Rapid Estimation of Core-Power Ratio in Coupled-Core System by Rod Drop Method
スポンサーリンク
概要
- 論文の詳細を見る
To determine rapidly the core-power ratio in a coupled-core system, a method is proposed on the basis of the control rod drop experiment. A formula of an asymmetrical two-point version was derived to deduce the core-power ratio and subcriticalities of the individual cores. It requires only a familiar measurement technique and tools for the conventional rod drop experiment to apply this formula for the purpose of obtaining these quantities. The present method was applied to the rod drop data measured in coupled-core systems, where the core-power ratio sensitively depended on the rod patterns. The validity of the proposed method was experimentally demonstrated through the comparison between the measured core-power ratios obtained by the present method and that derived from the flux distribution measurement.
- 社団法人 日本原子力学会の論文
- 2000-07-25
著者
-
宇根崎 博信
京大 炉
-
SHIROYA Seiji
Research Reactor Institute, Kyoto University
-
Shiroya S
Nuclear Engineering Science Division Research Reactor Institute Kyoto University
-
Shiroya S
Nuclear Energy Science Division Reserch Ractor Institute Kyoto University
-
Shiroya S
Research Reactor Institute Kyoto University
-
Shiroya S
Kyoto Univ.
-
Shiroya S
Kyoto Univ. Osaka
-
Shiroya Seiji
Nuclear Engineering Science Division Research Reactor Institute Kyoto University
-
Shiroya Seiji
Research Reactor Institute Kyoto University
-
TAKEDA Toshikazu
Department of Urology, Keio University School of Medicine
-
HORIGUCHI Tetsuo
Atomic Energy Research Institute, Kinki University
-
YAMAMOTO Junji
Department of Surgery, National Cancer Center Hospital
-
SANO Tadafumi
Nuclear Engineering Science Division, Research Reactor Institute, Kyoto University
-
HASHIMOTO Kengo
Atomic Energy Research Institute, Kinki University
-
Shiroya Seiji
Nuclear Energy Science Division Reserch Ractor Institute Kyoto University
-
UNESAKI Hironobu
Research Reactor Institute, Kyoto University
-
KITADA Takanori
Department of Sustainable Energy and Environmental Engineering, Graduate School of Engineering, Osak
-
SANO Tadafumi
Department of Nuclear Engineering,Graduate School of Engineering,Osaka University
-
AIZAWA Otohiko
Department of Energy Science and Engineering,Musashi Institute of Technology
-
Takeda Toshikazu
Department Of Nuclear Engineering Graduate School Of Engineering Osaka University
-
Yamamoto Junji
Department Of Electrical Engineering Setsunan University
-
Aizawa Otohiko
Department Of Energy Science And Engineering Musashi Institute Of Technology
-
Takeda T
Division Of Sustainable Energy And Environmental Engineering Graduate School Of Engineering Osaka Un
-
Horiguchi Tetsuo
Atomic Energy Research Institute Kinki University
-
Unesaki Hironobu
Nuclear Energy Science Division Research Reactor Institute Kyoto University
-
Unesaki Hironobu
Research Reactor Institute Kyoto University
-
Sano Tadafumi
Division Of Sustainable Energy And Environmental Engineering Graduate School Of Engineering Osaka Un
-
Kitada T
Division Of Sustainable Energy And Environmental Engineering Graduate School Of Engineering Osaka Un
-
Kitada Takanori
Department Of Nuclear Engineering Graduate School Of Engineering
-
Hashimoto Kengo
Atomic Energy Research Institute Kinki University
-
Unesaki H
Nuclear Engineering Science Division Research Reactor Institute Kyoto University
-
Hashimoto K
Interdisciplinary Graduate School Of Science And Engineering Kinki University
-
Hashimoto Kengo
Interdisciplinary Graduate School Of Science And Engineering Kinki University
-
Takeda Toshikazu
Department of Nuclear Energy, Graduate School of Engineering, Osaka University
関連論文
- Reaction rate analysis of nuclear spallation reactions generated by 150, 190, and 235 MeV protons
- Reaction Rate Analyses for an Accelerator-Driven System with 14MeV Neutrons in the Kyoto University Critical Assembly
- Preliminary Experiments on Accelerator-Driven Subcritical Reactor with Pulsed Neutron Generator in Kyoto University Critical Assembly
