Multiscale Thermal Hydraulic Study under the Inadvertent Safety Injection System Operation Scenario of Typical Pressurized Water Reactor
Joint Authors
Su, Guanghui
Wang, Mingjun
Zuo, Qiaolin
Yu, Hao
Tian, Wenxi
Qiu, Suizheng
Source
Science and Technology of Nuclear Installations
Issue
Vol. 2017, Issue 2017 (31 Dec. 2017), pp.1-15, 15 p.
Publisher
Hindawi Publishing Corporation
Publication Date
2017-10-18
Country of Publication
Egypt
No. of Pages
15
Abstract EN
The Reactor Pressure Vessel (RPV) inlet nozzles and downcomer wall in Pressurized Water Reactors (PWR) may suffer serious thermal shock caused by cold water from reactor Safety Injection System (SIS) in some unexpected accident scenarios.
It implies the formation of great temperature gradient on the inlet nozzles and RPV wall, leading to the localized stresses and propagation of possible flaws that appeared in the material.
In this paper, the multiscale thermal hydraulic analysis was performed for Chashma Nuclear Power Plant (NPP) under the inadvertent SIS operation scenario.
The primary loop and SIS were modeled using one-dimensional method, while the three-dimensional models of reactor cold leg, RPV inlet nozzles, and downcomer were established.
Then, the inadvertent Safety Injection System operation scenario was simulated using RELAP5 code, providing the boundary conditions for three-dimensional Computational Fluid Dynamics (CFD) analysis.
The fluid and solid coupling heat transfer simulation method was employed.
Results show that the maximum temperature difference was about 80 K in the most conservative condition and the RPV inlet nozzle region was the most critical region during the accident.
This work could provide in-depth understanding on the effect of cold coolant injection along the main pipes and RPV wall during the accident scenario.
American Psychological Association (APA)
Wang, Mingjun& Zuo, Qiaolin& Yu, Hao& Tian, Wenxi& Su, Guanghui& Qiu, Suizheng. 2017. Multiscale Thermal Hydraulic Study under the Inadvertent Safety Injection System Operation Scenario of Typical Pressurized Water Reactor. Science and Technology of Nuclear Installations،Vol. 2017, no. 2017, pp.1-15.
https://search.emarefa.net/detail/BIM-1203634
Modern Language Association (MLA)
Wang, Mingjun…[et al.]. Multiscale Thermal Hydraulic Study under the Inadvertent Safety Injection System Operation Scenario of Typical Pressurized Water Reactor. Science and Technology of Nuclear Installations No. 2017 (2017), pp.1-15.
https://search.emarefa.net/detail/BIM-1203634
American Medical Association (AMA)
Wang, Mingjun& Zuo, Qiaolin& Yu, Hao& Tian, Wenxi& Su, Guanghui& Qiu, Suizheng. Multiscale Thermal Hydraulic Study under the Inadvertent Safety Injection System Operation Scenario of Typical Pressurized Water Reactor. Science and Technology of Nuclear Installations. 2017. Vol. 2017, no. 2017, pp.1-15.
https://search.emarefa.net/detail/BIM-1203634
Data Type
Journal Articles
Language
English
Notes
Includes bibliographical references
Record ID
BIM-1203634