Estimating Temperature Reactivity Coefficients by Experimental Procedures Combined with Isothermal Temperature Coefficient Measurements and Dynamic Identification
スポンサーリンク
概要
- 論文の詳細を見る
A method to evaluate the moderator temperature coefficient (MTC) and the Doppler coefficient through experimental procedures performed during reactor physics tests of PWR power plants is proposed. This method combines isothermal temperature coefficient (ITC) measurement experiments and reactor power transient experiments at low power conditions for dynamic identification. In the dynamic identification, either one of temperature coefficients can be determined in such a way that frequency response characteristics of the reactivity change observed by a digital reactivity meter is reproduced from measured data of neutron count rate and the average coolant temperature. The other unknown coefficient can also be determined by subtracting the coefficient obtained from the dynamic identification from ITC. As the proposed method can directly estimate the Doppler coefficient, the applicability of the conventional core design codes to predict the Doppler coefficient can be verified for new types of fuels such as mixed oxide fuels.The digital simulation study was carried out to show the feasibility of the proposed method. The numerical analysis showed that the MTC and the Doppler coefficient can be estimated accurately and even if there are uncertainties in the parameters of the reactor kinetics model, the accuracies of the estimated values are not seriously impaired.
- 社団法人 日本原子力学会の論文
- 2006-05-25
著者
-
Tsuji Masashi
Graduate School of Engineering, Hokkaido University
-
YAMASAKI Masatoshi
Nuclear Fuel Industries, Ltd.
-
HANAYAMA Yasushi
Nuclear Fuel Industries, Ltd.
-
TSUJI Masashi
Laboratory of Nuclear Reactor Engineering, Graduate School of Engineering, Hokkaido University
-
AOKI Yukinori
Laboratory of Nuclear Reactor Engineering, Graduate School of Engineering, Hokkaido University
-
SHIMAZU Yoichiro
Laboratory of Nuclear Reactor Engineering, Graduate School of Engineering, Hokkaido University
-
Tsuji Masashi
Division Of Energy And Environmental System Graduate School Of Engineering Hokkaido University
-
Aoki Yukinori
Laboratory Of Nuclear Reactor Engineering 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.
-
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
- 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
- JENDL-4.0 Benchmarking for Effective Delayed Neutron Fraction of Fast Neutron Systems
- Efficient fission neutron spectrum matrix representation by singular value decomposition technique