ICONE11-36475 Research and Development on Accelerator-driven Transmutation System at JAERI
スポンサーリンク
概要
著者
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FUTAKAWA Masatoshi
Japan Atomic Energy Agency
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Nishihara Kenji
Japan Atomic Energy Agency
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Tsujimoto Kazufumi
Japan Atomic Energy Agency
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SASA Toshinobu
Japan Atomic Energy Agency
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OIGAWA Hiroyuki
Japan Atomic Energy Agency
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ARAI Yasuo
Japan Atomic Energy Agency
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TAKANO Hideki
Japan Atomic Energy Research Institute
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KURATA Yuji
Japan Atomic Energy Agency
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Kikuchi Kenji
Japan Atomic Research Institute
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Nishihara K
Japan Atomic Energy Agency
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Oigawa H
Japan Atomic Energy Agency
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OUCHI Nobuo
Japan Atomic Energy Agency
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UMENO Makoto
Japan Atomic Energy Agency
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Saito Sigeru
Japan Atomic Energy Research Institute
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Monato Kazuo
Japan Atomic Energy Research Institute
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Kurata Y
Japan Atomic Energy Agency
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Futakawa Masatoshi
Tokai Research Establishment Japan Atomic Energy Research Institute
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Saito Shigeru
Japan Atomic Energy Agency
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Kikuchi Kenji
Japan Atomic Energy Agency
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Arai Yasuo
Japan Atomic Energy Research Institute
関連論文
- Pitting Damage and Residual Stress Induced by Cavitation Erosion on Mercury Target Vessel
- Electrolysis of Burnup-Simulated Uranium Nitride Fuels in LiCl-KCl Eutectic Melts
- Analytical Validation of Uncertainty in Reactor Physics Parameters for Nuclear Transmutation Systems
- Neutronics Design of Accelerator-Driven System for Power Flattening and Beam Current Reduction
- Development of Dynamics Code and Proposal of Start-up Procedure for Accelerator Driven System
- Japanese Evaluated Nuclear Data Library Version 3 Revision-3 : JENDL-3.3
- Mockup Experiments on Investigate the Leak Rate Correlation between Mercury and Helium for the Mercury Target System of J-PARC
- Lifetime Estimation of Microbubble in Mercury
- Mitigation Technologies for Damage Induced by Pressure Waves in High-Power Mercury Spallation Neutron Sources (II) : Bubbling Effect to Reduce Pressure Wave
- Microbubble Formation at a Nozzle in Liquid Mercury
- Mitigation Technologies for Damage Induced by Pressure Waves in High-Power Mercury Spallation Neutron Sources (I) —Material Surface Improvement—
- Wettability effect on bubble formation at orifice type nozzle (特集 流動の可視化)
- Failure Probability Estimation of Multi-walled Vessels for Mercury Target
- Laser Surface Alloying of SUS316 Stainless Steel with Al-Si : Effect of Substrate Temperature on Structure and Properties of Modified Layer(Recent Advances in Materials and Processing (I))
- Evaluation of Mechanical Properties and Microstructure in Ion-Irradiated Surface Layer(Recent Advances in Materials and Processing (I))
- Micro-Impact Damage Caused by Mercury Bubble Collapse(Recent Advances in Materials and Processing (I))
- 316 Erosion Damage of Laser Alloyed Stainless Steel in Mercury
- Damage Diagnostic of Localized Impact Erosion by Measuring Acoustic Vibration
- Pitting Damage Formation up to over 10 Million Cycles Off-line Test by MIMTM
- ICONE11-36175 Off-line tests on pitting damage in mercury target
- Analytical Validation of Uncertainty in Reactor Physics Parameters for Nuclear Transmutation Systems
- Distribution of Microbubble Sizes and Behavior of Large Bubbles in Mercury Flow in a Mockup Target Model of J-PARC
- Parametric Survey for Benefit of Partitioning and Transmutation Technology in Terms of High-level Radioactive Waste Disposal
- ICONE11-36126 Examination of applicability of IK method in the negative reactivity measurements
- Measurement of Uranium-238 Doppler Effect in a Nitride Fueled LMFBR at FCA
- A New Static and Dynamic One-Point Equation and Analytic and Numerical Calculations for a Subcritical System
- Conceptual Design Study of Beam Window for Accelerator-Driven System
- Impact of Partitioning and Transmutation on High-Level Waste Disposal for the Fast Breeder Reactor Fuel Cycle
- Impact of Partitioning and Transmutation on LWR High-Level Waste Disposal
