Analysis of reactor body for dropping of fuel flask
Creators
- 1. Department of Structural Mechanics, Budapest University of Technology and Economic (Hungary)
- 2. TH-CAD Computing Ltd. (Hungary)
- 3. Power Stations and Network Engineering Company (Hungary)
Description
In the Hungarian Nuclear Power Plant was a project to put the fuel flask onto a special structure in the upper part of the reinforced reactor body. The structure was built form steel elements, and the fuel flask was support in four points on the structure. During the analysis we calculated the dynamic effect from the lifting procedure and the effect of earthquake too. After the discussion the power plant asked to analyse an accident situation, when the flask fall down form the middle level structure into the steel reactor container. The question was the calculation of displacements and stresses in these structures. For the calculation we used the finite element methods. The steel support structure has shell elements in the mechanical model and the reinforced walls, columns and slabs were modelling by solid elements. First step we calculated the natural circular frequencies of the mechanical model of the reactor structure. From the modal analysis we could decide the necessary numerical integration steps. The steel support structure was in plastic state, but was not broken. The reinforce walls and slabs were staying in elastic state and the stresses were under the limit. (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. 2655-2669
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
- 43021572
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENTS; CASKS; COMPUTER CALCULATIONS; EARTHQUAKES; FINITE ELEMENT METHOD; IMPACT TESTS; NUCLEAR POWER PLANTS; REACTOR VESSELS; REACTORS; REINFORCED CONCRETE; SIMULATION; SLABS; STEELS; STRESSES; SUPPORTS; WALLS
- Descriptors DEC
- ALLOYS; BUILDING MATERIALS; CALCULATION METHODS; CARBON ADDITIONS; COMPOSITE MATERIALS; CONCRETES; CONTAINERS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MATERIALS TESTING; MATHEMATICAL SOLUTIONS; MECHANICAL STRUCTURES; MECHANICAL TESTS; NUCLEAR FACILITIES; NUMERICAL SOLUTION; POWER PLANTS; REINFORCED MATERIALS; SEISMIC EVENTS; TESTING; THERMAL POWER PLANTS; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 26 figs., 6 tabs.