A Trial on the Comparative Study of Thermal Environment Indices

von YOSHIDA, Joseph Akira
Veröffentlicht in Ningen-Netsukankyō Kei Shinpojiumu (8. : 1984 : Tokio) Dai 8kai Ningen-Netsukankyō Kei Shinpojiumu hōkokushū (1984)

ICONE2020-16736 Development of a Multiphase Particle Method for Melt-Jet Breakup Behavior of Molten Core in Severe Accident

von Wang, Zidi
Veröffentlicht in ASME International Conference on Nuclear Engineering (2020 : Online) Proceedings of the ASME International Conference on Nuclear Engineering - 2020 ; Volume 1: Beyond design basis, codes and standards, computational fluid dynamics (CFD), decontamination and decommissioning, nuclear fuel and engineering, nuclear plant engineering (2020)

Study on transient temperature measurement at fuel clad surface in NSRR experiments

von Bessiron, Vincent
Veröffentlicht 2007

Hannōdo jikoji no hifuku-kan hyōmen dennetsu kyodō - reikyaku jōken o paramēta to shita NSRR jikken : = Heat transfer from fuel rod surface under reactivity-initiated accident co...

von Udagawa, Yutaka
Veröffentlicht 2014

Analysis for the Accident at Unit 2 of the Fukushima Daiichi NPS with THALES2/KICHE Code in BSAF2 Project

von Tamaki, Hitoshi
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 1 of 9 (2020)

Outline of the OECD/NEA/ARC-F Project

von Nakatsuka, Toru
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 3 of 9 (2020)

Analysis for the Accident at Unit 1 of the Fukushima Daiichi NPS with THALES2/KICHE Code in BSAF2 Project

von Tamaki, Hitoshi
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 1 of 9 (2020)

ICONE2020-16841 Computational Study on the Spherical Laminar Flame Speed of Hydrogen-Air Mixtures

von Trianti, Nuri
Veröffentlicht in ASME International Conference on Nuclear Engineering (2020 : Online) Proceedings of the ASME International Conference on Nuclear Engineering - 2020 ; Volume 1: Beyond design basis, codes and standards, computational fluid dynamics (CFD), decontamination and decommissioning, nuclear fuel and engineering, nuclear plant engineering (2020)

Analysis for the Accident at Unit 3 of the Fukushima Daiichi NPS with THALES2/KICHE Code in BSAF2 Project

von Ishikawa, Jun
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 1 of 9 (2020)