Probabilistic analysis of failure of the steam distribution device
- 1. Lithuanian Energy Institute, Lithuania (Lithuania)
- 2. RFK Engineering Mechanics Consultants (United States)
Description
The parameters used in structural integrity analyses are approximate and have distributions associated with their uncertainties. The material parameters, structural geometry and the applied loads (pressure, force, and temperatures) are all uncertain. These random effects should be incorporated into the analysis in order to have a more realistic estimation of the range of the structural response. The probabilistic analysis of failure of the steam distribution headers and their connections to the vertical vent pipes during a loss-of-coolant accident is the main subject of this paper. The codes ProFES and NEPTUNE are used for probabilistic analysis of failure of the steam distribution headers and their connections with the vertical vent pipes. ProFES is a probabilistic analysis system that allows designers to perform probabilistic finite element analysis (FEA) in a 3D environment that is similar to modern deterministic FEA. In this study ProFES is coupled to the deterministic finite element code NEPTUNE. The coupled code approach simplifies the modeling of uncertainties and evaluates the effect of these uncertainties on model and system reliability. Monte Carlo Simulation and Response Surface Methods were used for probabilistic analyses of the steam distribution headers and their connections with the vertical vent pipes. (authors)
Additional details
Publishing Information
- Publisher
- Atomic Energy Press
- Imprint Place
- Beijing (China)
- ISBN
- 7-5022-3421-7
- Imprint Title
- Proceedings of 18th international conference on structural mechanics in reactor technology
- Imprint Pagination
- 4896 p.
- Journal Page Range
- p. 3824-3832
Conference
- Title
- 18. international conference on structural mechanics in reactor technology
- Dates
- 7-12 Aug 2005
- Place
- Beijing (China)
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 43021684
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- APPROXIMATIONS; COMPUTER CODES; COMPUTERIZED SIMULATION; ENVIRONMENT; EQUIPMENT; FAILURES; FINITE ELEMENT METHOD; LOSS OF COOLANT; MONTE CARLO METHOD; N CODES; P CODES; PIPES; PROBABILISTIC ESTIMATION; RELIABILITY; STEAM; STEAM SYSTEMS; VENTS; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; COMPUTER CODES; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; MATHEMATICAL SOLUTIONS; NUMERICAL SOLUTION; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 figs., 5 tabs., 8 refs.