The corium behavior and its effects on containment behaviors along with mitigation
measures are investigated for Tehran Research Reactor (TRR) by using the MELCOR and …

Motivated by efficient assessment of the in-vessel retention (IVR) strategy employed in some
designs of light water reactors, a lumped-parameter code named as transIVR was …

The convection flow and heat transfer actuated by internal decay heat and the sloshing of
vessels are the primary problems in the study of thermal behaviors in volumetrically heated …

In a serious accident, after the core of a nuclear reactor melts and collapses, In-Vessel
Retention in the External Reactor Vessel Cooling (IVR-ERVC) is an effective technology to …

Lumped parameter codes for the two-layer melt pool heat transfer in IVR analysis are
usually only verified against the UCSB case and lack of validation. We assessed the …

In a severe accident in a CANDU reactor, disassembly of the core could produce a bed of
coarse debris at the bottom of the calandria that would eventually transition into a pool of …

Transient behavior and heat transfer characteristics of the multi-layer corium pool is a
significant problem that arises in the In-Vessel Retention analysis of the nuclear reactor …

In this paper, a simple model for stratified corium pool is built based on the concept of FIBS,
to estimate the IVR thermal load of IP200 reactor (which is a small modular reactor with …

The 3D model of the corium pool was simulated and examined using the WMLES model,
VOF model, phase transition model, and dynamic mesh technology. Three rolling periods …