Nuclear Engineering and Design
Công bố khoa học tiêu biểu
Sắp xếp:
Ex-vessel boiling experiments: laboratory- and reactor-scale testing of the flooded cavity concept for in-vessel core retention Part I: Observation of quenching of downward-facing surfaces
Nuclear Engineering and Design - Tập 169 - Trang 77-88 - 1997
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
Pressure transient and two-phase swelling due to a small top break
Nuclear Engineering and Design - Tập 95 - Trang 207-220 - 1986
Lifetime estimation of a BWR core shroud in terms of IGSCC
Nuclear Engineering and Design - Tập 368 - Trang 110831 - 2020
Experimental investigation of reaction behavior between carbon dioxide and liquid sodium
Nuclear Engineering and Design - Tập 241 - Trang 1319-1328 - 2011
Bending and twisting of pipe with creep
Nuclear Engineering and Design - Tập 66 - Trang 367-374 - 1981
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
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
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
Tổng số: 7,320
- 1
- 2
- 3
- 4
- 5
- 6
- 732