Published 1995
| Version v1
Book
Computing PWR fuel assemblies behaviour under seismic solicitations
Creators
- 1. Electricite de France (EDF), 92 - Clamart (France). Direction des Etudes et Recherches
Description
A complete numerical study of the dynamical behaviour of PWR fuel assemblies is described. A complete finite element model is described for modal analysis and a simplified two beams model is compared. Added and coupling mass effects on the assembly due to coolant fluid are computed. A final 15 assembly line is subjected to a seismic solicitation and impact forces computer. (author). 4 refs., 9 figs., 8 tabs
Additional details
Publishing Information
- Publisher
- Editora de Universidade Federal do Rio Grande do Sul.
- Imprint Place
- Porto Alegre, RS (Brazil)
- ISBN
- 85-7025-349-4
- Imprint Title
- Transactions of the 13. International Conference on Structural Mechanics in Reactor Technology. v. 1
- Imprint Pagination
- 604 p.
- Journal Page Range
- p. 63-68.
Conference
- Title
- 13. International Conference on Structural Mechanics in Reactor Technology.
- Dates
- 13-18 Aug 1995.
- Place
- Porto Alegre, RS (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 27029240
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLADDING; EARTHQUAKES; FINITE ELEMENT METHOD; FRACTURES; FUEL ASSEMBLIES; FUEL ELEMENTS; MECHANICAL PROPERTIES; NUCLEAR FUELS; NUMERICAL ANALYSIS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR CORES; REACTOR SAFETY; REACTORS; RUPTURES; STRESS ANALYSIS; STRESSES
- Descriptors DEC
- CALCULATION METHODS; DEPOSITION; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FAILURES; FUELS; MATERIALS; MATHEMATICS; NUMERICAL SOLUTION; POWER REACTORS; REACTOR MATERIALS; SAFETY; SEISMIC EVENTS; SURFACE COATING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Conference organized by the International Association for Structural Mechanics in Reactor Technology and Universidade Federal do Rio Grande do Sul.