Annals of Nuclear Energy
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Sắp xếp:
High temperature steam oxidation performance of uranium dioxide based accident tolerant fuel
Annals of Nuclear Energy - Tập 171 - Trang 109044 - 2022
On the anomaly in sizes of minimum critical mass cores
Annals of Nuclear Energy - Tập 86 - Trang 23-28 - 2015
Sensitivity of fuel failure detection by the delayed neutron measurement in the primary cooling circuit of HANARO
Annals of Nuclear Energy - Tập 33 Số 13 - Trang 1134-1140 - 2006
Experimental and numerical investigation of heat transfer from a narrow annulus to supercritical pressure water
Annals of Nuclear Energy - Tập 80 - Trang 416-428 - 2015
Photon interaction, energy absorption and neutron removal cross section of concrete including marble
Annals of Nuclear Energy - Tập 60 - Trang 8-14 - 2013
Review of interdisciplinary heat transfer enhancement technology for nuclear reactor
Annals of Nuclear Energy - Tập 159 - Trang 108302 - 2021
Comparison of theoretical formulae and bootstrap method for statistical error estimation of Feynman-α method
Annals of Nuclear Energy - Tập 124 - Trang 606-615 - 2019
Space and energy dependent theoretical formula for the third order neutron correlation technique
Annals of Nuclear Energy - Tập 33 Số 6 - Trang 521-537 - 2006
Development of deterministic code based on the discrete ordinates method for the third-order neutron correlation technique
Annals of Nuclear Energy - Tập 35 Số 5 - Trang 927-936 - 2008
The variance-to-mean ratio in subcritical systems driven by a spallation source
Annals of Nuclear Energy - Tập 25 Số 9 - Trang 667-676 - 1998
Tổng số: 5,104
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