accelerator-Driven System from Beam Trip and Restart Experiment
- Determination of Subcritical Reactivity of a Thermal Accelerator-Driven System from Beam Trip and Restart Experiment
- Feynman-α Analysis for a Thermal Subcritical Reactor System Driven by an Unstable 14MeV Neutron Source
- Development of efficient Krylov preconditioning techniques for multi-dimensional method of characteristics