RF production test facility for the LAMPS SH-60B Sea Hawk

1983 ◽  
Author(s):  
S. PARSONS
Author(s):  
Yun-Je Cho ◽  
Yeon-Sik Kim ◽  
Seok Cho ◽  
Seok Kim ◽  
Byoung-Uhn Bae ◽  
...  

Korea Atomic Energy Research Institute (KAERI) has designed and constructed a test facility for reactor coolant pumps (RCPs). The RCP Test Facility (RCPTF) has the capability to test a RCP under the operation condition of an Advanced Power Reactor 1400 MW (APR1400). The design values of the facility are 17.2 MPa, 343 °C, 11.7 m3/s, and 13 MW in maximum pressure, temperature, flow rate, and electrical power, respectively. In the facility, it is possible to perform a type test for a newly-developed RCP as well as a production test for a RCP before its installation in a nuclear power plant. For the production test, H-Q curves under the cold and hot conditions are acquired. For the type test, various transient tests are additionally performed including four types of seal transient tests, a thrust bearing transient test, a cost down test, and so on. To acquire H-Q curves of a RCP, the flow rate should be controlled by varying the flow resistance in the test loop. The RCPTF uses a Variable Restriction Orifice (VRO) whose flow area can be controlled by moving the two orifice plates installed in-parallel. The need for flow control valves and bypass lines was eliminated using the VRO such that the flow disturbance was minimized. The flow rate in the main loop of the RCPTF is measured by a standard venture flow meter. The flow rate in the RCPTF is very high and thus the venture flow meter could not be calibrated in the entire range of Reynolds number corresponding to the operating condition in the APR1400. The calibration was conducted at the Colorado Experiment Engineering Station Inc. (CEESI) in the USA where natural gas is used for a working fluid. If a discharge coefficient calibrated with the gas is applied in the test results performed using the water as a working fluid, a discrepancy can occur due to the static hole error. Therefore, the static hole error was compensated in the test results and the result shows the improvement. The effect of the temperature on the pressure pulsation amplitude was also evaluated. During a cold performance test and heat-up phase to the condition of a hot performance test, an abnormal increase in the pressure pulsation amplitude was observed near the specific temperature range. This is acoustic resonance phenomena that occur when a blade passing frequency of the RCP is proportional to the harmonic resonance frequency of the RCPTF.


2019 ◽  
Vol 44 (25) ◽  
pp. 12583-12592 ◽  
Author(s):  
H. Noguchi ◽  
H. Takegami ◽  
Y. Kamiji ◽  
N. Tanaka ◽  
J. Iwatsuki ◽  
...  

Author(s):  
Seok Kim ◽  
Byoung-Uhn Bae ◽  
Yun-Je Cho ◽  
Woo-Jin Jeon ◽  
Yeon-Sik Kim ◽  
...  

Korea Atomic Energy Research Institute (KAERI) has designed and constructed a test facility for reactor coolant pumps (RCPs). In RCP test facility (RCPTF), it is possible to perform a type test for a newly-developed RCP as well as a production test for the Advanced Power Reactor 1400 (APR1400) RCP before its installation in nuclear power plants. The thermal hydraulic and electric capability of the RCPTF covers up to 18.5 MPa, 343 °C, 11.7 m3/s, and 14.0 MW for the design pressure, temperature, flow rate, and maximum electric power, respectively. In 2013, a commissioning test was performed to verify its designed capability, followed by several modifications in the RCPTF including signal processing and control logic to enhance the verification and evaluation capability of the RCP performance. During the commission test period, the technical activity for RCP performance verification test and optimization of flow stability have also been performed. The developed techniques can be divided into four subjects; 1) Development of flow stabilization technique for high flow condition test facility, 2) Improvement on the accuracy of performance verification factor and development of evaluation method, 3) Evaluation of test facility vibration characteristics and optimization of measurement system, and 4) RCP coast-down data production. KAERI has completed a full set of technique developments, a prerequisite for the RCP performance test.


2017 ◽  
Vol 204 ◽  
pp. 390-402 ◽  
Author(s):  
Youngjoon Shin ◽  
Jihong Lim ◽  
Taehoon Lee ◽  
Kiyoung Lee ◽  
Changkeun Jo ◽  
...  

Author(s):  
J. J. Laidler ◽  
B. Mastel

One of the major materials problems encountered in the development of fast breeder reactors for commercial power generation is the phenomenon of swelling in core structural components and fuel cladding. This volume expansion, which is due to the retention of lattice vacancies by agglomeration into large polyhedral clusters (voids), may amount to ten percent or greater at goal fluences in some austenitic stainless steels. From a design standpoint, this is an undesirable situation, and it is necessary to obtain experimental confirmation that such excessive volume expansion will not occur in materials selected for core applications in the Fast Flux Test Facility, the prototypic LMFBR now under construction at the Hanford Engineering Development Laboratory (HEDL). The HEDL JEM-1000 1 MeV electron microscope is being used to provide an insight into trends of radiation damage accumulation in stainless steels, since it is possible to produce atom displacements at an accelerated rate with 1 MeV electrons, while the specimen is under continuous observation.


Sign in / Sign up

Export Citation Format

Share Document