- A New Experimental Correction Method for the First-Order Perturbation Approximation in the Steady Subcritical Reactor
- 光ファイバー検出器を用いた高速炉体系の中性子束分布の精密測定 (原子炉の高度化に関する研究)
- 光ファイバー検出器を用いた高速炉体系の中性子束分布測定実験 (原子炉の高度化に関する研究)
- A Long and Slender Position-Sensitive Helium-3 Proportional Counter with an Anode Wire Supported by a Ladder-Shaped Solid Insulator
- Development of Land Mine Detector System Based on the Measurements of Capture γ-Rays with Anticoincidence and Coincidence Methods
- FFAG-KUCA結合加速器駆動未臨界体系の炉物理実験 (京都大学原子炉実験所第44回学術講演会報文集)
- 京都大学臨界集合体実験装置(KUCA)を用いた技術職員研修
- 京都大学臨界集合体実験装置(KUCA)大学院実験テキスト
- Joint Reactor Laboratory Course for Students in KUCA
- KUCA臨界実験解析によるJENDL-3.3ライブラリの臨界性評価精度検証
- KUCAを用いた加速器駆動未臨界炉に関する研究
- 光ファイバー検出器を用いた高速炉体系の中性子束分布の精密測定 (原子炉の高度化に関する研究)
- 保安教育 (京都大学原子炉実験所平成14年度技術室受入研修報告書)
- 光ファイバ検出器を用いた中性子束分布測定実験 (一般共同研究・一般協力研究) -- (原子炉の高度化に関する研究)
- Brain metastasis of a papillary renal cell carcinoma, identified as type 2
- Microdosimetry on a Mini-Reactor UTR-KINKI for Educational Uses and Biological Researches
- Effect of Heavy Alcohol Intake on Long-term Results after Curative Resection of Hepatitis C Virus-related Hepatocellular Carcinoma
- First Injection of Spallation Neutrons Generated by High-Energy Protons into the Kyoto University Critical Assembly
- Static and Kinetic Experiments on Accelerator-Driven System with 14MeV Neutrons in Kyoto University Critical Assembly
- Experiments and Analyses for Relationship between Flux Tilt in Two-Energy-Group Model and First-Mode Eigenvalue Separation
- Determination of Lambda-Mode Eigenvalue Separation of a Thermal Accelerator-Driven System from Pulsed Neutron Experiment
- Measurements and Analysis of Neutron Flux Distribution in UTR-KINKI
- Research Project on Accelerator-driven Subcritical System Using FFAG Accelerator and Kyoto University Critical Assembly
- Reactor Noise Experiments by Using Acquisition System for Time Series Data of Pulse Train
- Extended Left Hepatectomy by Severing All Major Hepatic Veins with Reconstruction of the Right Hepatic Vein
- Surgery for multiple hepatic colorectal metastases
- 核データ・炉物理の視点から (特集 今何故トリウムか)
- Measurement of Flux Tilt and Eigenvalue Separation in axially Decoupled Core
- 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
- 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
- Reaction Rate Analysis of Nuclear Spallation Reactions Generated by 150, 190, and 235 MeV Protons
- Dead-Time Measurement for Radiation Counters by Variance-to-Mean Method
- Assessment of ^Th Nuclear Data through Analysis of Thorium-loaded Critical Experiments in Thermal-Neutron Systems using the Kyoto University Critical Assembly
- 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
- Localized Nodular Idiopathic Retroperitoneal Fibrosis : Successful Treatment with Surgical Resection
- Measurement of Fuel Importance Distribution in Non-uniformly Distributed Fuel Systems
- SYNTHESIS OF VALPROYL-2-PYRROLIDINONE AND ITS EVALUATION AS A COGNITIVE DRUG WITH THE ABILITY TO MODULATE ACIDIC AMINO ACIDS IN THE BRAIN
- Measurements of Reaction Rate Ratios as Indexes of Breeding Performance in Mock-up Cores of FCA Simulating Metallic-fueled LMFBR and MOX-fueled LMFBR
- Nuclear Design Study on a Super High-burnup Fuel Assembly for Pressurized Water Reactors Using Transuranium
- Analysis of Experiment on Temperature Coefficient of Reactivity in Light-Water-Moderated and Heavy-Water-Reflected Cylindrical Core Loaded with Highly-Enriched-Uranium or Medium-Enriched-Uranium Fuel
- Experimental Study on Temperature Coefficient of Reactivity in Light-Water-Moderated and Heavy-Water-Reflected Cylindrical Core Loaded with Highly-Enriched-Uranium or Medium-Enriched-Uranium Fuel
- Measurement and Analysis of Leakage Neutron Spectrum from a Spherical Pile of Silicon with Incident 14MeV Neutrons
- Measurement of Leakage Neutron Spectra from a Spherical Pile of Zirconium Irradiated with 14MeV Neutrons and Validation of Its Nuclear Data
- Measurement of Leakage Neutron Spectra from a Spherical Pile of Niobium Bombarded with 14MeV Neutrons and Validation of Its Nuclear Data
