Experiments on the Heat Transfer and Natural Circulation Characteristics of the Passive Residual Heat Removal System for an Advanced Integral Type Reactor

2007 ◽  
Vol 44 (5) ◽  
pp. 703-713 ◽  
Author(s):  
Hyun-Sik PARK ◽  
Ki-Yong CHOI ◽  
Seok CHO ◽  
Choon-Kyung PARK ◽  
Sung-Jae YI ◽  
...  
Keyword(s):  
Heat Transfer ◽  
Natural Circulation ◽  
Heat Removal ◽  
Integral Type ◽  
Type Reactor ◽  
Heat Removal System ◽  
Removal System ◽  
Circulation Characteristics ◽  
Residual Heat

Two phase natural circulation and the heat transfer in the passive residual heat removal system of an integral type reactor

2006 ◽  
Vol 33 (3) ◽  
pp. 262-270 ◽  
Author(s):  
Young-Jong Chung ◽  
Hee-Cheol Kim ◽  
Bub-Dong Chung ◽  
Moon-Ki Chung ◽  
Sung-Quun Zee
Keyword(s):  
Heat Transfer ◽  
Natural Circulation ◽  
Heat Removal ◽  
Integral Type ◽  
Two Phase ◽  
Type Reactor ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

Thermal Hydraulic Characteristics of the Integral Type Reactor, SMART-P for Validation of the Heat Removal Capability

2006 ◽  
Author(s):  
K. Y. Choi ◽  
S. Cho ◽  
S. J. Yi ◽  
H. S. Park ◽  
N. H. Choi ◽  
...  
Keyword(s):  
System Design ◽  
Heat Removal ◽  
Test Facility ◽  
Integral Type ◽  
Control Rod ◽  
Type Reactor ◽  
Loss Of Coolant ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

The SMART is an integral type reactor with new innovative design features aimed at achieving a highly enhanced safety and improved economics. This paper focuses on the thermal hydraulic experimental program for the development of SMART. Thermal hydraulic responses for the transient operations of the SMART-P are experimentally investigated by using an integral effect test facility. The test facility (VISTA) has been constructed to simulate the SMART-P, which is a pilot plant of the SMART. The VISTA facility is a full height and 1/96 volume scaled test facility with respect to the SMART-P with a power of 65MWt. In the present study, the VISTA facility was subjected to various transient conditions in order to understand the thermal-hydraulic responses following transients and finally to verify the system design of the SMART-P. Several experiments, including a heatup, a main coolant pump (MCP) speed change, and a power change, have been performed to investigate the heat transfer characteristics and the natural circulation performance of the primary system and the Passive Residual Heat Removal System (PRHRS) of the SMART-P by using the VISTA facility. Performance tests of a passive residual heat removal system (PRHRS) have also been carried out for its design optimization. Besides, several design basis accidents, such as an increase or a decrease of the feedwater flow, a loss of coolant flow, a control rod withdrawal, and a limited case of a loss of coolant accident (LOCA) on the line to the gas cylinder are under investigation in order to understand the thermal-hydraulic responses and finally to verify the system design of the SMART-P. Especially, the details of the experimental results for a loss of feedwater accident and a power increase accident due to a control rod withdrawal are explored in the present study.

scholarly journals EXPERIMENTS ON THE PERFORMANCE SENSITIVITY OF THE PASSIVE RESIDUAL HEAT REMOVAL SYSTEM OF AN ADVANCED INTEGRAL TYPE REACTOR

2009 ◽  
Vol 41 (1) ◽  
pp. 53-62 ◽  
Author(s):  
Hyun-Sik Park ◽  
Ki-Yong Choi ◽  
Seok Choi ◽  
Sung-Jae Yi ◽  
Choon-Kyung Park ◽  
...  
Keyword(s):  
Heat Removal ◽  
Integral Type ◽  
Type Reactor ◽  
Performance Sensitivity ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

Analysis of Passive Residual Heat Removal System at Primary Side when Station Blackout Occurs

2014 ◽  
Vol 986-987 ◽  
pp. 231-234
Author(s):  
Jun Teng Liu ◽  
Qi Cai ◽  
Xia Xin Cao
Keyword(s):  
Nuclear Reactor ◽  
Natural Circulation ◽  
Reactor Core ◽  
Saturation Temperature ◽  
Heat Removal ◽  
Primary Circuit ◽  
Station Blackout ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

This paper regarded CNP1000 power plant system as the research object, which is the second-generation half Nuclear Reactor System in our country, and tried to set Westinghouse AP1000 passive residual heat removal system to the primary circuit of CNP1000. Then set up a simulation model based on RELAP5/MOD3.2 program to calculate and analyze the response and operating characteristic of passive residual heat removal system on assumption that Station Blackout occurs. The calculation has the following conclusions: natural circulation was quickly established after accident, which removes core residual heat effectively and keep the core safe. The residual heat can be quickly removed, and during this process the actual temperature was lower than saturation temperature in reactor core.

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