Static and Kinetic Experiments on Accelerator-Driven System with 14MeV Neutrons in Kyoto University Critical Assembly
スポンサーリンク
概要
- 論文の詳細を見る
In preparation for connecting a Fixed Field Alternating Gradient (FFAG) accelerator at the Kyoto University Critical Assembly (KUCA), static and kinetic experimental and numerical analyses of Accelerator-Driven System (ADS) are envisaged. Improvement of source multiplication by the implementation of a neutron guide is expected to affect the characteristics of the ADS core. The effects on reactivity and neutron flux distribution are investigated by measurements of the subcriticality and the reaction rate distributions of indium wire, respectively, using the KUCA core and the current 14 MeV pulsed neutron generator. A comparison of the results of static measurements with those of calculations provides an estimation of MCNP-4C3 precision with JENDL-3.3 and ENDF/B-VI.2 for the basic research on ADS with 14 MeV neutrons at KUCA. The neutron guide has proved to be experimentally effective in improving external source when it is extended into the fuel region. Since the reactivity range of the actual ADS operation is expected to be around 3%Δk⁄k, the validity of both measurements and calculations has been demonstrated up to 6%Δk⁄k for the current KUCA cores. The prompt neutron decay constant is obtained by the pulsed neutron method, and subcriticality by the area ratio method, using an optical fiber detection system developed at KUCA. The optical fiber detector has been assessed as a promising original tool for the measurements of the subcriticality and prompt neutron decay constant, through ADS kinetic experiments with 14 MeV neutrons.
- 社団法人 日本原子力学会の論文
- 2008-11-01
著者
-
宇根崎 博信
京大
-
IWASAKI Tomohiko
Department of Quantum Science and Energy Engineering, Tohoku University
-
PYEON Cheol
Nuclear Engineering Science Division, Research Reactor Institute, Kyoto University
-
MISAWA Tsuyoshi
Nuclear Engineering Science Division, Research Reactor Institute, Kyoto University
-
Tomohiko Iwasaki
Department Of Quantum Science And Energy Engineering Graduate School Of Engineering Tohoku Universit
-
宇根崎 博信
京大 炉
-
三澤 毅
Nuclear Engineering Science Division Research Reactor Institute Kyoto University
-
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.
-
Pyeon Cheol
Nuclear Engineering Sci. Div. Res. Reactor Inst. 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
-
Shiroya Seiji
Nuclear Energy Science Division Research Reactor Institute Kyoto University
-
UNESAKI Hironobu
Nuclear Engineering Science Division, Research Reactor Institute, Kyoto University
-
HERVAULT Morgan
Department of Fundamental Energy Science, Graduate School of Energy Science, Kyoto University
-
Shiroya Seiji
Nuclear Energy Science Division Reserch Ractor Institute Kyoto University
-
Misawa Tsuyoshi
Nuclear Engineering Science Division Research Reactor Institute Kyoto University
-
Unesaki Hironobu
Nuclear Energy Science Division Research Reactor Institute Kyoto University
-
Iwasaki Tomohiko
Department Of Cardiology Heart Institute Of Japan Tokyo Women's Medical College
-
Hervault Morgan
Department Of Fundamental Energy Science Graduate School Of Energy Science Kyoto University
-
Unesaki H
Nuclear Engineering Science Division Research Reactor Institute Kyoto University
関連論文
- Reaction rate analysis of nuclear spallation reactions generated by 150, 190, and 235 MeV protons
- 平成11年度「関西支部主催オープンスクール」の報告
- Neutronics Design of Accelerator-Driven System for Power Flattening and Beam Current Reduction
- Development of Hydride Absorber for Fast Reactor : Evaluation of Design Method for Hydride Absorber Rod
- Measurements of(n, xp), (n, xd)Double Differential Cross Sections of Carbon and Aluminum for 65 and 75 MeV Neutrons
- 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
- The Response to Drug Therapy in Unstable Angina on the Basis of Coronary Angiography Findings : PATHOGENESIS AND MANAGEMENT OF IMPENDING MYOCARDIAL INFARCTION
- 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
- Application of Nodal Method to Lambda Mode Higher Harmonics Code
- コリメータを用いた炉心における反応率分布測定
- 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
- 仮想中性子源の概念を用いた摂動解析手法の開発 (京都大学原子炉実験所第43回学術講演会報文集)
- 光ファイバーを用いた小型中性子検出器の開発 (京都大学原子炉実験所第43回学術講演会報文集)
- KUCAを用いた原子炉物理の実験教育 (京都大学原子炉実験所第43回学術講演会報文集)
- 高速中性子測定のための光ファイバー検出器の開発 (京都大学原子炉実験所第42回学術講演会報文集)
- 仮想中性子源増倍法による未臨界度測定法の開発 (京都大学原子炉実験所第42回学術講演会報文集)
