Behavior of Irradiated ATR/MOX Fuel under Reactivity Initiated Accident Conditions
スポンサーリンク
概要
- 論文の詳細を見る
Pulse irradiation experiments with irradiated ATR/MOX fuel rods of 20 MWd/kgHM were conducted at the NSRR in Japan Atomic Energy Research Institute to study the transient behavior of MOX fuel rod under reactivity initiated accident conditions. Four pulse irradiation experiments were performed with peak fuel enthalpy ranging from 335 J/g to 586 J/g, resulted in no failure of fuel rods. Relatively large radial deformation of the fuel rods due to pellet-cladding mechanical interaction occurred in the experiments with peak fuel enthalpy above 500 J/g. Significant fission gas release up to 20% was measured by rod puncture measurement. The generation of fine radial cracks in pellet periphery, micro-cracks and boundary separation over the entire region of pellet were observed. These microstructure changes might contribute to the swelling of fuel pellets during the pulse irradiation. This could cause the large radial deformation of fuel rod and high fission gas release when the pulse irradiation conducted at relatively high peak fuel enthalpy. In addition, fine grain structures around the plutonium spot and cauliflower structure in cavity of the plutonium spot were observed in the outer region of the fuel pellet.
- 社団法人 日本原子力学会の論文
著者
-
FUKETA Toyoshi
Japan Atomic Energy Agency
-
SASAJIMA Hideo
Japan Atomic Energy Agency
-
NAKAMURA Takehiko
Japan Atomic Energy Agency
-
Kikuchi Keiichi
Japan Nuclear Cycle Development Institute
-
Nakamura Jinichi
Department Of Reactor Safety Research Japan Atomic Energy Research Institute
-
Fuketa T
Japan Atomic Energy Agency
-
Nakamura T
Japan Atomic Energy Res. Inst. Ibaraki‐ken
-
NAKAMURA Jinichi
Japan Atomic Energy Research Institute
関連論文
- Identification of Radial Position of Fission Gas Release in High-Burnup Fuel Pellets under RIA Conditions
- Stress Intensity Factor at the Tip of Cladding Incipient Crack in RIA-Simulating Experiments for High-Burnup PWR Fuels
- Optimized Ring Tensile Test Method and Hydrogen Effect on Mechanical Properties of Zircaloy Cladding in Hoop Direction
- Terminal Solid Solubility of Hydrogen in Hafnium
- Behavior of High Burn-up Fuel Cladding under LOCA Conditions
- Thermal Conductivity Change in High Burnup MOX Fuel Pellet
- Evaluation of Initial Temperature Effect on Transient Fuel Behavior under Simulated Reactivity-Initiated Accident Conditions
- Oxidation of Fuel Rod under Dry Storage Condition
- Clad-to-Coolant Heat Transfer in NSRR Experiments
- Radionuclide Release from Mixed-Oxide Fuel under High Temperature at Elevated Pressure and Influence on Source Terms
- Proposal of Simplified Model of Radionuclide Release from Fuel under Severe Accident Conditions Considering Pressure Effect
- Effects of Fuel Oxidation and Dissolution on Volatile Fission Product Release under Severe Accident Conditions
- Releases of Cesium and Poorly Volatile Elements from UO_2 and MOX Fuels under Severe Accident Conditions
- Fracture Behavior of Irradiated Zircaloy-4 Cladding under Simulated LOCA Conditions
- Irradiated Fuel Behavior under Power Oscillation Conditions
- Behavior of YSZ based Rock-Like Oxide Fuels under Simulated RIA Conditions
- Enhancement of Cesium Release from Irradiated Fuel at Temperature above 2,800 K
- Influence of Pressure on Cesium Release from Irradiated Fuel at Temperatures up to 2,773K
- Behavior of Coated Fuel Particle of High-Temperature Gas-Cooled Reactor under Reactivity-Initiated Accident Conditions
- Fission Gas Release in BWR Fuel with a Burnup of 56GWd/t during Simulated Reactivity Initiated Accident (RIA) Condition
- Measurements of Crystal Lattice Strain and Crystallite Size in Irradiated UO_2 Pellet by X-ray Diffractometry
- Behavior of 60 to 78MWd/kgU PWR Fuels under Reactivity-Initiated Accident Conditions
- Fission Gas Release in Irradiated UO_2 Fuel at Burnup of 45GWd/t during Simulated Reactivity Initiated Accident (RIA) Condition
- Failure Thresholds of High Burnup BWR Fuel Rods under RIA Conditions
- Behavior of Irradiated ATR/MOX Fuel under Reactivity Initiated Accident Conditions
- Fission Gas Release Behavior of High Burnup UO_2 Fuel under Reactivity Initiated Accident Conditions
- Fission Gas Induced Cladding Deformation of LWR Fuel Rods under Reactivity Initiated Accident Conditions
- Hydrogen Generation during Cladding/Coolant Interactions under Reactivity Initiated Accident Conditions
- Behavior of Pre-hydrided Zircaloy-4 Cladding under Simulated LOCA Conditions
- Thermal Stress Analysis of High-Burnup LWR Fuel Pellet Pulse-Irradiated in Reactivity-Initiated Accident Conditions
- Analysis of MOX Fuel Behavior in Halden Reactor by FEMAXI-6 Code
- Investigation of Hydride Rim Effect on Failure of Zircaloy-4 Cladding with Tube Burst Test
- Influence of Hydride Re-orientation on BWR Cladding Rupture under Accidental Conditions
- Influence of Cladding-Peripheral Hydride on Mechanical Fuel Failure under Reactivity-Initiated Accident Conditions
- Effect of Cladding Surface Pre-oxidation on Rod Coolability under Reactivity Initiated Accident Conditions
- RANNS Code Analysis on the Local Mechanical Conditions of Cladding of High Burnup Fuel Rods under PCMI in RIA-Simulated Experiments in NSRR
- Effect of Pre-Hydriding on Thermal Shock Resistance of Zircaloy-4 Cladding under Simulated Loss-of-Coolant Accident Conditions
- Effect of Cooling History on Cladding Ductility under LOCA Conditions
- Development of Leak Detection System Using High Temperature-Resistant Microphones
- Ring Compression Ductility of High-Burnup Fuel Cladding after Exposure to Simulated LOCA Conditions
- Irradiated Fuel Behavior under Power Oscillation Conditions
- Influence of Hydride Re-orientation on BWR Cladding Rupture under Accidental Conditions
- Irradiation studies of JAERI's fuel at Halden Reactor.