An investigation on the thermal hydraulic characteristics of the passive residual heat removal system (PRHRS) which is used in an integral pressurized water reactor (INSURE-100) is presented in this paper. The main components of primary coolant system are enclosed in reactor vessel. Primary fluid flow circle is natural circulation. The PRHRS can remove the energy from the primary side as long as the residual heat exchanger (RHE) is submerged in the emergency cooldown tank (ECT). The parameter study is performed by considering the effects of an effective height between the steam generators and the RHE and a valve actuation time, which are useful for the design of the PRHRS. The mass flow in the PRHRS has been affected by the height difference between the steam generators and the RHE. The pressure peak of the primary side and PRHRS has been affected by the valve action time.
Skip Nav Destination
18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4932-3
PROCEEDINGS PAPER
Analysis of PRHRS for an Integral Pressurized Water Reactor Using RELAP5/MOD3.4
Xuhua Ye,
Xuhua Ye
Harbin Engineering University, Harbin, China
Search for other works by this author on:
Minjun Peng,
Minjun Peng
Harbin Engineering University, Harbin, China
Search for other works by this author on:
Jiange Liu
Jiange Liu
Harbin Engineering University, Harbin, China
Search for other works by this author on:
Xuhua Ye
Harbin Engineering University, Harbin, China
Minjun Peng
Harbin Engineering University, Harbin, China
Jiange Liu
Harbin Engineering University, Harbin, China
Paper No:
ICONE18-29987, pp. 943-947; 5 pages
Published Online:
April 8, 2011
Citation
Ye, X, Peng, M, & Liu, J. "Analysis of PRHRS for an Integral Pressurized Water Reactor Using RELAP5/MOD3.4." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B. Xi’an, China. May 17–21, 2010. pp. 943-947. ASME. https://doi.org/10.1115/ICONE18-29987
Download citation file:
13
Views
Related Proceedings Papers
Related Articles
External Hazard Coinciding With Small Break LOCA—Thermohydraulic Calculation With System Code ATHLET
ASME J of Nuclear Rad Sci (April,2020)
Lower Plenum Voiding
J. Heat Transfer (August,1982)
Heat Exchanger Design Considerations for Gas Turbine HTGR Power Plant
J. Eng. Power (April,1977)
Related Chapters
Lessons Learned: NRC Experience
Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and Standards
Hydrodynamic Mass, Natural Frequencies and Mode Shapes
Flow-Induced Vibration Handbook for Nuclear and Process Equipment
Functionality and Operability Criteria
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 2, Third Edition