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Japan Nuclear Cycle Development Institute | 論文
- Iridium concentration and noble gas composition of Cretaceous-Tertiary boundary clay from Stevns Klint, Denmark
- 102 複雑体系内の乱流現象解析のためのLESに関する研究(関東支部 茨城講演会)
- CIVA法を用いた数値流体解析の並列計算(オーガナイズドセッション,計算力学とその応用)
- Japanese Evaluated Nuclear Data Library Version 3 Revision-3 : JENDL-3.3
- Development of Neutron Multiplicity Measurement Method in (γ, xn) Reactions(I. Nuclear Physics)
- Protected Plutonium Production by Transmutation of Minor Actinides for Peace and Sustainable Prosperity : Irradiation Tests of Np and Np-U Samples in the Experimental Fast Reactor JOYO (JAEA) and the Advanced Test Reactor at INL
- JENDL-4.0 benchmarking for fission reactor applications
- 1338 高速炉構造用316FR鋼の疲労寿命に及ぼすラチェットの影響に関する検討(S21-6 ステンレス鋼とチタン合金の疲労,S21 金属材料の疲労特性と破壊機構)
- Coulomb Excitation of^Gd
- JENDL-4.0 Benchmarking for Fission Reactor Applications
- Plutonium and Uranium in Human Bones from Areas surrounding the Semipalatinsk Nuclear Test Site
- 応力・熱流束方程式乱流モデルによる層流・乱流遷移域を含む管内乱流熱伝達の数値解析
- An Assessment of Multistage Counter Current Extraction of TRU from Spent Molten Salt into Liquid Metal II. Effect of Stage Efficiency, Scrub Stage, and TRU Concentration
- Thermal Neutron Capture Cross Sections of Zirconium-91 and Zirconium-93 by Prompt γ-ray Spectroscopy
- Design of a Compact 4π Ge Spectrometer for the Measurement of Neutron Capture Cross Sections of Minor Actinides
- Prompt Gamma Rays Emitted in Thermal-neutron Capture Reaction by ^Tc and Its Reaction Cross Section
- Measurement of Neutron Capture Cross Section of ^Np from 0.02 to 100eV
- Numerical Validation of the Theory of Coupled Reactors for the Heavy Water Critical Assembly DCA
- Thermal-Neutron Capture Cross Section and Resonance Integral of Americium-241
- Emission Probabilities of Gamma Rays from the Decay of 233Pa and 238Np, and the Thermal Neutron Capture Cross Section of 237Np