Thermo-Mechanical Analysis for Metallic Fuel Pin under Transient Condition |
Lee, Dong-Uk
(Korea Atomic Energy Research Institute)
Lee, Byoung-Oon (Korea Atomic Energy Research Institute) Kim, Yeong-Il (Korea Atomic Energy Research Institute) Hahn, Dohee (Korea Atomic Energy Research Institute) |
1 |
Swelling in Several Commercial Alloys Irradiated to Very High Neutron Fluence
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2 |
A Model to Predict The Failure of Liquid-Metal-Reactor Fuel Pins During Trnasient Overpower Conditons
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3 |
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4 |
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5 |
A Method of Calculating Fission Gas Diffusion from UO2 Fuel and Its Application to the X-2-f Loop Test
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6 |
A Comprehensive Fission Gas Release Model Considering Multiple Bubble Sizes on The Grain Boundary under Steady-state Conditions
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7 |
Metallic Fast Reactor Fuels
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ScienceOn |
8 |
State-of-the-Art Report on Liquid Metal Reactor Core Material HT9
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9 |
Modeling The Behavior of Metallic Fast Reactor Fuels During Extended Transients
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ScienceOn |
10 |
Swelling Behavior of U-Pu-Zr
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11 |
Deformation Analysis on HT-9 Fuel Rod According to The Variations of Temperature and Neutron Flux
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12 |
In-reactor Creep Behavior of Selected Ferritic Alloys
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