Annals of Nuclear Energy
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Sắp xếp:
Neutronic simulation of China Experimental Fast Reactor start-up tests. Part I: SARAX code deterministic calculation
Annals of Nuclear Energy - Tập 136 - Trang 107046 - 2020
Analysis of accumulators configuration in LB-LOCA for Bushehr NPP
Annals of Nuclear Energy - Tập 92 - Trang 96-106 - 2016
Immobilization of 137Cs and 60Co in concrete matrix
Annals of Nuclear Energy - Tập 30 - Trang 1899-1903 - 2003
Waste disposal aspects of the long term cooling characteristics of irradiated nuclear fuels
Annals of Nuclear Energy - Tập 2 - Trang 451-466 - 1975
Applicability of LR-0 mock-up results to VVER-1000 reactor pressure vessel issues
Annals of Nuclear Energy - Tập 98 - Trang 157-165 - 2016
Application of liquid-metal MHD generators to the LMFBR
Annals of Nuclear Energy - Tập 9 - Trang 215-224 - 1982
Gamma ray and neutron shielding properties of some concrete materials
Annals of Nuclear Energy - Tập 38 - Trang 2204-2212 - 2011
A new equation for Bondarenko self-shielded cross section sensitivities to nuclide densities
Annals of Nuclear Energy - Tập 156 - Trang 108122 - 2021
Advanced multi-physics simulation for reactor safety in the framework of the NURESAFE project
Annals of Nuclear Energy - Tập 84 - Trang 166-177 - 2015
Nanofluid application in post SB-LOCA transient in VVER-1000 NPP
Annals of Nuclear Energy - Tập 79 - Trang 101-110 - 2015
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