Development of Hydride Absorber for Fast Reactor : Application of Hafnium Hydride to Control Rod of Large Fast Reactor
スポンサーリンク
概要
- 論文の詳細を見る
The application of hafnium hydride (Hf-hydride) to a control rod for a large fast reactor where the B4C control rod is originally employed is studied. Three types of Hf-hydride control rods are designed. The control rod worth and its change during the burnup are evaluated for different hydrogen-to-hafnium ratios and are compared with those of the original B4C control rod. The result indicates that the worths of the Hf-hydride and the 10B-enriched B4C control rods are approximately the same, and the lifetime of the Hf-hydride control rod is almost four times longer than that of the 10B-enriched B4C control rod. The core performances of the shutdown margin, sodium void reactivity, Doppler reactivity coefficient, and breeding ratio are analyzed. It is indicated that those for the Hf-hydride control rod are almost the same as those for the original B4C control rod. The behavior of neutrons moderated by the Hf-hydride control rod is analyzed. It is confirmed that the Hf-hydride control rod does not cause any thermal spike problems in the fast reactor core.
- 社団法人 日本原子力学会の論文
- 2009-08-01
著者
-
IWASAKI Tomohiko
Department of Quantum Science and Energy Engineering, Tohoku University
-
KONASHI Kenji
Institute for Materials Research, Tohoku University
-
Konashi Kenji
Institute For Materials Research Tohoku University
-
Iwasaki Tomohiko
Department Of Cardiology Heart Institute Of Japan Tokyo Women's Medical College
関連論文
- Reaction rate analysis of nuclear spallation reactions generated by 150, 190, and 235 MeV protons
- 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
- The Response to Drug Therapy in Unstable Angina on the Basis of Coronary Angiography Findings : PATHOGENESIS AND MANAGEMENT OF IMPENDING MYOCARDIAL INFARCTION
- 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
- Static and Kinetic Experiments on Accelerator-Driven System with 14MeV Neutrons in Kyoto University Critical Assembly
- -1300- CHANGES OF COAGULATION AND FIBRINOLYTIC ACTIVITY IN UNSTABLE ANGINA(PROCEEDINGS OF THE 59th ANNUAL SCIENTIFIC MEETING OF THE JAPANESE CIRCULATION SOCIETY)
- Impact of Partitioning and Transmutation on LWR High-Level Waste Disposal
- Estimation of Hydrogen Redistribution in Zirconium Hydride under Temperature Gradient
- 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
- 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
- Measurement of Prompt Fission Neutron Spectrum of Neptunium-237 for 0. 62 MeV Incident Neutrons
- 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
- 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
- An Analysis of Cladding Failure on Beam Transient of Lead-Bismuth-Cooled Accelerator-Driven System
- Thermomechanical Properties of Hafnium Hydride
- Thermal Conductivity of Hafnium Hydride
- 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
- Analysis of Post Irradiation Experiments in PWR Using New Nuclear Data Libraries.
- Measurement and Analysis of Cadmium Ratios of Activation Foils in Thermal Critical Assembly(KUCA B 3/8" P36EU-NU-EU).