2019
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Dehbi A, Kelm S, Kalilainen J, Mueller H
The influence of thermal radiation on the free convection inside enclosures
Nuclear Engineering and Design. 2019; 341: 176-185. https://doi.org/10.1016/j.nucengdes.2018.10.025
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Fernandez Moguel L, Lind T, Rýdl A
Analysis of fission product transport in unit 3 of Fukushima Daiichi
In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS); 2019:508-521.
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Fernandez-Moguel L, Rydl A, Lind T
Updated analysis of Fukushima Unit 3 with MELCOR 2.1. Part 2: fission product release and transport analysis
Annals of Nuclear Energy. 2019; 130: 93-106. https://doi.org/10.1016/j.anucene.2019.02.017
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Fernandez-Moguel L, Rydl A, Lind T
Updated analysis of Fukushima unit 3 with MELCOR 2.1. Part 1: thermal-hydraulic analysis
Annals of Nuclear Energy. 2019; 123: 59-77. https://doi.org/10.1016/j.anucene.2018.09.008
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Herranz LE, Pellegrini M, Lind T, Sonnenkalb M, Godin-Jacqmin L, López C, et al.
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF) phase II – results of severe accident analyses for Unit 1
In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS); 2019:1107-1118.
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Jäckel BS, Lind T, Fernandez-Moguel L, Steinbrück M, Park S
Application of a newly developed computer code model for nitriding and re-oxidation of cladding materials on separate effect tests and integral experiments
In: Proceedings of the ERMSAR 2019. sine loco: sine nomine; 2019:024 (14 pp.).
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Kalilainen J, Lind T, Stuckert J, Stegmaier U
Aerosol results of the QUENCH-18 bundle test
In: Proceedings of the ERMSAR 2019. sine loco: sine nomine; 2019:019 (11 pp.).
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Kalilainen J, Lind T, Stuckert J, Bergfeldt T, Sippula O, Jokiniemi J
The measurement of Ag/In/Cd release under air-ingress conditions in the QUENCH-18 bundle test
Journal of Nuclear Materials. 2019; 517: 315-327. https://doi.org/10.1016/j.jnucmat.2019.02.021
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Lind T, Campbell S, Herranz LE, Kissane M, Song JH
A summary of fission-product-transport phenomena during SGTR severe accidents
In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park, IL, USA: American Nuclear Society (ANS); 2019:4063-4075.
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Lind T, Guentay S, Herranz LE, Suckow D
A summary of the ARTIST: aerosol retention during SGTR severe accident
Annals of Nuclear Energy. 2019; 131: 385-400. https://doi.org/10.1016/j.anucene.2019.04.006
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Lind T, Pellegrini M, Herranz LE, Sonnenkalb M, Nishi Y, Tamaki H, et al.
Overwiew and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF) phase II – results of severe accident analyses for Unit 3
In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS); 2019:1133-1146.
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Manara D, Jacquemain D, Van Dorsselaere JP, Bottomley PD, Adorni M, Journeau C, et al.
Severe accident research priority ranking: a new assessment eight years after the Fukushima Daiichi accident
In: Proceedings of the ERMSAR 2019. sine loco: sine nomine; 2019:1-25.
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Papadopoulos P, Tietze S, Suckow D, Ceder SJ, Roth B, Lind T
Hydrodynamic characterisation inside a wet scrubber for different flow regimes relevant for pool scrubbing and FCVS
In: Proceedings of the ERMSAR 2019. Prague: AF POWER agency; 2019:028 (10 pp.).
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Pellegrini M, Herranz L, Sonnenkalb M, Lind T, Maruyana Y, Gaunt R, et al.
Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF project
In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS); 2019:1147-1162.
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Sonnenkalb M, Pellegrini M, Herranz LE, Lind T, Morreale AC, Kanda K, et al.
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF) phase II – results of severe accident analyses for unit 2
In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS); 2019:1119-1132.
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Yang J, Suckow D, Lind T, Prasser H-M
Study of level swell for a Filtered Containment Venting System at the VEFITA facility
Progress in Nuclear Energy. 2019; 113: 7-17. https://doi.org/10.1016/j.pnucene.2019.01.003
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