Dynamic calculations of the IAEA safety MTR research reactor Benchmark problem using RELAP5/3.2 code

<i>Nuclear Power Reactor Safety</i>

E.E. Lewis, Harold W. Lewis · Physics Today · 1979 · 131 citations

A Kinetics and Thermal-Hydraulics Capability for the Analysis of Research Reactors

W.L. Woodruff · Nuclear Technology · 1984 · 70 citations

Engineering, Mechanical Engineering, Alwr Thermal Hydraulics +17

Modelling of low-pressure subcooled flow boiling using the RELAP5 code

Boštjan Končar, Borut Mavko · Nuclear Engineering and Design · 2003 · 54 citations

Heat Transfer Process, Engineering, Fluid Mechanics +11

Simulation of loss-of-flow transients in research reactors

C. Housiadas · Annals of Nuclear Energy · 2000 · 45 citations

Engineering, Research Reactors, Systems Engineering +5

Nuclear Power Reactor Safety

E.E. Lewis · Nuclear Technology · 1979 · 21 citations

Engineering, Risk Management, Nuclear Safety +3