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Title: Supplying materials needed for grain growth characterizations of nano-grained UO2

This activity is supported by the US Nuclear Energy Advanced Modeling and Simulation (NEAMS) Fuels Product Line (FPL) and aims at providing experimental data for the validation of the mesoscale simulation code MARMOT. MARMOT is a mesoscale multiphysics code that predicts the coevolution of microstructure and properties within reactor fuel during its lifetime in the reactor. It is an important component of the Moose-Bison-Marmot (MBM) code suite that has been developed by Idaho National Laboratory (INL) to enable next generation fuel performance modeling capability as part of the NEAMS Program FPL. In order to ensure the accuracy of the microstructure based materials models being developed within the MARMOT code, extensive validation efforts must be carried out. In this report, we summarize our preliminary synchrotron radiation experiments at APS to determine the grain size of nanograin UO2. The methodology and experimental setup developed in this experiment can directly apply to the proposed in-situ grain growth measurements. The investigation of the grain growth kinetics was conducted based on isothermal annealing and grain growth characterization as functions of duration and temperature. The kinetic parameters such as activation energy for grain growth for UO2 with different stoichiometry are obtained and compared with molecular dynamicsmore » (MD) simulations.« less
Authors:
 [1] ;  [1] ;  [1] ;  [1] ;  [2] ;  [2]
  1. Argonne National Lab. (ANL), Argonne, IL (United States)
  2. Rensselaer Polytechnic Inst., Troy, NY (United States)
Publication Date:
OSTI Identifier:
1227385
Report Number(s):
ANL/NE--15/27
121527; TRN: US1500910
DOE Contract Number:
AC02-06CH11357
Resource Type:
Technical Report
Research Org:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org:
USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation (NA-20)
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 36 MATERIALS SCIENCE; URANIUM DIOXIDE; GRAIN SIZE; GRAIN GROWTH; EXPERIMENTAL DATA; COMPUTERIZED SIMULATION; SYNCHROTRON RADIATION; VALIDATION; MOLECULAR DYNAMICS METHOD; ACTIVATION ENERGY; COMPARATIVE EVALUATIONS; ANNEALING; AVAILABILITY; TIME DEPENDENCE; TEMPERATURE DEPENDENCE; KINETICS; MICROSTRUCTURE; B CODES; M CODES; STOICHIOMETRY