Nuclear Engineering and Design

Title Publication Date Language Citations
Highly enriched uranium recycle and conversion facility at COGEMA Pierrelatte1997/12/01English
Determination of neutron generation time in miniature neutron source reactor by measurement of neutronics transfer function2000/02/01English
Organic iodine chemistry2001/11/01English
Mobile system for the management of fuel assemblies from research reactors1995/11/01English
Index1999/08/01English
Component exposure in hypothetical accidents with very fast depressurization in a HTR module reactor1999/06/01English
Theoretical analyses of thermal post-buckling problems of liner shells1998/04/01English
Flow-induced vibration test of an advanced water reactor model Part 1: turbulence-induced forcing function1995/07/01English
Author index2001/12/01English
Nuclear waste management in the US: The Nuclear Waste Technical Review Board's perspective1997/11/01English
Author index of volume 2092001/11/01English
The use of superelement approach for the mathematical simulation of reactor structure dynamic behaviour2000/03/01English
Seismic safety of nuclear power plants in eastern Europe1998/05/01English
Author index2001/09/01English
Author Index of Volume 2042001/02/01English
Brittle fracture analysis of the Kozloduy Unit 1 RPV1999/08/01English
The nuclear safety research project2000/12/01English
Forced vibration test of the Hualien large scale soil structure interaction model (part 2)1997/10/01English
Prediction of turbulent mixing rates of both gas and liquid phases between adjacent subchannels in a two-phase slug-churn flow2000/11/01English
Random cyclic stress-strain responses of a stainless steel pipe-weld metal I — a statistical investigation2000/07/01English
Influence of fuel bundle loading errors on the subcritically during refueling campaigns for the present BWR cores of KRB-II1997/07/01English
Author index of volume 1681997/05/01English
Editorial1999/11/01English
Contents of issue 171 (1–3)1997/07/01English
Gravity-driven countercurrent two-phase flow during filling of an unvented vessel1995/07/01English
Simulation of isothermal fission gas release1999/03/01English
The integrated management system as an auxiliary means for providing data for the probabilistic safety assessment1997/07/01English
Computational methods assuring nuclear power plant structural integrity and safety: an overview of the recent activities at VTT1998/07/01English
Effect of pressure on critical heat flux in uniformly heated vertical annulus under low flow conditions2001/01/01English
Scatter of a ferritic steel in the transition region analyzed by Charpy tests and dynamic tensile tests1999/04/01English