Structural mechanics in reactor technology SMIRT 6
- Publisher
- Elsevier Science
- Year
- 1980
- Tongue
- English
- Weight
- 80 KB
- Volume
- 13
- Category
- Article
- ISSN
- 0013-7944
No coin nor oath required. For personal study only.
โฆ Synopsis
Topical scope
The topical scope of the previous SMIRT Conferences will be maintained. The Conference will cover all aspects of engineering mechanics as applied to mechanical and structural components and the relevant systems in nuclear fission or fusion reactors.
That application can be understood in its widest sense, including the theoretical developments of mechanics wherever they are applicable to reactor technology, the discussion of load conditions, the behaviour of materials, interactions with fluid mechanics, accident sequences or calculation procedures. The problems of structural mechanics analysis will thus be clarified in the general context of reactor design, reliability and safety. Rationalization of the reference loads can be undertaken on the basis of statistical and probabilistic considerations.
The papers may be theoretical or applied, or they can combine the two by pointing out areas in which the theoretical results can be applied and how actual behaviour correlates with the theory. One of the aims of the conference in to bring about a synthesis between different approaches.
The papers will be distributed among the following Divisions; Thermal and fluid/structure dynamics analysis. Analysis of reactor fuel and cladding materials. Structural analysis of reactor fuel elements and assemblies. Structural analysis of fast reactor core and coolant circuit structure Structural analysis of thermal reactor core and coolant circuit structures. Structural analysis of steel reactor pressure vessels. Structural engineering of prestressed reactor pressure vessels.
Loading conditions and structural analysis of reactor containment. Seismic response analysis of nuclear power plant systems. Materials modelling and inelastic behaviour of materials and structures. Methods for structural analysis.
Mechanical and thermal problems of future fusion reactor power plants.
Information may be obtained from SMIRT-6 Organization Committee c/o SFEN--48, rue de la Procession F
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