- Research and Development Program on Accelerator Driven Subcritical System in JAEA
- Neutronics Design for Lead-Bismuth Cooled Accelerator-Driven System for Transmutation of Minor Actinide
- ICONE11-36475 Research and Development on Accelerator-driven Transmutation System at JAERI
- Lead-Bismuth Eutectic Compatibility with Materials in the Concept of Spoliation Target for ADS(International Conferences on Power and Energy System)
- ICONE11-36245 RECENT ACTIVITIES OF PB-BI TECHNOLOGY FOR ADS AT JAERI
- Stress Waves due to Deposited Heat in Mercury and Lead Spallation Targets
- Experimental Investigation of Lead-Bismuth Evaporation Behavior
- ICONE11-36485 R & D Status of Superconducting Proton Linear Accelerator for ADS at JAERI
- Compact Coating of Tantalum on Tungsten Prepared by Molten Salt Electrodeposition
- Electro-Deposition of Tantalum on Tungsten and Nickel in LiF-NaF-CaF_2 Melt Containing K_2TaF_7-Electrochemical Study
- 315 Mechanical Property Evaluation of Nanoscale Zone by Indentation Technique
- 106 Strain Rate Dependence on Electric Resistivity of Austenitic Stainless Steel
- Distribution of Microbubble Sizes and Behavior of Large Bubbles in Mercury Flow in a Mockup Target Model of J-PARC
- Dynamic Response of Mercury Subjected to Pressure Wave
- Conceptual Design Study of Beam Window for Accelerator-Driven System
- Development of a Filler Metal for Weldments of a Ni-Cr-W Superalloy with High Creep Strength(Special Issue on Creep and Fatigue at Elevated Temperatures)
- SB-02-1(064) Development of a filler metal for weldments of a Ni-Cr-W superalloy with high creep strength(Materials Performance in Nuclear Application 2)
- Long-Term Creep Properties of Hastelloy XR in Simulated High-Temperature Gas-Cooled Reactor Helium
- Mitigation Technologies for Damage Induced by Pressure Waves in High-Power Mercury Spallation Neutron Sources (III) — Consideration of the Effect of Microbubbles on Pressure Wave Propagation through a Water Test —
- System Design of a Proton Linac for the Neutron Science Project at Japan Atomic Energy Research Institute
- Creep Properties of Base Metal and Welded Joint of Hastelloy XR Produced for High-Temperature Engineering Test Reactor in Simulated Primary Coolant Helium
- Impact of Partitioning and Transmutation on High-Level Waste Disposal for the Fast Breeder Reactor Fuel Cycle
- Equilibrium Evaporation Behavior of Polonium and Its Homologue Tellurium in Liquid Lead-Bismuth Eutectic
- Crack Initiation and Growth Behavior for High Temperature Creep Fatigue Interaction in a Notched Specimen of Ni-Based Alloy : Solid-Mechanics, Strength of Materials
- SB-03-3(074) Inelastic Constitutive Equation in Alloy800H(Materials Performance in Nuclear Application 3)
- Applicability of Al-Powder-Alloy Coating to Corrosion Barriers of 316SS in Liquid Lead-Bismuth Eutectic
- ICONE11-36094 STRUCTURAL INTEGRITY OF BEAM WINDOW OF MERCURY TARGET
- Temperature Dependence of Creep Properties of Cold-worked Hastelloy XR
- Mitigation Technologies for Damage Induced by Pressure Waves in High-Power Mercury Spallation Neutron Sources (III) : Consideration of the Effect of Microbubbles on Pressure Wave Propagation through a Water Test
- Corrosion of CrN-Coated Steels in Liquid Pb-Bi
- Temperature Dependence of Corrosion of Ferritic/Martensitic and Austenitic Steels in Liquid Lead-Bismuth Eutectic
- Estimation of acceptable beam-trip frequencies of accelerators for accelerator-driven systems and comparison with existing performance data
- Sound Radiation from a Housing Containing a Vibration Source
- A New Static and Dynamic One-Point Equation and Analytic and Numerical Calculations for a Subcritical System
- Temperature Dependence of Parameters Used in Intermediate Treatment of Resonance Absorption
- Multi-level correction to breit-wigner single-level formula.
- Gamma-ray production cross sections for aluminum and copper at 5.3-MeV neutron energy.
- Effective multiplication factors and reaction rates calculated with fission spectra of U-235,U-238 and Pu-239.
- Preliminary Results of Benchmark Tests on JENDL-2
- Doppler effect of structural materials in fast reactors.
- Intermediate Neutron Resonance Absorption with Interference Scattering in Heterogeneous Systems
- Number of Resonances to be Adopted for Obtaining Practically Reliable Cross Section Curves
- Accuracy of Analytical Treatments for Resonance Absorption in Doppler Resonance Regions
- Effect of Resonance Scattering of Sodium on Resonance Absorption of U-238
- Preparation of Neptunium Mononitride by Carbothermic Reduction.
- Fabrication of Uranium-Plutonium Mixed Nitride Fuel Pins for Irradiation Tests in JMTR.
- Effect of fission gas release on burnup characteristics and void reactivity in HCLWRs.
- Carbothermic synthesis of uranium-plutonium mixed carbide.
- Kinetics on carbothermic reduction of UO2+C powders and compacts to UC2.