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...
Main Authors: | , , , |
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Format: | Article |
Language: | English |
Published: |
Elsevier
2020-12-01
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Series: | Nuclear Engineering and Technology |
Subjects: | |
Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573320300322 |