High Burnup Fuel Cladding Materials R&D for Advanced Nuclear Systems : Nano-sized oxide dispersion strengthening steels
スポンサーリンク
概要
- 論文の詳細を見る
Cladding materials development is crucial to realize highly efficient and high-burnup operation over 100 GWd/t of so called Generation IV nuclear energy systems, such as supercritical-water-cooled reactor (SCWR) and lead-cooled fast reactor (LFR). Oxide dispersion strengthening (ODS) ferritic/martensitic steels, which contain 9–12%Cr, show rather high resistance to neutron irradiation embrittlement and high strength at elevated temperatures. However, their corrosion resistance is not good enough in SCW and in lead at high temperatures. In order to improve corrosion resistance of the ODS steels in such environment, high-Cr ODS steels have been developed at Kyoto University. An increase in Cr content resulted in a drastic improvement of corrosion resistance in SCW and in lead, while it was expected to cause an enhancement of aging embrittlement as well as irradiation embrittlement. Anisotropy in tensile properties is another issue. In order to overwhelm these issues, surveillance tests of the material performance have been performed for high Cr-ODS steels produced by new processing technologies. It is demonstrated that high-Cr ODS steels have a high potential as fuel cladding materials for SCWR and LFR with high efficiency and high burnup.
- 社団法人 日本原子力学会の論文
- 2007-03-25
著者
-
岩田 憲幸
桐蔭横浜大学工学部
-
Iwata Noriyuki
Institute of Advanced Energy, Kyoto University
-
Kasada Ryuta
Institute of Advanced Energy, Kyoto University
-
Kimura Akihiko
Institute of Advanced Energy, Kyoto University
-
CHO Han-Sik
Graduate School of Energy Science, Kyoto University
-
TODA Naoki
Graduate School of Energy Science, Kyoto University
-
YUTANI Kentaro
Graduate School of Energy Science, Kyoto University
-
KISHIMOTO Hirotatsu
Institute of Advanced Energy, Kyoto University
-
UKAI Shigeharu
OEC, Japan Nuclear Cycle Development Institute
-
FUJIWARA Masayuki
Kobelco, Ltd.
-
Yutani Kentaro
Graduate School Of Energy Sci. Kyoto Univ.
-
Yutani Kentaro
Graduate School Of Energy Science Kyoto University
-
Cho Han-sik
Graduate School Of Energy Science Kyoto University
-
Ukai Shigeharu
Hokkaido University
-
Iwata Noriyuki
Drug Discovery Research Laboratory Sanwa Kagaku Kenkyusho Co. Ltd.
-
Kishimoto Hirotatsu
Inst. Of Advanced Energy Kyoto Univ.
-
Kishimoto Hirotatsu
Institute Of Advanced Energy Kyoto University
-
Toda Naoki
Graduate School Of Energy Science Kyoto University
-
Kasada Ryuta
Institute Of Advanced Energy Kyoto University
-
Ukai Shigeharu
Oarai Engineering Center Japan Nuclear Cycle Development Institute
-
Iwata Noriyuki
Institute Of Advanced Energy Kyoto University
-
Kimura Akihiko
Institute Of Advanced Energy Kyoto University
-
Fujiwara Masayuki
Kobelco Research Institute Inc.
-
Fujiwara Masayuki
Kobelco Ltd.