- easurement and Analysis of Leakage Neutron Spectra from Spherical Assemblies of Chromium, Manganese and Copper with 14MeV Neutrons
- 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
- Development of Land Mine Detector System Based on the Measurements of Capture γ-Rays with Anticoincidence and Coincidence Methods
- Reaction Rate Analysis of Nuclear Spallation Reactions Generated by 150, 190, and 235MeV Protons
- 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
- Molecular markers associated with lymph node metastasis in pancreatic ductal adenocarcinoma by genome-wide expression profiling
- Isolated gastric metastasis from renal cell carcinoma 19 years after radical nephrectomy
- An Extended Rod Drop Method Applicable to Subcritical Reactor System Driven by Neutron Source
- Reduction of Delayed-Neutron Contribution to Variance-to-Mean Ratio by Application of Difference Filter Technique
- Sensitivity Analysis for Multiplication Factor Change of LWR Cell Caused by the Differences between JENDL-3.2 and JENDL-3.3
- Clinicopathology of pancreaticobiliary maljunction : relationship between alterations in background biliary epithelium and neoplastic development
- Surgical treatment of intraductal papillary-mucinous tumor (IPMT) of the pancreas : operative indications based on surgico-pathologic study focusing on invasive carcinoma derived from IPMT
- Determination of Subcritical Reactivity of a Thermal Accelerator-Driven System from Beam Trip and Restart Experiment
- Computed tomography lymphography for the detection of sentinel nodes in patients with gastric carcinoma
- Curative resection of hepatocellular carcinoma with intrabile duct tumor growth mimicking hilar bile duct carcinoma
- Space-Dependent Effect Observed in Subcriticality Measurements for Loosely Coupled-Core System
- Development of a Compact and User-friendly Ion Irradiation System Controlled Remotely through the Internet
- Determination of Subcritical Reactivity of a Thermal Accelerator-Driven System from Beam Trip and Restart Experiment
- Application of a ^6LiF Small Neutron Detector with an Optical Fiber to Tritium Production Rate Measurement in D-T Neutron Fields
- An Improvement of the Transverse Leakage Treatment for the Nodal S_N Transport Calculation Method in Hexagonal-Z Geometry
- Factors influencing infectious complications after pancreatoduodenectomy
- "OKTAVIAN-I, II. As D-T Neutron Sources for Studies of Radiation Effects on Plasma Diagnostics"
- Feynman-α Analysis for a Thermal Subcritical Reactor System Driven by an Unstable 14MeV Neutron Source
- Systemic inflammatory response syndrome as a predictor of anastomotic leakage after esophagectomy
- Method for Calculating Anisotropic Neutron Transport Using Scattering Kernel without Polynomial Expansion
- Early metabolic response to neoadjuvant letrozole, measured by FDG PET/CT, is correlated with a decrease in the Ki67 labeling index in patients with hormone receptor-positive primary breast cancer : a pilot study
- 日米欧原子力学生国際交流事業による米国留学生受け入れ : 平成23年度の報告と今後の展望
- Transumbilical approach for laparo-endoscopic single-site adrenalectomy : Initial experience and short-term outcome
- ^F-Fluorodeoxyglucose positron emission tomography optimizes neoadjuvant chemotherapy for primary breast cancer to achieve pathological complete response
- Measurements and Analysis of Neutron Flux Distribution in UTR-KINKI
- Neutron Anisotropic Scattering Effect in Heterogeneous Cell Calculations of Light Water Reactors
- Interpretation of Spatial Kinetics for Rod Drop Experiment in Loosely Coupled-Core Systems.
- Temperature coefficient of reactivity in light-water moderated and reflected cores loaded with highly-enriched-uranium fuel.
- Neutron transport calculations by using double-differential cross sections.
- Simple and Quick Measurement of Neutron Flux Distribution by Using an Optical Fiber with Scintillator.
- Measurements of double differential neutron emission cross sections for fusion reactor candidate elements.
- Measurement of Reactivity Effect and Thermal Neutron Flux in Non-uniformly Distributed Fuel Assemblies.