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School of Nuclear Engineering, Purdue University | 論文
- Heat Transfer Study for Thermal-Hydraulic Design of the Soild-Target of Spallation Neutron Source
- 画像処理による細管内気液二相流界面輸送の計測(FR2 計測制御の最先端)
- ICONE11-36391 INTERFACIAL AREA TRANSPORT OF BUBBLY FLOW AT LOW LIQUID REYNOLDS NUMBER UNDER MICROGRAVITY ENVIRONMENT
- ICONE11-36179 SAFETY ANALYSIS OF MULTIPLE-FAILURE OF PASSIVE SAFETY SYSTEMS IN SBWR-1200 SBLOCA
- ICONE11-36015 ONE-DIMENSIONAL DRIFT-FLUX MODEL FOR DOWNWARD TWO-PHASE FLOW
- Local Interfacial Structure of Subcooled Boiling Flow in a Heated Annulus
- The credit analysis of recycling beryllium and uranium in BeO-UO_2 nuclear fuel
- ICONE11-36591 NEW QUICKEST TRANSIENT DETECTION METHODOLOGY : NUCLEAR ENGINEERING APPLICATIONS
- The diagnostic accuracy of high-mobility group box 1 protein and twelve other markers in discriminating bacterial, viral and co-infected bronchial pneumonia in Han children