scholarly journals Comparison of three small-break loss-of-coolant accident tests with different break locations using the system-integrated modular advanced reactor-integral test loop facility to estimate the safety of the smart design

2017 ◽  
Vol 49 (5) ◽  
pp. 968-978 ◽  
Author(s):  
Hwang Bae ◽  
Dong Eok Kim ◽  
Sung-Uk Ryu ◽  
Sung-Jae Yi ◽  
Hyun-Sik Park
Keyword(s):  
Integral Test ◽  
Loss Of Coolant Accident ◽  
Test Loop ◽  
Loss Of Coolant

Experimental Demonstration of Safety of AHWR during Stagnation Channel Break Condition in an Integral Test Loop

2018 ◽  
Vol 4 (2) ◽  
Author(s):  
Mukesh Kumar ◽  
A. K. Nayak ◽  
Sumit V. Prasad ◽  
P. K. Verma ◽  
R. K. Singh ◽  
...  
Keyword(s):  
Nuclear Reactor ◽  
Low Flow ◽  
Experimental Demonstration ◽  
Integral Test ◽  
Water Reactor ◽  
Loss Of Coolant Accident ◽  
Test Loop ◽  
Loss Of Coolant ◽  
Channel Conditions ◽  
Channel Type

Detection of loss of coolant accident (LOCA) and generation of reactor trip signal for shutting down the reactor is very important for safety of a nuclear reactor. Large break LOCA (LBLOCA) is a typical design basis accident in all reactors and has attracted attention of the reactor designers. However, studies reveal that small break loss of coolant accident (SBLOCA) can be more severe as it is difficult to detect with conventional methods to generate reactor trip. SBLOCA in channel-type reactors is essential to consider as it may create stagnation channel conditions in the reactor coolant channel, which may lead to fuel failure, if the reactor is not tripped. Advanced heavy water reactor (AHWR) is a channel-type boiling water reactor, which may experience stagnation channel conditions in case of SBLOCA in feeder pipes. For initiating the trip signals and safe shut down of the reactor in such cases, a novel system comprising of acoustic-based sensors is incorporated in the reactor design. The system detects the peculiar sound of the steam leaked from the main heat transport system (MHTS) and generates reactor trip signal. The experimental demonstration of such new system is essential before its introduction in the reactor. The experimental demonstration of the stagnation channel break, its detection by acoustic-based sensors system, and reactor trip followed by generation of reactor trip signal was performed and presented in the paper. The experiment showed that the trip signal for AHWR can be generated within 5 s with acoustic sensor and 2 s by low flow signal and reactor trip can be ensured in 7 s following a LOCA.

Simulating Analysis for Small Break LOCA Test Facilities by Applying the Volume Scaling With Reduced Pressure and Reduced Height

2001 ◽  
Author(s):  
S. K. Moussavian ◽  
M. A. Salehi
Keyword(s):  
Experimental Data ◽  
Pressure Drop ◽  
Test Facility ◽  
Integral Test ◽  
Reduced Pressure ◽  
Simple Loop ◽  
Loss Of Coolant Accident ◽  
Reduced Height ◽  
Simulating Analysis ◽  
Loss Of Coolant

Abstract In this paper first we briefly define the different scaling schemes and scaling logic in which we use these schemes to simulate the Small-Break Loss Of Coolant Accident (SB-LOCA) in test facilities. The simple loop of the test facility is considered and the mass, momentum and energy conservation equations are used for the derivation of the scaling model. The variations of mass flow rate, pressure drop and the void fraction in the loop as functions of the time scale or the inventories are obtained. Finally, the calculated results from the simulating schemes are compared with the experimental data previously obtained in an integral test facility.

Simulated AP600 Response to Small-Break Loss-of-Coolant-Accident and Non-Loss-of-Coolant-Accident Events: Analysis of SPES-2 Integral Test Results

1998 ◽  
Vol 122 (1) ◽  
pp. 19-42 ◽  
Author(s):  
M. T. Friend ◽  
R. F. Wright ◽  
R. Hundal ◽  
L. E. Hochreiter ◽  
M. Ogrins
Keyword(s):  
Test Results ◽  
Integral Test ◽  
Loss Of Coolant Accident ◽  
Loss Of Coolant

Integral Test and Engineering Analysis of Coolant Depletion during a Large-Break Loss-of-Coolant Accident

2005 ◽  
Vol 149 (2) ◽  
pp. 200-216 ◽  
Author(s):  
Yong Soo Kim ◽  
Chang Hwan Park ◽  
Byoung Uhn Bae ◽  
Goon Cherl Park ◽  
Kune Yull Suh ◽  
...  
Keyword(s):  
Engineering Analysis ◽  
Integral Test ◽  
Loss Of Coolant Accident ◽  
Loss Of Coolant

Large-Break Loss-of-Coolant Accident Testing and Simulation for 200-MWe Simplified Boiling Water Reactor

2002 ◽  
Author(s):  
S. T. Revankar ◽  
Y. Xu ◽  
H. J. Yoon ◽  
M. Ishii
Keyword(s):  
Safety System ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Integral Test ◽  
Water Reactor ◽  
Loss Of Coolant Accident ◽  
Loss Of Coolant ◽  
Main Steam ◽  
Core Cooling ◽  
Safety Systems

