Nuclear Engineering and Design

Title Publication Date Language Citations
Accident localization system with jet condensers for VVER 440-V 230 NPP at Jaslovské Bohunice1995/08/01English
Crack initiation and arrest in a pressurized thermal shock test for a model pressure vessel made of VVER-440 reactor pressure vessel steel1995/09/01English
Mechanistic modeling for ring-type boiling water reactor fuel spacer design (3) run-off effect and model formulation2001/12/01English
Static strength analysis of CANDU-6 reactor fuel bundle2000/09/01English
Post-CHF heat transfer with water and refrigerants1996/06/01English
Index1999/09/01English
The effect of coolant viscosity on natural convection film boiling1999/05/01English
Advanced fuel elements for passive pressure tube light water reactors1997/04/01English
Hydrodynamic instabilities in flat-plate-type fuel assemblies1995/09/01English
Mechanical and leakrate predictions for nuclear power plant containments in accidental conditions2001/01/01English
IAEA activities on passive safety systems and overview of international development2000/09/01English
Strategy of active waste management in the Russian Federation1997/10/01English
Index1998/10/01English
EC-sponsored research activities on innovative passive safety systems2000/09/01English
Design features of a cable–bollard vehicle barrier system1998/05/01English
Preface1997/11/01English
EPR accident scenarios and provisions2001/07/01English
Life extension simulation of aged reactor pressure vessel material using probabilistic fracture mechanics analysis on a massively parallel computer1995/09/01English
Coupled calculation of the radiological release and the thermal-hydraulic behaviour of a 3-loop PWR after a SGTR by means of the code RELAP51997/12/01English
Dynamic behaviour of anchors in cracked and uncracked concrete: a progress report1997/05/01English
Probabilistic fracture mechanics analysis of nuclear structural components: a review of recent Japanese activities2001/08/01English
An exact exit condition for multiphase critical flow2001/04/01English
The integration of seawater desalination system with nuclear power plant: Operational flexibility enhancement and thermo-economic performances2024/03/01English
A numerical model to investigate the irradiation effect on the dynamics of nuclear fuel bundles2024/03/01English
Comparison of accelerated and non-accelerated post-LOCA simulation2024/03/01English
HTR-Conference Announcement2001/12/01English
Current research results on the technical basis for environmental qualification of safety-related digital I&C hardware in nuclear power plants1999/12/01English
Regulatory view of containment integrity in the United Kingdom1996/11/01English
Neutron signal characterization of the power instability event at Laguna Verde BWR2000/04/01English
The development and creating of new-generation full-scope simulator and new technology of simulation1997/10/01English