Performance of Sequoyah Containment Anchorage System
- Iowa State Univ. of Science and Technology, Ames, IA (United States). Inst. for Physical Research and Technology
Deformation of a steel containment anchorage system during a severe accident may result in a leakage path at the containment boundaries. Current design criteria are based on either ductile or brittle failure modes of headed bolts that do not account for factors such as cracking of the containment basemat or deformation of the anchor bolt that may affect the behavior of the containment anchorage system. The purpose of this study was to investigate the performance of a typical ice condenser containment`s anchorage system. This was accomplished by analyzing the Sequoyah Containment Anchorage System. Based on a strength of materials approach and assuming that the anchor bolts are resisting the uplift caused by the internal pressure, one can estimate that the failure of the anchor bolts would occur at a containment pressure of 79 psig. To verify these results and to calibrate the strength of materials equation, the Sequoyah containment anchorage system was analyzed with the ABAQUS program using a three-dimensional, finite-element model. The model included portions of the steel containment building, shield building, anchor bolt assembly, reinforced concrete mat and soil foundation material.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (United States); Ames Lab., IA (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-7405-ENG-82
- OSTI ID:
- 10115741
- Report Number(s):
- SAND--92-7308; IS--5012; ON: DE94005313
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
ANCHORS
CONTAINMENT SYSTEMS
DEFORMATION
FASTENERS
ICE CONDENSERS
PERFORMANCE
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
REACTOR ACCIDENTS
REACTOR SAFETY
SEQUOYAH-1 REACTOR
SEQUOYAH-2 REACTOR
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
ANCHORS
CONTAINMENT SYSTEMS
DEFORMATION
FASTENERS
ICE CONDENSERS
PERFORMANCE
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
REACTOR ACCIDENTS
REACTOR SAFETY
SEQUOYAH-1 REACTOR
SEQUOYAH-2 REACTOR