NDLI: Program Outline of Seismic Fragility Capacity Tests on Nuclear Power Plant Equipment

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Iijima, Toru Abe, Hiroshi Fujita, Takafumi
Copyright Year	2004
Abstract	A seismic probabilistic safety assessment (PSA) is an available method to evaluate residual risk of nuclear plant that is designed with definitive seismic design condition. Seismic fragility capacity data are necessary for seismic PSA, but we don’t have sufficient data of active components of nuclear plants in Japan. This paper describes a plan of seismic fragility capacity tests on nuclear power plant equipment. The purpose of those tests is to obtain seismic fragility capacity of important equipment from a safety design point of view. And the equipment for the fragility capacity tests were selected considering effect on core damage frequency (CDF) that was evaluated by our preliminary seismic PSA. Consequently horizontal shaft pump, electric cabinets, Control Rod Drive system (CRD system) of BWR and PWR plant and vertical shaft pump were selected. The seismic fragility capacity tests are conducted from phase-1 to phase-3, and horizontal shaft pump and electric cabinets are tested on phase-1. The fragility capacity test consists of two types of tests. One is actual equipment test and another is element test. On actual equipment test, a real size model is tested with high-level seismic motion, and critical acceleration and failure mode are investigated. Regarding fragility test phase-1, we selected typical type horizontal shaft pump and electric cabinets for the actual equipment test. Those were Reactor Building Closed Cooling Water (RCW) Pump and eight kinds of electric cabinets such as relay cabinet, motor control center. On the test phase-1, maximum input acceleration for the actual equipment test is intended to be 6G-force. Since the shaking table of TADOTSU facility didn’t have capability for high acceleration, we made vibration amplifying system. In this system, amplifying device is mounted on original shaking table and it moves in synchronization with original table. The element test is conducted with many samples and critical acceleration, median and deviation are evaluated. For the element test we selected bearings and liner rings of horizontal shaft pump and about thirty kinds of electric parts. The actual equipment test of phase-1 started from September 2003, and it will finish March 2004. The test phase-2 for CRD system and phase-3 for vertical shaft pump will start following test phase-1.
Sponsorship	Nuclear Engineering Division
Starting Page	367
Ending Page	373
Page Count	7
File Format	PDF
ISBN	0791846881
DOI	10.1115/ICONE12-49524
e-ISBN	0791837351
Volume Number	12th International Conference on Nuclear Engineering, Volume 2
Conference Proceedings	12th International Conference on Nuclear Engineering
Language	English
Publisher Date	2004-04-25
Publisher Place	Arlington, Virginia, USA
Access Restriction	Subscribed
Subject Keyword	Water Cooling Vibration Motor controls Bearings Risk Boiling water reactors Synchronization Earthquake resistant design Design Finishes Probabilistic safety assessment Pumps Safety Nuclear power stations Damage Pressurized water reactors Failure mechanisms
Content Type	Text
Resource Type	Article

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