Javascript must be enabled to continue!
Analysis of CAP1400 Reactor Coolant Hot Leg Flow Field
View through CrossRef
The CAP1400 reactor coolant main pipe plays a very important role in the plant safety operation, as it transports coolant among the Reactor Vessel, the Steam Generator and the Reactor Coolant Pumps, simultaneously connects the main equipments. The flow resistance of CAP1400 coolant main pipe is calculated by classic flow resistance calculation formula at present, but a big tolerance would be caused by the big size, complex structure and multi system/ instruments interfaces of the main pipe. Otherwise, CAP1400 Reactor Coolant System employs elbow flow instrument to measure coolant flowrate, the big size piping nozzle like ADS 4th and surge line might influence the stability of flow field, which affects the accuracy of the elbow flow instrument. A CFD software STAR-CCM+ is used to model CAP1400 main pipe hot leg in this paper and analyze the detailed flow field to obtain more precise calculation results, and verify if the elbow flow instrument arrangement is reasonable.
American Society of Mechanical Engineers
Title: Analysis of CAP1400 Reactor Coolant Hot Leg Flow Field
Description:
The CAP1400 reactor coolant main pipe plays a very important role in the plant safety operation, as it transports coolant among the Reactor Vessel, the Steam Generator and the Reactor Coolant Pumps, simultaneously connects the main equipments.
The flow resistance of CAP1400 coolant main pipe is calculated by classic flow resistance calculation formula at present, but a big tolerance would be caused by the big size, complex structure and multi system/ instruments interfaces of the main pipe.
Otherwise, CAP1400 Reactor Coolant System employs elbow flow instrument to measure coolant flowrate, the big size piping nozzle like ADS 4th and surge line might influence the stability of flow field, which affects the accuracy of the elbow flow instrument.
A CFD software STAR-CCM+ is used to model CAP1400 main pipe hot leg in this paper and analyze the detailed flow field to obtain more precise calculation results, and verify if the elbow flow instrument arrangement is reasonable.
Related Results
Evaluation on CAP1400 Passive Containment Cooling System Capability
Evaluation on CAP1400 Passive Containment Cooling System Capability
CAP1400 is the large advanced passive demonstration plant, which is one of the National Science and Technology Major Projects. CAP1400 is an innovative design and development based...
Overview of the CAP1400 Reactor Hydraulic Simulation Tests
Overview of the CAP1400 Reactor Hydraulic Simulation Tests
CAP1400 is the trademark of a newly designed, by Shanghai Nuclear Engineering Research and Design Institute, third generation passive PWR. To verify the hydraulic functions and to ...
Muscle Metabolism during Exercise in Hemiparetic Patients
Muscle Metabolism during Exercise in Hemiparetic Patients
1. A group of eight male patients with moderate hemiparesis was studied at rest and during 40 min of exercise on four occasions. Both two-leg and one-leg exercise were performed an...
The Development and Application of the Engineering and Design Analyzer of CAP1400 Nuclear Power Plant
The Development and Application of the Engineering and Design Analyzer of CAP1400 Nuclear Power Plant
In the process of research and development for a new nuclear power plant, it is very necessary to develop a dynamic platform and tools to analyze and verify the plant control &...
ANALISIS PENGATURAN POSISI CONTROL RODS PADA KONSEP REAKTOR DAYA EKSPERIMENTAL INDONESIA PASCA REACTOR SCRAM
ANALISIS PENGATURAN POSISI CONTROL RODS PADA KONSEP REAKTOR DAYA EKSPERIMENTAL INDONESIA PASCA REACTOR SCRAM
ANALISISPENGATURAN POSISI CONTROL RODS PADA KONSEP REAKTOR DAYA EKSPERIMENTAL INDONESIA PASCA REACTOR SCRAM POST REACTOR SCRAM CONTROL RODS POSITION ADJUSTMENT ANALYSIS FOR THE IN...
Evaluation Of Operating Performance Of The Reactor Coolant System Of Rsg-Gas Using Chemcad6.1.4
Evaluation Of Operating Performance Of The Reactor Coolant System Of Rsg-Gas Using Chemcad6.1.4
<p>Evaluation of the operation of reactor main coolant system RSG-GAS is very important. This is related with the operation of the reactor that has been going on more than 27...
Large Scale PWR Passive Containment Cooling System Wind Tunnel Test
Large Scale PWR Passive Containment Cooling System Wind Tunnel Test
CAP1400 is a large passive pressurized water reactor nuclear power plant, which relies on engineering safety features such as passive containment cooling system (PCS) to remove the...
Performance Test and Simulation Study on the Air Path of CAP1400 Passive Containment Cooling System
Performance Test and Simulation Study on the Air Path of CAP1400 Passive Containment Cooling System
As a large scale passive pressurized water reactor nuclear power plant, CAP1400 can remove the reactor decay heat to outside containment with the air cooling in the air flow path o...

