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 DORA PSI
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. DORA PSI
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 DORA PSI
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 DORA PSI
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. DORA PSI
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.). DORA PSI
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.). DORA PSI
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 DORA PSI
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. DORA PSI
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. DORA PSI
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. DORA PSI
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.). DORA PSI
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. DORA PSI
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. DORA PSI
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 DORA PSI