Benchmark Analysis on Loss-of-Flow-without-Scram Test of FFTF Using Refined SAC-3D Models

The Fast Flux Test Facility (FFTF) is a liquid sodium-cooled nuclear reactor designed by the Westinghouse Electric Corporation for the U.S. Department of Energy. In July 1986, a series of unprotected transients were performed to demonstrate the passive safety of FFTF. Among these, a total of 13 loss...

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Autores principales:	Siyu Lyu, Daogang Lu, Danting Sui
Formato:	article
Lenguaje:	EN
Publicado:	Hindawi Limited 2021
Materias:	Electrical engineering. Electronics. Nuclear engineering TK1-9971
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spelling	oai:doaj.org-article:d198fd73590d4b57859dd211dff471c62021-11-22T01:10:50ZBenchmark Analysis on Loss-of-Flow-without-Scram Test of FFTF Using Refined SAC-3D Models1687-608310.1155/2021/5843910https://doaj.org/article/d198fd73590d4b57859dd211dff471c62021-01-01T00:00:00Zhttp://dx.doi.org/10.1155/2021/5843910https://doaj.org/toc/1687-6083The Fast Flux Test Facility (FFTF) is a liquid sodium-cooled nuclear reactor designed by the Westinghouse Electric Corporation for the U.S. Department of Energy. In July 1986, a series of unprotected transients were performed to demonstrate the passive safety of FFTF. Among these, a total of 13 loss-of-flow-without scram (LOFWOS) tests were conducted to confirm the liquid metal reactor safety margins, provide data for computer code validation, and demonstrate the inherent and passive safety benefits of specific design features. In our preliminary work, we have performed relatively coarse modeling of the FFTF. To better predict the transient behavior of FFTF LOFWOS test #13, we modeled it using a more refined thermal-hydraulics model. In this paper, we simulate FFTF LOFWOS test #13 with the system safety analysis code SAC-3D according to the benchmark specifications provided by Argonne National Laboratory (ANL). The simulation range includes the primary and secondary circuits. The reactor core was modeled by the built-in 3D neutronics calculation module and the parallel-channel thermal-hydraulics calculation module. To better predict the reactivity feedback introduced by coolant level variations within the GEMs, a real-time macro cross-section homogenization processing module was developed. The steady-state power distribution was calculated as the transient simulation initial boundary conditions. In general, both the steady-state calculation results and the whole-plant transient behavior predictions are in good agreement with the measured data. The relatively large deviations in transient simulation occur in the outlet temperature predictions of the PIOTA in row 6. It can be preliminarily explained by the reason for neglecting the heat transfer between channels in this model.Siyu LyuDaogang LuDanting SuiHindawi LimitedarticleElectrical engineering. Electronics. Nuclear engineeringTK1-9971ENScience and Technology of Nuclear Installations, Vol 2021 (2021)
institution	DOAJ
collection	DOAJ
language	EN
topic	Electrical engineering. Electronics. Nuclear engineering TK1-9971
spellingShingle	Electrical engineering. Electronics. Nuclear engineering TK1-9971 Siyu Lyu Daogang Lu Danting Sui Benchmark Analysis on Loss-of-Flow-without-Scram Test of FFTF Using Refined SAC-3D Models
description	The Fast Flux Test Facility (FFTF) is a liquid sodium-cooled nuclear reactor designed by the Westinghouse Electric Corporation for the U.S. Department of Energy. In July 1986, a series of unprotected transients were performed to demonstrate the passive safety of FFTF. Among these, a total of 13 loss-of-flow-without scram (LOFWOS) tests were conducted to confirm the liquid metal reactor safety margins, provide data for computer code validation, and demonstrate the inherent and passive safety benefits of specific design features. In our preliminary work, we have performed relatively coarse modeling of the FFTF. To better predict the transient behavior of FFTF LOFWOS test #13, we modeled it using a more refined thermal-hydraulics model. In this paper, we simulate FFTF LOFWOS test #13 with the system safety analysis code SAC-3D according to the benchmark specifications provided by Argonne National Laboratory (ANL). The simulation range includes the primary and secondary circuits. The reactor core was modeled by the built-in 3D neutronics calculation module and the parallel-channel thermal-hydraulics calculation module. To better predict the reactivity feedback introduced by coolant level variations within the GEMs, a real-time macro cross-section homogenization processing module was developed. The steady-state power distribution was calculated as the transient simulation initial boundary conditions. In general, both the steady-state calculation results and the whole-plant transient behavior predictions are in good agreement with the measured data. The relatively large deviations in transient simulation occur in the outlet temperature predictions of the PIOTA in row 6. It can be preliminarily explained by the reason for neglecting the heat transfer between channels in this model.
format	article
author	Siyu Lyu Daogang Lu Danting Sui
author_facet	Siyu Lyu Daogang Lu Danting Sui
author_sort	Siyu Lyu
title	Benchmark Analysis on Loss-of-Flow-without-Scram Test of FFTF Using Refined SAC-3D Models
title_short	Benchmark Analysis on Loss-of-Flow-without-Scram Test of FFTF Using Refined SAC-3D Models
title_full	Benchmark Analysis on Loss-of-Flow-without-Scram Test of FFTF Using Refined SAC-3D Models
title_fullStr	Benchmark Analysis on Loss-of-Flow-without-Scram Test of FFTF Using Refined SAC-3D Models
title_full_unstemmed	Benchmark Analysis on Loss-of-Flow-without-Scram Test of FFTF Using Refined SAC-3D Models
title_sort	benchmark analysis on loss-of-flow-without-scram test of fftf using refined sac-3d models
publisher	Hindawi Limited
publishDate	2021
url	https://doaj.org/article/d198fd73590d4b57859dd211dff471c6
work_keys_str_mv	AT siyulyu benchmarkanalysisonlossofflowwithoutscramtestoffftfusingrefinedsac3dmodels AT daoganglu benchmarkanalysisonlossofflowwithoutscramtestoffftfusingrefinedsac3dmodels AT dantingsui benchmarkanalysisonlossofflowwithoutscramtestoffftfusingrefinedsac3dmodels
_version_	1718418369694138368

Benchmark Analysis on Loss-of-Flow-without-Scram Test of FFTF Using Refined SAC-3D Models

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