| 1 | A proposed method of calculating displacement dose rates | Nuclear Engineering and Design | 1975 | 1,318 |
| 2 | How to use damage mechanics | Nuclear Engineering and Design | 1984 | 1,036 |
| 3 | Two-fluid model and hydrodynamic constitutive relations | Nuclear Engineering and Design | 1984 | 608 |
| 4 | Review of two-phase flow instability | Nuclear Engineering and Design | 1973 | 591 |
| 5 | MOOSE: A parallel computational framework for coupled systems of nonlinear equations | Nuclear Engineering and Design | 2009 | 588 |
| 6 | Ductile fracture models and their potential in local approach of fracture | Nuclear Engineering and Design | 1987 | 533 |
| 7 | Reduced and selective integration techniques in the finite element analysis of plates | Nuclear Engineering and Design | 1978 | 501 |
| 8 | Ultimate strength analysis of prestressed concrete pressure vessels | Nuclear Engineering and Design | 1968 | 497 |
| 9 | Continuous damage mechanics — A tool to describe phenomena before crack initiation | Nuclear Engineering and Design | 1981 | 445 |
| 10 | Westinghouse AP1000 advanced passive plant | Nuclear Engineering and Design | 2006 | 444 |
| 11 | Design and development of the AHWR—the Indian thorium fuelled innovative nuclear reactor | Nuclear Engineering and Design | 2006 | 418 |
| 12 | Peridynamic modeling of concrete structures | Nuclear Engineering and Design | 2007 | 392 |
| 13 | Fundamental frequency analysis of functionally graded beams by using different higher-order beam theories | Nuclear Engineering and Design | 2010 | 378 |
| 14 | Fluid flow and convective heat transfer to fluids at supercritical pressure | Nuclear Engineering and Design | 2013 | 369 |
| 15 | Heat transfer to supercritical fluids flowing in channels—empirical correlations (survey) | Nuclear Engineering and Design | 2004 | 359 |
| 16 | Current status and technical description of Chinese 2×250MWth HTR-PM demonstration plant | Nuclear Engineering and Design | 2009 | 352 |
| 17 | Molten salt reactors: A new beginning for an old idea | Nuclear Engineering and Design | 2010 | 332 |
| 18 | A review of correlations to model the packing structure and effective thermal conductivity in packed beds of mono-sized spherical particles | Nuclear Engineering and Design | 2010 | 332 |
| 19 | Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles — Bundle friction factors, subchannel friction factors and mixing parameters | Nuclear Engineering and Design | 1986 | 324 |
| 20 | Numerical investigation on thermal–hydraulic performance of new printed circuit heat exchanger model | Nuclear Engineering and Design | 2008 | 323 |
| 21 | Current status of materials development of nuclear fuel cladding tubes for light water reactors | Nuclear Engineering and Design | 2017 | 315 |
| 22 | The 2006 CHF look-up table | Nuclear Engineering and Design | 2007 | 312 |
| 23 | The physical closure laws in the CATHARE code | Nuclear Engineering and Design | 1990 | 308 |
| 24 | A review of procedures for the analysis and design of concrete structures to resist missile impact effects | Nuclear Engineering and Design | 1976 | 304 |
| 25 | The design features of the HTR-10 | Nuclear Engineering and Design | 2002 | 301 |
| 26 | New discrete models and their application to seismic response analysis of structures | Nuclear Engineering and Design | 1978 | 296 |
| 27 | Experimental heat transfer in supercritical water flowing inside channels (survey) | Nuclear Engineering and Design | 2005 | 281 |
| 28 | Multiple-station ground motion processing and simulation based on smart-1 array data | Nuclear Engineering and Design | 1989 | 267 |
| 29 | In-vessel coolability and retention of a core melt | Nuclear Engineering and Design | 1997 | 266 |
| 30 | Probabilistic seismic safety study of an existing nuclear power plant | Nuclear Engineering and Design | 1980 | 256 |
| 31 | Mechanical properties of steel fiber reinforced reactive powder concrete following exposure to high temperature reaching 800°C | Nuclear Engineering and Design | 2011 | 252 |
| 32 | Derivation of element stiffness matrices by assumed strain distributions | Nuclear Engineering and Design | 1982 | 247 |
| 33 | Investigation on turbulent heat transfer to lead–bismuth eutectic flows in circular tubes for nuclear applications | Nuclear Engineering and Design | 2006 | 243 |
| 34 | A review of flow-induced vibrations in reactors and reactor components | Nuclear Engineering and Design | 1983 | 239 |
| 35 | Seismic fragilities for nuclear power plant risk studies | Nuclear Engineering and Design | 1984 | 237 |
| 36 | MAX phase carbides and nitrides: Properties for future nuclear power plant in-core applications and neutron transmutation analysis | Nuclear Engineering and Design | 2012 | 237 |
| 37 | Effect of specimen sizes, specimen shapes, and placement directions on compressive strength of concrete | Nuclear Engineering and Design | 2006 | 235 |
| 38 | CFD modelling of subcooled boiling—Concept, validation and application to fuel assembly design | Nuclear Engineering and Design | 2007 | 234 |
| 39 | Development of supercritical water heat-transfer correlation for vertical bare tubes | Nuclear Engineering and Design | 2011 | 233 |
| 40 | A review of research and development of supercritical carbon dioxide Brayton cycle technology in nuclear engineering applications | Nuclear Engineering and Design | 2020 | 231 |
| 41 | Heavy metal oxide glasses as gamma rays shielding material | Nuclear Engineering and Design | 2016 | 230 |
| 42 | Heat transfer to liquid metal: Review of data and correlations for tube bundles | Nuclear Engineering and Design | 2009 | 223 |
| 43 | Development of an ultrasound velocity profile monitor | Nuclear Engineering and Design | 1991 | 222 |
| 44 | Effect of temperature on graphite oxidation behavior | Nuclear Engineering and Design | 2004 | 219 |
| 45 | The inhomogeneous MUSIG model for the simulation of polydispersed flows | Nuclear Engineering and Design | 2008 | 218 |
| 46 | Application of the finite element method to heat conduction analysis | Nuclear Engineering and Design | 1966 | 217 |
| 47 | The 1995 look-up table for critical heat flux in tubes | Nuclear Engineering and Design | 1996 | 217 |
| 48 | Development of very-high-density low-enriched-uranium fuels | Nuclear Engineering and Design | 1997 | 217 |
| 49 | Investigation of alternative layouts for the supercritical carbon dioxide Brayton cycle for a sodium-cooled fast reactor | Nuclear Engineering and Design | 2009 | 215 |
| 50 | Experimental observations on the general trends of the steady state and stability behaviour of single-phase natural circulation loops | Nuclear Engineering and Design | 2002 | 214 |
