Published 1987
| Version v1
Book
Validation of a fuel bundle mechanical performance code 'ETOILE' with BDI experimental data. T. 2
Creators
- 1. Nippon Atomic Industry Group Co. Ltd., Kawasaki, Kanagawa. Nuclear Research Lab.
Description
'ETOILE'/1//2/ is a 3-D FEM code for the prediction of the fuel pin bundle distortions and mechanical behaviors during irradiation in LMFBR cores. A validation study of the 'ETOILE' code has been made with the experimental data of the bundle stiffness described in a paper published by HEDL/3/, and it has been reported at SMiRT 8 /4/. In this paper, a validation study of the code with the experimental data of the maximum reduction in clearance between pins is presented. (orig.)
Additional details
Publishing Information
- Publisher
- Balkema.
- Imprint Place
- Rotterdam (Netherlands)
- ISBN
- 90-6191-764-6
- Imprint Title
- Transactions of the 9th international conference on structural mechanics in reactor technology. Vol. C
- Imprint Pagination
- 187 p.
- Journal Page Range
- p. 25-30.
Conference
- Title
- 9. biennial international conference on structural mechanics in reactor technology (SMIRT-9).
- Dates
- 17-21 Aug 1987.
- Place
- Lausanne (Switzerland).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 19028872
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COORDINATES; E CODES; FINITE ELEMENT METHOD; FUEL ELEMENT CLUSTERS; FUEL PINS; LMFBR TYPE REACTORS; MESH GENERATION; MOTION; THREE-DIMENSIONAL CALCULATIONS; VERIFICATION
- Descriptors DEC
- BREEDER REACTORS; COMPUTER CODES; EPITHERMAL REACTORS; EVALUATION; FAST REACTORS; FBR TYPE REACTORS; FUEL ASSEMBLIES; FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; NUMERICAL SOLUTION; REACTOR COMPONENTS; REACTORS