| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 4925540 | Nuclear Engineering and Design | 2017 | 7 Pages |
Abstract
An experimental investigation was conducted to simulate the sagging behavior of a full length Pressure Tube of a channel of 220 MWe Indian PHWR. The investigation aimed to recreate a condition resembling Loss of Coolant Accident (LOCA) with Emergency Core Cooling System (ECCS) failure in a nuclear power plant. A full length channel assembly immersed in moderator was subjected to electrical resistance heating of Pressure Tube (PT) to simulate the residual heat after shutting down of reactor. The temperature of PT started rising and the contact between PT and CT was established at the center of the tube where average bottom temperature was 637 °C. The integrity of PT was maintained throughout the experiment and the PT heat up was arrested on contact with the CT due to transfer of heat to the moderator.
Keywords
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Energy Engineering and Power Technology
Authors
Sujay Negi, Ravi Kumar, P. Majumdar, D. Mukopadhyay,