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Aitel Corporation | 論文
- Japanese Evaluated Nuclear Data Library Version 3 Revision-3 : JENDL-3.3
- Simultaneous Evaluation of Fission Cross Sections of Uranium and Platonium Isotopes for JENDL-3.3
- Analysis of Flows around a BWR Spacer by the Two-Fluid Particle Interaction Method
- ICONE11-36287 Parametric Study on Ultra-long life core, Pb-Bi cooled U-Zr metallic fuelled core with burnable poison
- JENDL-4.0 : A New Library for Nuclear Science and Engineering
- Precise Evaluation of Corrosion Environments of Structural Materials under Complex Water Flow Condition, (I) Estimation of Corrosion Potentials in Reactor Pressure Vessel Bottom of BWRs