Estimation of the Doppler Coefficient from a Lower Power Transient Observed in a Zero-Power Reactor Physics Test of a PWR (I) : Methodology
スポンサーリンク
概要
- 論文の詳細を見る
A method for estimating the Doppler coefficient from low power transient data that are measured in a routine experiment conducted in a zero-power reactor physics test of a PWR power plant has been developed. A dynamics identification model was introduced by considering two dynamics components for reactor kinetics and heat removal in the primary coolant loops. The dynamics identification method in the time domain was applied under consideration that the effect of reactivity feedback observed in the experiment was very small and measured transient data contained some intermittent intervals unavailable for dynamics identification. Unknown parameters, including the Doppler coefficient, contained in the dynamics model were determined stepwise through five estimation steps. In these steps, gamma ray noises were removed from the NIS signal, the reactivity feedback component was extracted from reactivity transient, and fuel temperature transient was determined in such way as to reproduce the observed low power transient in the digital simulation. In the final step, the Doppler coefficient was estimated from the extracted reactivity feedback component using the quantities evaluated in the preceding steps. The estimated value agreed well with the value evaluated with a core design code.
- 社団法人 日本原子力学会の論文
- 2009-05-01
著者
-
TSUJI Masashi
Division of Molecular Chemistry, Graduate School of Engineering, Hokkaido University
-
Tsuji Masashi
Graduate School of Engineering, Hokkaido University
-
SHIMAZU Yoichiro
Division of Energy and Environmental System, Graduate School of Engineering, Hokkaido University
-
NARABAYASHI Tadashi
Division of Energy and Environmental System, Graduate School of Engineering, Hokkaido University
-
OHOKA Yasunori
Nuclear Fuel Industries, Ltd.
-
YAMASAKI Masatoshi
Nuclear Fuel Industries, Ltd.
-
HANAYAMA Yasushi
Nuclear Fuel Industries, Ltd.
-
Ohoka Yasunori
Nuclear Fuel Industries Ltd.
-
Tsuji Masashi
Division Of Energy And Environmental System Graduate School Of Engineering Hokkaido University
-
Hanayama Yasushi
Nuclear Fuel Industries Ltd.
-
Tsuji Masashi
Graduate School Of Engineering Hokkaido University
-
Shimazu Yoichiro
Research Institute Of Reactor Engineering University Of Fukui
-
Yamasaki Masatoshi
Nuclear Fuel Industries Ltd.
-
Narabayashi Tadashi
Graduate School Of Engineering Hokkaido University
-
TSUJI Masashi
Hokkaido University
関連論文
- Chiraluty Induction in Cyclopolymerization XVI. Synthesis of Optically Active Poly(methyl acrylate-co-dimethyl fumarate) by Radical Cyclopolymerization of Asymmetrical Nonconjugated Diene Having Chiral pentanediol
- Enantiomer-Selective Radical Polymerization of rac-2,4-Pentanediyl Dimethacrylate by 2,2'-Azobisisobutyronitrile/Copper(II) Trifluoromethanesulfonate/Chiral Diamine as Asymmetric Reverse Atom Transfer Radical Polymerization Initiating System
- Examination of Actual Neutron Count Rate Data during a Control Rod Drop Testing for Estimation of Control Rod Worth in PWRs
- Scale Model Test and Transient Analysis of Steam Injector Driven Passive Core Injection System for Innovative-Simplified Nuclear Power Plant
- Stability Monitoring for BWR based on Singular Value Decomposition Method using Artificial Neural Network
- Estimation of the Doppler Coefficient from a Lower Power Transient Observed in a Zero-Power Reactor Physics Test of a PWR (I) : Methodology
- Estimating Temperature Reactivity Coefficients by Experimental Procedures Combined with Isothermal Temperature Coefficient Measurements and Dynamic Identification
- Feasibility of Continuous Sub-criticality Monitoring using a Digital Reactivity Meter to Overcome the Criticality Accident
- ICONE11-36466 STUDY OF THE EFFECT OF AXIAL NEUTRON SOURCE DISTRIBUTION ON THE DETECTOR SIGNAL FOR A MODIFIED NEUTRON SOURCE MULTIPLICATION METHOD
- A New Uncertainty Reduction Method for Fuel Fabrication Process with Erbia-Bearing Fuel
- Sensitivity Analysis for Multiplication Factor Change of LWR Cell Caused by the Differences between JENDL-3.2 and JENDL-3.3
- Some Technical Issues on Continuous Subcriticality Monitoring by a Digital Reactivity Meter during Criticality Approach
- Examination of Actual Neutron Count Rate Data during a Control Rod Drop Testing for Estimation of Control Rod Worth in PWRs
- JENDL-4.0 Benchmarking for Effective Delayed Neutron Fraction of Fast Neutron Systems
- Study on Turbulent Behavior of Water Jet in Supersonic Steam Injector
- JENDL-4.0 Benchmarking for Effective Delayed Neutron Fraction of Fast Neutron Systems
- Efficient fission neutron spectrum matrix representation by singular value decomposition technique