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Title: HTR 2014 Paper - Comparison of fission product release predictions using PARFUME with results from the AGR-1 safety tests

Abstract

Safety tests were conducted on fourteen fuel compacts from AGR-1, the first irradiation experiment of the Advanced Gas Reactor (AGR) Fuel Development and Qualification program, at temperatures ranging from 1600 to 1800°C to determine fission product release at temperatures that bound reactor accident conditions. The PARFUME (PARticle FUel ModEl) code was used to predict the release of fission products silver, cesium, strontium, and krypton from fuel compacts containing tristructural isotropic (TRISO) coated particles during the safety tests, and the predicted values were compared with experimental results. Preliminary comparisons between PARFUME predictions and post-irradiation examination (PIE) results of the safety tests show an overall over-prediction of the fractional release of these fission products, which is largely attributed to an over-estimation of the diffusivities used in the modeling of fission product transport in TRISO-coated particles. Correction factors to these diffusivities were assessed for silver and cesium in order to enable a better match between the modeling predictions and the safety testing results. In the case of strontium, correction factors could not be assessed because potential release during the safety tests could not be distinguished from matrix content released during irradiation. In the case of krypton, all the coating layers are partly retentivemore » and the available data did not allow to determine their respective retention powers, hence preventing to derive any correction factors.« less

Authors:
Publication Date:
Research Org.:
Idaho National Laboratory (INL)
Sponsoring Org.:
DOE - NE
OSTI Identifier:
1169231
Report Number(s):
INL/CON-14-32983
DOE Contract Number:  
DE-AC07-05ID14517
Resource Type:
Conference
Resource Relation:
Conference: HTR 2014,Weihai, Shandong Province, China,10/27/2014,10/31/2014
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; AGR-1; PARFUME; TRISO

Citation Formats

Collin, Blaise P. HTR 2014 Paper - Comparison of fission product release predictions using PARFUME with results from the AGR-1 safety tests. United States: N. p., 2001. Web.
Collin, Blaise P. HTR 2014 Paper - Comparison of fission product release predictions using PARFUME with results from the AGR-1 safety tests. United States.
Collin, Blaise P. Mon . "HTR 2014 Paper - Comparison of fission product release predictions using PARFUME with results from the AGR-1 safety tests". United States. https://www.osti.gov/servlets/purl/1169231.
@article{osti_1169231,
title = {HTR 2014 Paper - Comparison of fission product release predictions using PARFUME with results from the AGR-1 safety tests},
author = {Collin, Blaise P.},
abstractNote = {Safety tests were conducted on fourteen fuel compacts from AGR-1, the first irradiation experiment of the Advanced Gas Reactor (AGR) Fuel Development and Qualification program, at temperatures ranging from 1600 to 1800°C to determine fission product release at temperatures that bound reactor accident conditions. The PARFUME (PARticle FUel ModEl) code was used to predict the release of fission products silver, cesium, strontium, and krypton from fuel compacts containing tristructural isotropic (TRISO) coated particles during the safety tests, and the predicted values were compared with experimental results. Preliminary comparisons between PARFUME predictions and post-irradiation examination (PIE) results of the safety tests show an overall over-prediction of the fractional release of these fission products, which is largely attributed to an over-estimation of the diffusivities used in the modeling of fission product transport in TRISO-coated particles. Correction factors to these diffusivities were assessed for silver and cesium in order to enable a better match between the modeling predictions and the safety testing results. In the case of strontium, correction factors could not be assessed because potential release during the safety tests could not be distinguished from matrix content released during irradiation. In the case of krypton, all the coating layers are partly retentive and the available data did not allow to determine their respective retention powers, hence preventing to derive any correction factors.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2001},
month = {10}
}

Conference:
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