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The comparison of designed water-cooled and air-cooled passive residual heat removal system for 300MW nuclear power plant during the feed-water line break scenario.
- Source :
-
Annals of Nuclear Energy . Jul2013, Vol. 57, p164-172. 9p. - Publication Year :
- 2013
-
Abstract
- Abstract: The steam generator (SG) secondary water-cooled and air-cooled passive residual heat removal systems (PRHRSs) are proposed and designed for 300MW Pressurized Water Reactor (PWR). The RELAP5/MOD3.4 code is utilized to study the behavior of the PRHRSs and transient characteristics of primary loop system during Feed-water Line Break (FLB) accident. The characteristic comparison between water-cooled and air-cooled PRHRSs is also conducted in this study. The results show that both water-cooled and air-cooled PRHRSs can establish stable natural circulations in PRHRS loops, which realize the effective core decay heat removal from primary loop. Results illustrate that both water-cooled PRHRS and air-cooled PRHRS designed in the study have great significance for improving the inherent safety of 300MW nuclear power plant. However, the water-cooled PRHRS heat transfer ability is stronger in the initial time, while it becomes weaker as the system tank water evaporates in the later stage. In contrast, the air-cooled PRHRS, ensuring the main reactor operation parameters to decrease to a more safety value, is more effective than water-cooled PRHRS for long term cooling. [Copyright &y& Elsevier]
Details
- Language :
- English
- ISSN :
- 03064549
- Volume :
- 57
- Database :
- Academic Search Index
- Journal :
- Annals of Nuclear Energy
- Publication Type :
- Academic Journal
- Accession number :
- 89249533
- Full Text :
- https://doi.org/10.1016/j.anucene.2013.01.027