Nuclear Engineering and Design

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Intelligent system for transient data collection and fatigue monitoring of pressurised water reactors nuclear steam supply system
Nuclear Engineering and Design - Tập 192 - Trang 103-109 - 1999
P Morilhat, T.H Chau, D Savoldelli, C Mallez
Pressure transient and two-phase swelling due to a small top break
Nuclear Engineering and Design - Tập 95 - Trang 207-220 - 1986
P.G Hardy, H.J Richter
Lifetime estimation of a BWR core shroud in terms of IGSCC
Nuclear Engineering and Design - Tập 368 - Trang 110831 - 2020
Iouri Balachov, Balazs Fekete, Digby D. Macdonald, Benjamin Spencer
Experimental investigation of reaction behavior between carbon dioxide and liquid sodium
Nuclear Engineering and Design - Tập 241 - Trang 1319-1328 - 2011
Shinya Miyahara, Hiroyasu Ishikawa, Yoshio Yoshizawa
Bending and twisting of pipe with creep
Nuclear Engineering and Design - Tập 66 - Trang 367-374 - 1981
John H. Lau
Application of the Seebeck effect for monitoring of neutron embrittlement and low-cycle fatigue in nuclear reactor steel
Nuclear Engineering and Design - Tập 235 - Trang 1777-1788 - 2005
M. Niffenegger, K. Reichlin, D. Kalkhof
Development of two-dimensional hydrogen distribution model in small-scale spaces under severe accidents
Nuclear Engineering and Design - Tập 396 - Trang 111894 - 2022
Investigation of steam explosion duration in stratified configuration
Nuclear Engineering and Design - Tập 353 - Trang 110233 - 2019
Matjaž Leskovar, Vasilij Centrih, Mitja Uršič, Janez Kokalj
Measurements of convective heat transfer to vertical upward flows of CO2 in circular tubes at near-critical and supercritical pressures
Nuclear Engineering and Design - Tập 289 - Trang 92-107 - 2015
H. Zahlan, D. Groeneveld, S. Tavoularis
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