OECD/NEA Sandia Fuel Project phase I: Benchmark of the ignition testing

•A unique PWR spent fuel pool experimental project is analytically investigated.•Predictability of fuel clad ignition in case of a complete loss of coolant in SFPs is assessed.•Computer codes reasonably estimate peak cladding temperature and time of ignition. The OECD/NEA Sandia Fuel Project provide...

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Published inNuclear engineering and design Vol. 307; pp. 418 - 430
Main Authors Adorni, Martina, Herranz, Luis E., Hollands, Thorsten, Ahn, Kwang-II, Bals, Christine, D'Auria, Francesco, Horvath, Gabor L., Jaeckel, Bernd S., Kim, Han-Chul, Lee, Jung-Jae, Ogino, Masao, Techy, Zsolt, Velazquez-Lozad, Alexander, Zigh, Abdelghani, Rehacek, Radomir
Format Journal Article
LanguageEnglish
Published Elsevier B.V 01.10.2016
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Summary:•A unique PWR spent fuel pool experimental project is analytically investigated.•Predictability of fuel clad ignition in case of a complete loss of coolant in SFPs is assessed.•Computer codes reasonably estimate peak cladding temperature and time of ignition. The OECD/NEA Sandia Fuel Project provided unique thermal-hydraulic experimental data associated with Spent Fuel Pool (SFP) complete drain down. The study conducted at Sandia National Laboratories (SNL) was successfully completed (July 2009 to February 2013). The accident conditions of interest for the SFP were simulated in a full scale prototypic fashion (electrically heated, prototypic assemblies in a prototypic SFP rack) so that the experimental results closely represent actual fuel assembly responses. A major impetus for this work was to facilitate severe accident code validation and to reduce modeling uncertainties within the codes. Phase I focused on axial heating and burn propagation in a single PWR 17×17 assembly (i.e. “hot neighbors” configuration). Phase II addressed axial and radial heating and zirconium fire propagation including effects of fuel rod ballooning in a 1×4 assembly configuration (i.e. single, hot center assembly and four, “cooler neighbors”). This paper summarizes the comparative analysis regarding the final destructive ignition test of the phase I of the project. The objective of the benchmark is to evaluate and compare the predictive capabilities of computer codes concerning the ignition testing of PWR fuel assemblies. Nine institutions from eight different countries were involved in the benchmark calculations. The time to ignition and the maximum temperature are adequately captured by the calculations. It is believed that the benchmark constitutes an enlargement of the validation range for the codes to the conditions tested, thus enhancing the code applicability to other fuel assembly designs and configurations. The comparison of lumped parameter and CFD computer codes represents a further valuable achievement.
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ISSN:0029-5493
1872-759X
DOI:10.1016/j.nucengdes.2016.07.016