Evaluation of dose rate and uncertainty of fuel debris in a canister for the safe retrieval of damaged nuclear fuel [PDF]
, 2021 Damaged fuel from core melting accidents like Three Mile Island and Fukushima Daiichi need to be retrieved and disposed. Retrieval of damaged fuel is considerably more complex than for standard fuel as fuel is relocated and deformed during the accident ...
LEE, KYOUNGJIN
core
The Proceedings of the International Conference on Nuclear Engineering (ICONE), 2019 Christophe Journeau +2 more
exaly +2 more sources
The Proceedings of the International Conference on Nuclear Engineering (ICONE), 2019 Christophe Journeau +1 more
exaly +2 more sources
Proceedings of the International Topical Workshop on Fukushima Decommissioning ResearchShunichi Suzuki +2 more
exaly +2 more sources
Development of Numerical Simulation Method to Evaluate Heat Transfer Performance of Air Around Fuel Debris: Part 2 — Validation of JUPITER for Free Convection Heat Transfer [PDF]
, 2017 A dry method is one of fuel debris retrieval methods for decommissioning of TEPCO’s Fukushima Daiichi nuclear power station. If stopping the water leakage from a damaged primary containment vessel (PCV) is impossible, the dry method may be adopted ...
Mitsuhiko Shibata +3 more
core +1 more source
Development of Numerical Simulation Method to Evaluate Heat Transfer Performance of Air Around Fuel Debris: Part 1 — Effect of the Debris Shape [PDF]
, 2017 Fuel debris retrieval in atmospheric conditions is proposed as one candidate in the Fukushima Daiichi NPS since it can suppress generation of the contaminated water. However, there are unknowns and uncertainties to evaluate the air cooling performance of
Shinichiro Uesawa +2 more
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Final Report - Spent Nuclear Fuel Retrieval System Manipulator System Cold Validation Testing [PDF]
, 1999 Manipulator system cold validation testing (CVT) was performed in support of the Fuel Retrieval System (FRS) Sub-Project, a subtask of the Spent Nuclear Fuel Project at the Hanford Site in Richland, Washington.
Jackson, D.R., Kiebel, G.R.
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Spent nuclear fuel retrieval system fuel handling development testing. Final report [PDF]
, 1997 Fuel handling development testing was performed in support of the Fuel Retrieval System (FRS) Sub-Project, a subtask of the Spent Nuclear Fuel Project at the Hanford Site in Richland, Washington.
Meeuwsen, P.V., Jackson, D.R.
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Characterization of Aerosols Emitted during Core Boring of Prototypic Fukushima Daiichi Fuel Debris Simulants [PDF]
, 2023 International audienceOne of the important challenges for the decommissioning of the damaged reactors of the Fukushima Daiichi Nuclear Power Station (1F) is the fuel debris retrieval.
Bouyer, Viviane +9 more
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Characterization of chemical composition and particle size distribution ofaerosols released during laser cutting of fuel debris simulants [PDF]
, 2020 International audienceWe present here the results regarding the characterization of chemical composition and size distribution ofaerosols released during laser cutting of two types of fuel debris simulants (Ex-Vessel and In-Vessel scenarios) inair and ...
Excoffier, Emmanuel +7 more
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