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Title: Validation Data and Model Development for Fuel Assembly Response to Seismic Loads

Vibrations are inherently present in nuclear reactors, especially in cores and steam generators of pressurized water reactors (PWR). They can have significant effects on local heat transfer and wear and tear in the reactor and often set safety margins. The simulation of these multiphysics phenomena from first principles requires the coupling of several codes, which is one the most challenging tasks in modern computer simulation. Here an ambitious multiphysics multidisciplinary validation campaign is conducted. It relied on an integrated team of experimentalists and code developers to acquire benchmark and validation data for fluid-structure interaction codes. Data are focused on PWR fuel bundle behavior during seismic transients.
Authors:
 [1] ;  [2]
  1. George Washington Univ., Washington, DC (United States)
  2. Atomic Energy Commission (CEA) (France)
Publication Date:
OSTI Identifier:
1239276
Report Number(s):
DOE/NEUP--12--3549
12-3549; TRN: US1600310
DOE Contract Number:
AC07-05ID14517
Resource Type:
Technical Report
Research Org:
George Washington Univ., Washington, DC (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE). Nuclear Energy University Programs
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PWR TYPE REACTORS; FUEL ELEMENT CLUSTERS; COMPUTERIZED SIMULATION; VALIDATION; HEAT TRANSFER; FLUID-STRUCTURE INTERACTIONS; BENCHMARKS; TRANSIENTS; WEAR; SEISMIC EFFECTS