Dynamic response of a fluid filled test loop under FCI loading
Creators
- 1. Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Reaktorentwicklung
Description
For in-pile experiments with a LMFBR fuel pin bundle a special test loop will be used allowing for appropriate changes of the local cooling conditions. As a consequence of such experiments an energetic fuel coolant interaction (FCI) generating a high pressure peak in the loop cannot be ruled out under very pessimistic assumptions. Therefore, the walls of the loop must be able to withstand this pressure peak without major damage. In order to show this, the pressure propagations along the channels of the loop will be investigated in this paper. The geometry of the loop is very complex with several parallel coolant channels and sudden variations of the channel cross-sections. The smallest channel width is less than one centimeter, the outer diameter is about one decimeter and the loop length is several meters. Furthermore, in case of a pressure peak loading, fluid-structure interaction at thin walled parts of the loop must be considered. As computational tool for this complex problem the computer program SING-S has been used. It is based on a boundary integral method developed recently and allows for an adequate modelling of the problem without any artificial damping. In other methods such damping could cause considerable errors. The circular cross-sections of the loop are approximated by rectangular cross-sections having the same area. Then the boundaries of the resulting channels can be easily described by plane rectangular dipole panels. (orig./GL)
Additional details
Publishing Information
- Publisher
- North-Holland.
- Imprint Place
- Amsterdam (Netherlands)
- ISBN
- 0444 86694 9
- Imprint Title
- Transactions of the 7. international conference on structural mechanics in reactor technology. Vol. E
- Imprint Pagination
- 751 p.
- Journal Page Range
- p. 95-102.
Conference
- Title
- 7. international seminar on computational aspects of the finite element method (CAFEM-7) in conjunction with the 7. international conference on structural mechanics in reactor technology (SMIRT-7).
- Dates
- 22-26 Aug 1983.
- Place
- Chicago, IL (USA).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 15050101
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DAMPING; FLUID-STRUCTURE INTERACTIONS; FUEL-COOLANT INTERACTIONS; LMFBR TYPE REACTORS; MATHEMATICAL MODELS; PEAKS; PRESSURE DEPENDENCE; S CODES; WAVE PROPAGATION
- Descriptors DEC
- BREEDER REACTORS; COMPUTER CODES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; REACTORS
Optional Information
- Notes
- Imprint:Vol. D and E bound in one volume.
- Secondary number(s)
- EUR--8596 DE/EN/FR.