Development of Irradiation Techniques for Material Study in JMTR

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The Oarai Branch has been carrying out the irradiation of materials using the JMTR, for these twenty years. We have made efforts to improve the irradiation conditions and to satisfy. the various demands evoked by our users. Here, we describe our efforts to improve the irradiation rigs and the irradiation techniques.
東北大学の論文
1991-03-05

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Neutron Irradiation Effects on Optical Fibers
Electrical current and voltatge induced in MI-cable under irradiation in JMTR
Development of Controlled Temperature-Cycle Irradiation Technique in JMTR
In Reactor Measurement of Electrical Conductivity of Single Crystal α-Alumina
Thermal Desorption of Hydrogen at the Titanium Hydride-Oxide Interface
Isotope Effects in Thermal Diffusivity and Electrical Resistivity of Zirconium Hydride and Deuteride
Vickers Microhardness Testing with Miniaturized Disk Specimens
Superconducting Properties and Strain Effects in High Fields for Bronze-Processed Multifilamentary (Nb, Ti)_3Sn Wires and Composite-Processed Ultrafine Filament Nb_3Al Wires(Low-T_c Superconducting Materials Research)
Development of Molybdenum Alloy with High Toughness at Low Temperatures
Magnetic Properties of U(Ru_Rh_x)_2Si_2 : Heavy Fermion Properties and Successive Magnetic Phase Transitions : Chapter 6. Magnetic Properties : 6-4. Low Temperature Magnetic Properties
Use of the Nonflammable Hydrofluorocarbon (HFC-43-10mee) and Tri-n-butyl Phosphate (TBP) for Nuclear Fuel Reprocessing : Phase Distribution of Uranyl Nitrate and Irradiation Effect of Co-60 γ-Ray
Effect of Specimen Geometry on Charpy Impact Test Results for Ferritic Steel Irradiated in JMTR
Trapping and detrapping of hydrogen in graphite materials exposed to hydrogen gas
Development Of High Time-Resolution Laser Flash Equipment For Thermal Diffusivity Measurements Using Miniature-Size Specimens Irradiated Heavily In A Reactor
Studies on hydrogen absorption-desorption proterties of U-Th-Zr alloys for developing new reactor fuel materials
New Ternary Hydride Formation in U-Ti-H System
Precipitation Behavior of Irradiated Reduced-Activation Ferritic Steels
Development of rig for fundamental study of radiation effects on fusion materials in JMTR
Study of Radiation Induced Electrical Degradation of Alumina in a Dynamic Pumping Condition in a Fission Reactor
Irradiation Behavior of developed radiaiton resistance optical-fibers and observed optical radiation from their SiO_2 cores under reactor irradiation
Development of Irradiation Techniques for Material Study in JMTR
Low Activation V-Ti-Cr-Si Type Alloys for Fusion Applications
Transport Properties of USb and UTe
Purification of Uranium Metal : 3-1 Purification : Chapter 3. Preparation and Characterization of Materials
Study of Properties of Uranium and its Compounds I : Purification of Metallic Uranium
Radiation effects in Ceramics I. Study of Dynamic Irradiation Effects on Electrical Conductivity in JMTR : in comparison with results obtained with other irradiation sources
Microstructure, Mechanical Properties and Fracture Behavior of α Particle Irradiated Type 316 Stainless Steel
Analysis of the Neutron Spectrum by a Simple Method
Effects of Neutron Irradiation on Mechanical Properties of Molybdenum
Derivation of Energy Generated by Nuclear Fission-Fusion Reaction
Embrittlement in Neutron Irradiated Niobium
Microstructures of High-Purity Ferritic Steels after Helium Implantation
Under Glorious Tradition of the Institute for Materials Research
Material Development for Nuclear Fusion and Energy Development Using Actinoids
Effects of temperature, strain rate, and specimen orientation on localized plastic deformation of irradiated zircaloy-2.
Effect of neutron irradiation on fracture behavior of zirconium.
Relation between microstructure and recovery behavior in fast-neutron irradiated titanium.
Effect of neutron irradiation on mechanical properties of niobium and Nb-Y alloy.
Mechanical properties of neutron-irradiated niobium.
Effect of neutron irradiation on deformation behavior of zirconium.
Neutron irradiation effects on thermally activated process of tensile properties of titanium.
Irradiation Creep Behavior of Vanadium Alloys during Neutron Irradiation in a Liquid Metal Environment

Development of Irradiation Techniques for Material Study in JMTR

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