The performance of the safety systems of a new design of the 200-MWe simplified boiling water reactor during a large-break, loss-of-coolant accident transient was investigated through code modeling and integral system testing. The accident considered was a break in the main steam line which is the major design basis accident. RELAP5/MOD3 best estimate reactor thermalhydraulic code was used and its applicability to the reactor safety system evaluation was examined. The integral tests were perfomed to assess the safety systems and the response of the emergency core cooling systems to accident conditions in a scaled facility called PUMA. The details of the safety system behavior are presented. The integral test simulations examined code applicability at the scaled facility level as well as prototype key safety system performance.

scholarly journals Major Achievements and Prospect of the ATLAS Integral Effect Tests

2012 ◽  
Vol 2012 ◽  
pp. 1-18 ◽  
Author(s):  
Ki-Yong Choi ◽  
Yeon-Sik Kim ◽  
Chul-Hwa Song ◽  
Won-Pil Baek
Keyword(s):  
Large Scale ◽  
Test Facility ◽  
Pressurized Water Reactor ◽  
Hydraulic Test ◽  
Validation Data ◽  
Pressurized Water ◽  
Loss Of Coolant Accident ◽  
Test Loop ◽  
Loss Of Coolant ◽  
Integral Effect

A large-scale thermal-hydraulic integral effect test facility, ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation), has been operated by KAERI. The reference plant of ATLAS is the APR1400 (Advanced Power Reactor, 1400 MWe). Since 2007, an extensive series of experimental works were successfully carried out, including large break loss of coolant accident tests, small break loss of coolant accident tests at various break locations, steam generator tube rupture tests, feed line break tests, and steam line break tests. These tests contributed toward an understanding of the unique thermal-hydraulic behavior, resolving the safety-related concerns and providing validation data for evaluation of the safety analysis codes and methodology for the advanced pressurized water reactor, APR1400. Major discoveries and lessons found in the past integral effect tests are summarized in this paper. As the demand for integral effect tests is on the rise due to the active national nuclear R&D program in Korea, the future prospects of the application of the ATLAS facility are also discussed.

An Experimental Investigation on Thermal-Hydraulic Interaction Between Core Makeup Tank and Safety Injection Tank of an Integral Small Reactor During a Small Break Loss-of-Coolant Accident

2015 ◽  
Author(s):  
Hwang Bae ◽  
Sung Uk Ryu ◽  
Hyo Bong Ryu ◽  
Woo Shik Kim ◽  
Sung-Jae Yi ◽  
...  
Keyword(s):  
Pressure Vessel ◽  
Reactor Pressure Vessel ◽  
Injection System ◽  
Test Facility ◽  
Passive Safety ◽  
Injection Test ◽  
Loss Of Coolant Accident ◽  
Test Loop ◽  
Loss Of Coolant ◽  
Reactor Pressure

A passive injection test was conducted using a core makeup tank (CMT), a safety injection tank (SIT) and an automatic depressurization system (ADS), which consists of a passive safety system (PSS) of the SMART reactor. This paper investigates the thermal-hydraulic interaction between CMT and SIT during sequential injections of coolant from these two tanks to a high-temperature and high-pressure reactor pressure vessel using an integral effect test facility of SMART-ITL (System-Integrated Modular Advanced ReacTor-Integral Test Loop). Both CMT and SIT were connected to the reactor pressure vessel by a pressure balance line (PBL) and injection line (IL). A steady-state condition was maintained for 1,000 seconds before the start of the injection. The major parameters agreed well with the target value. After one of safety injection system line was simulated to be broken, a transient injection test was conducted according to the small-break loss-of-coolant accident (SBLOCA) scenario. Coolant injections from a CMT and SIT were started sequentially by opening quick-opening valves installed on the IL and PBL piping, respectively. Several thermal-hydraulic phenomena such as direct contact condensation, thermal stratification, and coupling effects between the CMT and SIT were locally observed during the SBLOCA scenario. The results show that the adopted passive safety injection system functions well as an emergency core cooling system.

Experimental Investigation of Liquid Entrainment in ADS-4 Branch Line

2014 ◽  
Author(s):  
Ducheng Sun ◽  
Jianchang Liu ◽  
Wenxi Tian ◽  
Suizheng Qiu ◽  
Guanghui Su ◽  
...  
Keyword(s):  
Experimental Investigation ◽  
Preliminary Test ◽  
Scaling Analysis ◽  
Entrainment Rate ◽  
Fourth Stage ◽  
Loss Of Coolant Accident ◽  
Test Loop ◽  
Loss Of Coolant ◽  
Vertical Up ◽  
Hydraulic Processes

In order to gain more insights into the system depressurization and entrainment behavior after actuation of the fourth-stage (ADS-4) valves during a loss-of-coolant-accident, the ADS-4 Depressurization and Entrainment TEst Loop (ADETEL) scaled to AP1000 was constructed to simulate the accident scenario with air-water and steam-water. A brief scaling analysis with emphasis on related thermal hydraulic processes was presented. Entrainment phenomena at vertical up tee branch were observed and analyzed. Preliminary test data of onset of entrainment and entrainment rate were collected with air-water tests and relevant conclusions were obtained.

Analyses of ACME integral test results on CAP1400 small-break loss-of-coolant-accident transient

2016 ◽  
Vol 88 ◽  
pp. 375-397 ◽  
Author(s):  
Yu Quan Li ◽  
Hua Jian Chang ◽  
Zi Shen Ye ◽  
Fang Fang Fang ◽  
Yan Shi ◽  
...  
Keyword(s):  
Test Results ◽  
Integral Test ◽  
Loss Of Coolant Accident ◽  
Loss Of Coolant
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