- 高次モードを用いた中性子源増倍法による未臨界度測定の検討 (第40回京都大学原子炉実験所学術講演会)
- 中性子を利用した地雷探知における計測システムの開発 (京都大学原子炉実験所第39回学術講演会 報文集)
- 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
- 中性子源増倍法を用いた未臨界度測定法の空間依存性の検討
- 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)
- MEASUREMENT OF SERUM ANNEXIN V CONCENTRATION BY ELISA IN ACUTE MYOCARDIAL INFARCTION
- -375-EFFECT OF ISOSORBIDE DINITRATE (ISDN) TO EXERCISE CAPACITY IN PATIENTS WITH MITRAL STENOSIS (MS) : Cardiovascular Drugs : FREE COMMUNICATIONS(II) : PROCEEDINGS OF THE 53th ANNUAL SCIENTIFIC MEETING OF THE JAPANESE CIRCULATION SOCIETY
- 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
- -1300- CHANGES OF COAGULATION AND FIBRINOLYTIC ACTIVITY IN UNSTABLE ANGINA(PROCEEDINGS OF THE 59th ANNUAL SCIENTIFIC MEETING OF THE JAPANESE CIRCULATION SOCIETY)
- 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
- Impact of Partitioning and Transmutation on LWR High-Level Waste Disposal
- 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
- 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
- EXERCISE-INDUCED ST SEGMENT ELEVATION IN PRECORDIAL LEADS INDICATES MYOCARDIAL ISCHEMIA IN PATIENTS WITH NON-Q WAVE ANTERIOR MYOCARDIAL IN FARCTION
- THE RELATION BETWEEN THE PERCENTAGE OF MYOCARDIAL NECROSIS AND THE OCCURENCE OF PUMP FAILURE IN ACUTE MYOCARDIAL INFARCTION : Cardiac Pathology : 53 Annual Scientific Meeting, Japanese Circulation Society
- -P232- MORPHOLOGICAL AND BIOCHEMICAL DIFFERENCE BETWEEN KINETIC CELL DEATH AND REPERFUSION INJURY
- -P146- STUDY OF THE INCIDENCE OF KINETIC CELL DEATH IN 500 AUTOPSIED HEARTS AND THE RELATIONSHIP BETWEEN KINETIC CELL DEATH AND CARDIOPULMONARY RESUSCITATION
- -47-BASIC STUDIES ON THE PATHOGENESIS OF ACUTE MYOCARDIAL INFARCTION : RELATIONSHIP BETWEEN KINETIC CELL DEATH AND MAGNESIUM AND POTASSIUM CONTENTS IN MYOCARDIUM AND SKELETAL MUSCLE
- -36-COMPARATIVE STUDY OF RECONSTRUCTION AND ECG FINDINGS OF INFARCT HEART AUTOPSY CASES : FIRST REPORT: Q WAVES AND INFARCT SIZES
- Assessment of ^Th Nuclear Data through Analysis of Thorium-loaded Critical Experiments in Thermal-Neutron Systems using the Kyoto University Critical Assembly
- Measurement of Fuel Importance Distribution in Non-uniformly Distributed Fuel Systems
- 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 of Prompt Fission Neutron Spectrum of Neptunium-237 for 0. 62 MeV Incident Neutrons
- 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
- AN APPARENT 1-YEAR LAG RELATIONSHIP OF HEAVY SNOW YEARS BETWEEN EURASIA AND NORTH AMERICA
- Subcriticality Monitoring with a Digital Reactivity Meter
- Transmutation of Minor Actinide in Well Thermalized Neutron Field and Application of Advanced Neutron Source (ANS)
- Development of Hydride Absorber for Fast Reactor : Application of Hafnium Hydride to Control Rod of Large Fast Reactor
- An Analysis of Transient Behavior of a Matallic Fuel FBR during Initiating Phase of Core Disruptive Accident
- Measurement of Fast Neutron-Induced Fission Cross Section Ratio of Neptunium-237 relative to Uranium-235 between 6 and 120 keV
- Measurement and Analysis of Fission Rate Distributions of ^Np and ^U in a Polyethylene System with a 65 MeV Neutron Source
- Determination of Subcritical Reactivity of a Thermal Accelerator-Driven System from Beam Trip and Restart Experiment
- An Analysis of Cladding Failure on Beam Transient of Lead-Bismuth-Cooled Accelerator-Driven System
- 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
- Feynman-α Analysis for a Thermal Subcritical Reactor System Driven by an Unstable 14MeV Neutron Source
- Feynman-α Analysis for a Thermal Subcritical Reactor System Driven by an Unstable 14 MeV Neutron Source
- Neutron Economy of Transmutation of TRUin Thermal and Fast Neutron Fields
- Burning of MOX fuels in LWRs ; fuel history effects on thermal properties of hull and end piece wastes and the repository performance
- 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
- A Novel Concept for Americium-containing Target for Use in Fast Reactors
- Analysis of Post Irradiation Experiments in PWR Using New Nuclear Data Libraries.
- 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.
- Measurement and Analysis of Cadmium Ratios of Activation Foils in Thermal Critical Assembly(KUCA B 3/8" P36EU-NU-EU).
- Simple and Quick Measurement of Neutron Flux Distribution by Using an Optical Fiber with Scintillator.
- Measurement of Reactivity Effect and Thermal Neutron Flux in Non-uniformly Distributed Fuel Assemblies.