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Mitsubishi Research Institute Inc. | 論文
- Profiles of Chemical Effects on Cells (pCEC) : a toxicogenomics database with a toxicoinformatics system for risk evaluation and toxicity prediction of environmental chemicals
- Measurements of(n, xp), (n, xd)Double Differential Cross Sections of Carbon and Aluminum for 65 and 75 MeV Neutrons
- 調査・研究 通話料金指数の作成
- 5.ゲノムデータの視覚化による効果的な理解(バイオデータベースの今)
- 高レベル放射性廃棄物処分に関するシミュレーション
- HGREP (Human Genome REconstruction Project) の使い方
- Calculations of Effective Dose and Ambient Dose Equivalent Conversion Coefficients for High Energy Photons
- External Radiation Conversion Coefficients using Radiation Weighting Factor and Quality Factor for Neutron and Proton from 20 MeV to 10 GeV
- Measurements of Activation Cross Sections on Spallation Reactions for ^Co and ^Cu at Incident Neutron Energies of 40 to 120 MeV
- Measurements and Calculations of Neutron Energy Spectra Behind Polyethylene Shields Bombarded by 40- and 65-MeV Quasi-Monoenergetic Neutron Sources
- Special Issue on Knowledge-Based Software Engineering
- A Qualitative Schematic Analysis that Shows a Collaborative Process of Knowledge Construction while Using a Bulletin Board System : A Case of Undergraduate Students' Learning about Astronomy in a Course
- A Course for Prospective Teachers Involving Portfolio Development through Cross Grades Interaction in a CSCL Environment
- Measurement of Prompt Fission Neutron Spectrum of Neptunium-237 for 0. 62 MeV Incident Neutrons
- Measurements of Double-Differential Neutron Emission Cross Sections of ^6Li, ^7Li and ^9Be for 11. 5 MeV and 18. 0 MeV Neutrons
- Silicate Anion Structural Change in Calcium Silicate Hydrate Gel on Dissolution of Hydrated Cement
- SORPTION OF ALKALINE METAL IONS ONTO C-S-H : CALCIUM SILICATE HYDRATED PHASES
- Dissolution Phenomena of CaO-SiO_2-H_2O Gel at Ca/Si>1 Coexisting with Ettringite System
- Measurement of Fast Neutron-Induced Fission Cross Section Ratio of Neptunium-237 relative to Uranium-235 between 6 and 120 keV
- Measurement and Analysis of Fission Rate Distributions of ^Np and ^U in a Polyethylene System with a 65 MeV Neutron Source