関連論文
- Ca(NO_3)_2とMgCl_2とを含浸した球状シリカゲルからの多孔質ディオプサイド微粒子の調製
- 1B21 液相法により合成したディオプサイドの結晶化プロセスとその生体活性
- Characterization of Mechanically Alloyed Powders for High-Cr Oxide Dispersion Strengthened Ferritic Steel
- High Burnup Fuel Cladding Materials R&D for Advanced Nuclear Systems : Nano-sized oxide dispersion strengthening steels
- ゾルーゲル法により合成したZnO微粉末のフォトルミネッセンス(イノベーティブセラミックス(I))
- Effects of aluminum on the corrosion behavior of 16% Cr ODS ferritic steels in a nitric acid solution
- Effects of Aluminum on the Corrosion Behavior of 16%Cr ODS Ferritic Steels in a Nitric Acid Solution
- SYNTHESIS AND BIOLOGICAL ACTIVITY OF THE NOVEL SULFATED AND PHOSPHORYLATED BIVALENT β-D-GALACTOPYRANOSIDES CONTAINING FATTY-ALKYL RESIDUES
- Effects of Zr Addition on the Microstructure of 14%Cr4%Al ODS Ferritic Steels
- A Convenient and Efficient Synthesis of Sialyl Lewis X
- 3D analysis of cracking behaviour under indentation in ion-irradiated β-SiC
- Application of FIB with micro pick-up to microstructural study of irradiated SiC/SiC composites
- Microstructural analysis of the deformation range under nano-indentation in β-SiC
- Amorphous Alloy Electrodes for Electro-oxidation of Propane
- Low Temperature Swelling in Beta-SiC Associated with Point Defect Accumulation
- Characterization of High Temperature Creep Properties in Recrystallized 12Cr-ODS Ferritic Steel Claddings
- Grain Boundary Phosphorus Segregation in Thermally Aged Low Alloy Steels
- Precipitation Behavior of Irradiated Reduced-Activation Ferritic Steels
- Characterization of Mechanically Alloyed Powders for High-Cr Oxide Dispersion Strengthened Ferritic Steel
- Mechanical Behavior of Oxide Dispersion Strengthened Steels Irradiated in JOYO
- Application of Small Punch Test to Evaluate Sigma-Phase Embrittlement of Pressure Vessel Cladding Material
- Development of Manufacturing Process of PNC-FMS Wrapper Tube with SUS316 Short Joint
- Improvement of Creep Strength of 9CrODS Martensitic Steel by Controlling Excess Oxygen and Titanium Concentrations
- Production and Properties of Nano-scale Oxide Dispersion Strengthened (ODS) 9Cr Martensitic Steel Claddings
- Development of 9Cr-ODS Martensitic Steel Claddings for Fuel Pins by means of Ferrite to Austenite Phase Transformation
- Effects of Aluminum on the Corrosion Behavior of 16% Cr ODS Ferritic Steels in a Nitric Acid Solution
- Effects of Dual-Ion Irradiation on the Swelling of SiC/SiC Composites
- Factors Controlling Irradiation Hardening of Iron-Copper Model Alloy
- Development of Oxide Dispersion Strengthened Ferritic Steels for FBR Core Application, (I) Improvement of Mechanical Properties by Recrystallization Processing
- Refinement of Oxide Particles by Addition of Hf in Ni-0.5 mass% Al-1 mass% Y_2O_3 Alloys
- Irradiation Creep-Swelling Interaction in Modified 316 Stainless Steel up to 200dpa
- Current Status of Reduced-Activation Ferritic/Martensitic Steels R&D for Fusion Energy
- Work Hardening, Sensitization, and Potential Effects on the Susceptibility to Crack Initiation of 316L Stainless Steel in BWR Environment
- Work Hardening, Sensitization, and Potential Effects on the Susceptibility to Crack Initiation of 316L Stainless Steel in BWR Environment
- Grain Boundary Deformation at High Temperature Tensile Tests in ODS Ferritic Steel
- Evaluation of impact properties of weld joint of reactor pressure vessel steels with the use of miniaturized specimens
- PREFACE
- Effects of Nickel Addition on Microstructural Evolution and Mechanical Properties of Reduced Activation Martensitic Steels Irradiated in the ATR-A1
- Grain Boundary Phosphorus Segregation in Thermally Aged Low Alloy Steels
- Structure-Activity Relationship of the Warburgia Sesquiterpene Dialdehydes
- Irradiation Effect on Tensile Property of F82H IEA and Its Joint in TITAN Project