Journal of Nuclear Science and Technology
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Sắp xếp:
Corrosion Behavior of Stainless Steels in Simulated PWR Primary Water—Effect of Chromium Content in Alloys and Dissolved Hydrogen—
Journal of Nuclear Science and Technology - Tập 45 Số 10 - Trang 975-984 - 2008
Current understanding of radiation-induced degradation in light water reactor structural materials
Journal of Nuclear Science and Technology - Tập 50 Số 3 - Trang 213-254 - 2013
Statistical Estimation of Distributions of Physical Quantities in Nuclear Fission
Journal of Nuclear Science and Technology - Tập 11 Số 11 - Trang 461-470 - 1974
Radiation Resistivity of Pure-Silica-Core Image Guides.
Journal of Nuclear Science and Technology - Tập 30 Số 2 - Trang 95-106 - 1993
Characterization of High Temperature Creep Properties in Recrystallized 12Cr-ODS Ferritic Steel Claddings
Journal of Nuclear Science and Technology - Tập 39 Số 8 - Trang 872-879 - 2002
Development of Oxide Dispersion Strengthened Steels for FBR Core Application, (II)
Journal of Nuclear Science and Technology - Tập 35 Số 4 - Trang 294-300 - 1998
Development of Oxide Dispersion Strengthened Ferritic Steels for FBR Core Application, (I)
Journal of Nuclear Science and Technology - Tập 34 Số 3 - Trang 256-263 - 1997
Optimized Ring Tensile Test Method and Hydrogen Effect on Mechanical Properties of Zircaloy Cladding in Hoop Direction
Journal of Nuclear Science and Technology - Tập 46 Số 6 - Trang 545-552 - 2009
Partitioning of14C into Solid, Liquid, and Gas Phases in Various Paddy Soils in Japan
Journal of Nuclear Science and Technology - Tập 47 Số 3 - Trang 238-243 - 2010
Strontium Isotope Effect in Liquid-Liquid Extraction of Strontium Chloride Using a Crown Ether
Journal of Nuclear Science and Technology - Tập 32 Số 12 - Trang 1230-1235 - 1995
Tổng số: 63
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