Statistical Optimization of Nuclear Reactor System by Means of Modal Analysis Method
スポンサーリンク
概要
- 論文の詳細を見る
This paper deals with the optimization of a nuclear reactor system with consideration of neutron flux uncertainty. Using the average and two kinds of variance of neutron flux which are obtained by means of modal analysis technique, the author has formulated the maximization of average power output under the condition to make the uncertainty of neutron flux as small as possible and presented Mode Optimization Technique for the optimization problem of a distributive system. Numerical results show that the optimal distribution of average neutron flux is not always flat when we consider the uncertainty of neutron flux as a loss of safety or reliability of a nuclear reactor. The author finally points out some problems concerning the performance index for this statistical optimization of a nuclear reactor system.
- 一般社団法人日本機械学会の論文
著者
-
Hara Fumio
Faculty Of Engineering Department Of Mechanical Engineering Science University Of Tokyo
-
HARA Fumio
Faculty of Engineering, Science University of Tokyo
関連論文
- Unsteady Fluid Force Acting on Two Tandem Circular Cylinders Subjected to Two-Phase Cross-Flow
- Analysis of the Neural Network Recognition Characteristics of 6 Basic Facial Expressions
- Experimental Study on Active Suppression by Gas Bubble Injection for Earthquake Induced Sloshing in Tanks : Vibration, Control Engineering, Engineering for Industry
- Two-Phase-Flow-Induced Vibrations in a Horizontal Pulping System
- Statistical Optimization of Nuclear Reactor System by Means of Modal Analysis Method