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Title: FEM (finite element method) thermal modeling and thermal hydraulic performance of an enhanced thermal conductivity UO2/BeO composite fuel

An enhanced thermal conductivity UO2-BeO composite nuclear fuel was studied. A methodology to generate ANSYS (an engineering simulation software) FEM (Finite Element Method) thermal models of enhanced thermal conductivity oxide nuclear fuels was developed. The results showed significant increase in the fuel thermal conductivities and have good agreement with the measured ones. The reactor performance analysis showed that the decrease in centerline temperature was 250-350K for the UO2-BeO composite fuel, and thus we can improve nuclear reactors' performance and safety, and high-level radioactive waste generation.
Authors:
 [1]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Purdue Univ., West Lafayette, IN (United States)
Publication Date:
OSTI Identifier:
1055292
Report Number(s):
LA-UR--11-01854; LA-UR--11-1854
TRN: US1600065
DOE Contract Number:
AC52-06NA25396
Resource Type:
Conference
Resource Relation:
Conference: 14. International Topical Meeting on Nuclear Reactor Thermohydraulics (NURETH-14), Toronto, ON (Canada), 25-30 Sep 2011
Research Org:
Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
Sponsoring Org:
USDOE
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; BERYLLIUM OXIDES; URANIUM DIOXIDE; NUCLEAR FUELS; THERMAL CONDUCTIVITY; FINITE ELEMENT METHOD; THERMAL HYDRAULICS; HIGH-LEVEL RADIOACTIVE WASTES; PERFORMANCE; REACTORS; SAFETY; COMPUTERIZED SIMULATION