Thermal Behavior of the Reactor Vessel Penetration Under External Vessel Cooling During a Severe AccidentKang, Kyoung-Ho; Park, Rae-Joon; Kim, Jong-Tae; Min, Byung-Tae; Lee, Ki-Young; Kim, Sang-Baik · Nuclear Technology · 2004

Two-phase natural circulation flow of air and water in a reactor cavity model under an external vessel cooling during a severe accidentR.J. Park; K.S. Ha; S.B. Kim; H.D. Kim · 2006

Features of heat and deformation behavior of a VVER-600 reactor pressure vessel under conditions of inverse stratification of corium pool and worsened external vessel cooling during the severe accident. Part 2. Creep deformation and failure of the reactor pressure vesselLoktionov, Vladimir; Mukhtarov, Erkin; Lyubashevskaya, Irina · Nuclear Engineering and Design · 2018

Features of heat and deformation behavior of a VVER-600 reactor pressure vessel under conditions of inverse stratification of corium pool and worsened external vessel cooling during the severe accident. Part 1. The effect of the inverse melt stratification and in-vessel top cooling of corium pool on the thermal loads acting on VVER-600’s reactor pressure vessel during a severe accidentLoktionov, Vladimir; Mukhtarov, Erkin; Lyubashevskaya, Irina · Nuclear Engineering and Design · 2018

Emergency relief systems—sizing and scale-up. A practical and safe, but not overly conservative, sizing method is detailedHans K. Fauske; Michael A. Grolmes; Robert E. Henry · 1983