Published 1994
| Version v1
Book
Effect of the fluid structure interaction on the dynamic response of a PWR reactor core
Creators
- 1. Electricite de France, Villeurbanne (France). Dept. of Basic Design
- 2. Inst. National des Sciences et Techniques Nucleaires, Saclay (France)
Description
The criterion retained for the design of the fuel assembly mixing grids under accidental dynamic loads (earthquake and LOCA) consists of checking that the maximum impact force on the grids does not exceed their resistance to dynamic buckling. The first stage in design is therefore the calculation of the reaction of the core to these accidental stresses. This article describes the approach which determines lateral loading on the fuel assembly mixing grids during earthquake. In this formulation, forces induced by the fluid structure interaction are taking into account. And a comparison between the dynamic response of the core with or without taking into account the fluid structure interaction is presented
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-1195-6
- Imprint Title
- Sloshing, fluid-structure interaction and structural response due to shock and impact loads 1994. PVP-Vol. 272
- Imprint Pagination
- 239 p.
- Journal Page Range
- p. 119-125.
Conference
- Title
- 1994 pressure vessels and piping conference.
- Dates
- 19-23 Jun 1994.
- Place
- Minneapolis, MN (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26030475
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BAFFLES; DEFORMATION; DESIGN; FLUID-STRUCTURE INTERACTIONS; FUEL ASSEMBLIES; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR CORES; RESPONSE FUNCTIONS; SEISMIC EFFECTS; THEORETICAL DATA
- Descriptors DEC
- ACCIDENTS; CONTROL EQUIPMENT; DATA; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; FUNCTIONS; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-940613--.