Response of Soviet VVER-440 accident localization systems to overpressurization
The Soviet designed VVER-440 model V230 and VVER-440 model V213 reactors do not use full containments to mitigate the effects of accidents. Instead, these VVER-440 units employ a sealed set of interconnected compartments, collectively called the accident localization system (ALS), to reduce the release of radionuclides to the atmosphere during accidents. Descriptions of the VVER accident localization structures may be found in the report DOE NE-0084. The objective of this paper is to evaluate the structural integrity of the VVER-440 ALS at the Soviet design pressure, and to determine their response to pressure loadings beyond the design value. Complex, three-dimensional, nonlinear, finite element models were developed to represent the major structural components of the localization systems of the VVER-440 models V230 and V213. The interior boundary of the localization system was incrementally pressurized in the calculations until the prediction of gross failure. 6 refs., 9 figs.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5983558
- Report Number(s):
- CONF-890855-39; ON: DE89013195
- Country of Publication:
- United States
- Language:
- English
Similar Records
Structural response of rectilinear containment to overpressurization
Single failure effects on surge line break transients for the VVER-440 reactor
Related Subjects
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ASIA
BUILDING MATERIALS
CONCRETES
CONTAINMENT
EASTERN EUROPE
ENRICHED URANIUM REACTORS
EUROPE
MATERIALS
MITIGATION
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
STRUCTURAL MODELS
THERMAL POWER PLANTS
THERMAL REACTORS
USSR
WATER COOLED REACTORS
WATER MODERATED REACTORS
WWER TYPE REACTORS