Nuclear Engineering and Design

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Neutron propagation experiments with a lead test section inserted in the core of the LR-0 reactor
Nuclear Engineering and Design - Tập 335 - Trang 151-160 - 2018
Evžen Losa, Michal Košťál, Vojtěch Rypar, Bohumil Jánský, Evžen Novák, Giacomo Grasso, Massimo Sarotto, Francesco Lodi
General methodology for gas monitoring of cladding failure in sodium-cooled fast reactors
Nuclear Engineering and Design - Tập 403 - Trang 112149 - 2023
C. Ding, P. Filliatre, L. Desgranges
BWR small break LOCA counterpart tests at ROSA-III and FIST test facilities
Nuclear Engineering and Design - Tập 102 - Trang 151-163 - 1987
Y. Koizumi, H. Nakamura, K. Tasaka, J.A. Findlay, L.S. Lee, W.A. Sutherland
Optimum selection of an energy resource using fuzzy logic
Nuclear Engineering and Design - Tập 239 - Trang 3062-3068 - 2009
Ayah E. Abouelnaga, Abdelmohsen Metwally, Mohammad E. Nagy, Saeed Agamy
A shape function approach for predicting deteriorated heat transfer to supercritical pressure fluids on account of a thermal entry length phenomenon
Nuclear Engineering and Design - Tập 397 - Trang 111923 - 2022
Andrea Pucciarelli, Walter Ambrosini
Numerical analysis of self-induced free surface flow oscillation by fluid dynamics computer code splash-ale
Nuclear Engineering and Design - Tập 200 - Trang 127-138 - 2000
M. Iida
Impact of gap size uncertainty on calculated temperature uncertainty for the advanced gas reactor experiments
Nuclear Engineering and Design - Tập 329 - Trang 110-123 - 2018
Binh T. Pham, Jeffrey J. Einerson, Grant L. Hawkes, Nancy J. Lybeck, David A. Petti
Design of the HDR experimental program on blowdown loading and dynamic response of PWR-vessel internals
Nuclear Engineering and Design - Tập 43 - Trang 419-435 - 1977
R. Krieg, E.G. Schlechtendahl, K.-H. Scholl
The importance of input interactions in the uncertainty and sensitivity analysis of nuclear fuel behavior
Nuclear Engineering and Design - Tập 275 - Trang 229-241 - 2014
T. Ikonen, V. Tulkki
Creep–fatigue interaction damage model and its application in modified 9Cr–1Mo steel
Nuclear Engineering and Design - Tập 241 - Trang 4856-4861 - 2011
Guodong Zhang, Yanfen Zhao, Fei Xue, Jinna Mei, Zhaoxi Wang, Changyu Zhou, Lu Zhang
Tổng số: 7,335   
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