Overview of Thermal-Hydraulic Test Program for Evaluating or Verifying the Performance of New Design Features in APR1400 Reactor
- Korea Atomic Energy Research Institute, Yuseong P.O. Box 105, Daejeon 305-600 (Korea, Republic of)
Experimental program and some of test results for thermal-hydraulic evaluation or verification of new design features in APR1400 are introduced for major test items. APR1400 incorporates many advanced design features to enhance its performance and safety. New design features adopted in APR1400 include, among others, four trains of the safety injection system (SIS) with direct vessel injection (DVI) mode and passively operating safety injection tank (SIT), the In-containment Refueling Water Storage Tank (IRWST) and the safety depressurization and vent system (SDVS). For these new design features, experimental activities relevant for ensuring their performance and contribution to the safety enhancement have been carried out at KAERI. They include the LBLOCA ECCS performance evaluation test for the DVI mode of SIS, performance verification test of the fluidic device as a passive flow controller, performance evaluation test of steam sparger for SDVS and the CEDM (control element drive mechanism) performance evaluation test. In this paper, the test program is briefly introduced, which includes the test objectives, experimental method and some of typical results for each test item. (authors)
- Research Organization:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 21167852
- Resource Relation:
- Conference: ICAPP'02: 2002 International congress on advances in nuclear power plants, Hollywood, FL (United States), 9-13 Jun 2002; Other Information: Country of input: France; 14 refs
- Country of Publication:
- United States
- Language:
- English
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