Seismic-fragility tests of new and accelerated-aged Class 1E battery cells
The seismic-fragility response of naturally-aged nuclear station safety-related batteries is of interest for two reasons: (1) to determine actual failure modes and thresholds and (2) to determine the validity of using the electrical capacity of individual cells as an indicator of the potential survivability of a battery given a seismic event. Prior reports in this series discussed the seismic-fragility tests and results for three specific naturally-aged cell types: 12-year old NCX-2250, 10-year old LCU-13, and 10-year old FHC-19. This report focuses on the complementary approach, namely, the seismic-fragility response of accelerated-aged batteries. Of particular interest is the degree to which such approaches accurately reproduce the actual failure modes and thresholds. In these tests the significant aging effects observed, in terms of seismic survivability, were: embrittlement of cell cases, positive bus material and positive plate grids; and excessive sulphation of positive plate active material causing hardening and expansion of positive plates. The IEEE Standard 535 accelerated aging method successfully reproduced seismically significant aging effects in new cells but accelerated grid embrittlement an estimated five years beyond the conditional age of other components.
- Research Organization:
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Ontario Hydro, Toronto (Canada). Research Center; Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering Technology
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6518144
- Report Number(s):
- NUREG/CR-4098; SAND-84-2631; ON: TI87008181
- Country of Publication:
- United States
- Language:
- English
Similar Records
Test series 1: seismic-fragility tests of naturally-aged Class 1E Gould NCX-2250 battery cells
Test Series 2: seismic-fragility tests of naturally-aged Class 1E Exide FHC-19 battery cells
Related Subjects
ELECTRIC BATTERIES
AGING
FAILURES
SEISMIC EFFECTS
ENGINEERED SAFETY SYSTEMS
NUCLEAR POWER PLANTS
ACCELERATION
CORROSION
CRACKING
EMBRITTLEMENT
EXPERIMENTAL DATA
INSPECTION
SULFIDATION
TESTING
CHEMICAL REACTIONS
DATA
DECOMPOSITION
ELECTROCHEMICAL CELLS
INFORMATION
NUCLEAR FACILITIES
NUMERICAL DATA
POWER PLANTS
PYROLYSIS
THERMAL POWER PLANTS
THERMOCHEMICAL PROCESSES
220900* - Nuclear Reactor Technology- Reactor Safety
220200 - Nuclear Reactor Technology- Components & Accessories