TY - GEN
T1 - Modeling and analysis of fission product transport in the AGR-3/4 experiment
AU - Humrickhouse, Paul W.
AU - Collin, Blaise P.
AU - Hawkes, Grant L.
AU - Harp, Jason M.
AU - Demkowicz, Paul A.
AU - Petti, David A.
PY - 2016
Y1 - 2016
N2 - In this work we describe the ongoing modeling and analysis efforts in support of the AGR-3/4 experiment. AGR-3/4 is intended to provide data to assess fission product retention and transport (e.g., diffusion coefficients) in fuel matrix and graphite materials. We describe a set of pre-test predictions that incorporate the results of detailed thermal and fission product release models into a coupled 1D radial diffusion model of the experiment, using diffusion coefficients reported in the literature for Ag, Cs, and Sr. We make some comparisons of the predicted Cs profiles to preliminary measured data and find these to be reasonable, in most cases within an order of magnitude. Our ultimate objective is to refine the diffusion coefficients using AGR-3/4 data, so we develop an analytical method for doing so and demonstrate its efficacy via a series of numerical experiments using the model predictions.
AB - In this work we describe the ongoing modeling and analysis efforts in support of the AGR-3/4 experiment. AGR-3/4 is intended to provide data to assess fission product retention and transport (e.g., diffusion coefficients) in fuel matrix and graphite materials. We describe a set of pre-test predictions that incorporate the results of detailed thermal and fission product release models into a coupled 1D radial diffusion model of the experiment, using diffusion coefficients reported in the literature for Ag, Cs, and Sr. We make some comparisons of the predicted Cs profiles to preliminary measured data and find these to be reasonable, in most cases within an order of magnitude. Our ultimate objective is to refine the diffusion coefficients using AGR-3/4 data, so we develop an analytical method for doing so and demonstrate its efficacy via a series of numerical experiments using the model predictions.
UR - http://www.scopus.com/inward/record.url?scp=85026305224&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:85026305224
T3 - International Topical Meeting on High Temperature Reactor Technology, HTR 2016
SP - 863
EP - 877
BT - International Topical Meeting on High Temperature Reactor Technology, HTR 2016
PB - American Nuclear Society
T2 - 8th International Topical Meeting on High Temperature Reactor Technology, HTR 2016
Y2 - 6 November 2016 through 10 November 2016
ER -