CFD study of the PTS experiment in ROCOM test facility

With the aging of nuclear reactors, embrittlement of the reactor pressure vessel (RPV) steel, as a consequence of routine operations, is highly probable. To ensure operational integrity and safety, prediction and mitigation of compromising damage, brought on by pressurized thermal shock (PTS) follow...

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Bibliographic Details
Main Authors: Zoran Čarija, Fran Ledić, Ante Sikirica, Bojan Niceno
Format: Article
Language:English
Published: Elsevier 2020-12-01
Series:Nuclear Engineering and Technology
Subjects:
CFD
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573320300322