Irradiation Test of Fuel Containing Minor Actinides in the Experimental Fast Reactor Joyo
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概要
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The mixed oxide containing minor actinides (MA-MOX) fuel irradiation program is being conducted using the experimental fast reactor Joyo of the Japan Atomic Energy Agency to research early thermal behavior of MA-MOX fuel. Two irradiation experiments were conducted in the Joyo MK-III 3rd operational cycle. Six prepared fuel pins included MOX fuel containing 3% or 5% americium (Am-MOX), MOX fuel containing 2% americium and 2% neptunium (Np/Am-MOX), and reference MOX fuel. The first test was conducted with high linear heat rates of approximately 430 W/cm maintained during only 10 minutes in order to confirm whether or not fuel melting occurred. After 10 minutes irradiation in May 2006, the test subassembly was transferred to the hot cell facility and an Am-MOX pin and a Np/Am-MOX pin were replaced with dummy pins including neutron dosimeters. The test subassembly loaded with the remaining four fuel pins was re-irradiated in Joyo for 24-hours in August 2006 at nearly the same linear power to obtain re-distribution data on MA-MOX fuel. Linear heat rates for each pin were calculated using MCNP accounting for both prompt and delayed heating components, and then adjusted using E/C for 10B (n, α) reaction rates measured in the MK-III core neutron field characterization test. Post irradiation examination of these pins to confirm the fuel melting and the local concentration under irradiation of NpO2-x or AmO2-x in the (U, Pu)O2-x fuel are underway. The test results are expected to reduce uncertainties on the design margin in the thermal design for MA-MOX fuel.
著者
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SEKINE Takashi
Japan Atomic Energy Agency
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Aoyama Takafumi
Japan Atomic Energy Agency
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TANAKA Kosuke
Japan Atomic Energy Agency
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Soga Tomonori
Japan Atomic Energy Agency
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KITAMURA Ryoichi
Japan Atomic Energy Agency
関連論文
- Development of Observation Techniques in Reactor Vessel of Experimental Fast Reactor Joyo
- Core Modification to Improve Irradiation Efficiency of the Experimental Fast Reactor Joyo
- Measurement of Burnup in FBR MOX Fuel Irradiated to High Burnup
- Densification of Molybdenum-Cermet Fuel by Sintering with Metal Additives
- Demonstration of Control Rod Holding Stability of the Self Actuated Shutdown System in Joyo for Enhancement of Fast Reactor Inherent Safety
- Transmutation of Technetium in the Experimental Fast Reactor "JOYO"
- Reduction in Degree of Absorber-Cladding Mechanical Interaction by Shroud Tube in Control Rods for the Fast Reactor
- Core Modification to Improve Irradiation Efficiency of the Experimental Fast Reactor Joyo
- Irradiation Test of Fuel Containing Minor Actinides in the Experimental Fast Reactor Joyo
- Verification of JUPITER Standard Analysis Method for Upgrading Joyo MK-III Core Design and Management