Correlation among FBR core characteristics for various fuel compositions
スポンサーリンク
概要
- 論文の詳細を見る
- 2012-05-01
著者
-
OKUBO Tsutomu
Japan Atomic Energy Agency
-
KAWASHIMA Katsuyuki
Japan Nuclear Energy Safety Organization
-
MIZUNO Tomoyasu
Japan Atomic Energy Agency
-
Ohki Shigeo
Japan Atomic Energy Agency
-
MARUYAMA Shuhei
Japan Atomic Energy Agency
-
KAWASHIMA Katsuyuki
Japan Atomic Energy Agency
関連論文
- Evaluation of Creep Damage and Diametral Strain of Fast Reactor MOX Fuel Pins Irradiated to High Burnups
- FEMAXI-6 Code Verification with MOX Fuels Irradiated in Halden Reactor
- Study on Characteristics of Void Reactivity Coefficients for High-Conversion-Type Core of FLWR for MA Recycling
- Analysis of Core Physics Experiments on Fresh and Irradiated BR3 MOX Fuel in REBUS Program
- Evaluation of Creep Damage and Diametral Strain of Fast Reactor MOX Fuel Pins Irradiated to High Burnups
- Irradiation Performance of Fast Reactor MOX Fuel Assemblies Irradiated to High Burnups
- ICONE11-36176 CONTAINMENT PRESSURE SUPPRESSION SYSTEM WITH FUNCTIONS OF WATER INJECTION AND NONCONDENSABLE GAS CONFINEMENT
- Conceptual Design of Innovative Water Reactor for Flexible Fuel Cycle (FLWR) and its Recycle Characteristics
- ICONE11-36611 A comparative design study of Pb-Bi cooled reactor cores with forced and natural convection cooling
- ICONE11-36598 Conceptual Design of a Medium Scale Lead-Bismuth Cooled Fast Reactor
- Effect of Decontamination Factor on Core Neutronic Design of Light Water Reactors Using Recovered Uranium Reprocessed by Advanced Aqueous Method
- Conceptual Design Study of 180MWt Small-Sized Reduced-Moderation Water Reactor Core
- Effect of Pu-Rich Agglomerate in MOX Fuel on a Lattice Calculation
- Correlation among FBR core characteristics for various fuel compositions
- A Design Study of High Breeding Ratio Sodium Cooled Metal Fuel Core without Blanket Fuels
- Assessment of current safety evaluation analysis on reflood behavior during PWR-LOCA by using CCTF data.
- Experimental study of ECC water injection rate effects on reflood phase of PWR-LOCA.
- Experimental study of initial downcomer water accumulation velocity effects on reflood phase of PWR-LOCA.
- Assessment of core thermo-hydrodynamic models of REFLA-1D code with CCTF data for reflood phase of PWR-LOCA.
- Experimental study of system behavior during reflood phase of PWR-LOCA using CCTF.
- Effect of loop seal on reflood phenomena in PWR.
- CHF Experiments under Steady-State and Transient Conditions for Tight Lattice Core with Non-Uniform Axial Power Distribution.
- Experimental Study on Difference in Reflood Core Heat Transfer among CCTF, FLECHT-SET and Predicted with FLECHT Correlation.
- Visual study of flow behavior in upper plenum during simulated reflood phase of PWR-LOCA.