⌘+K

Pulse Explore Communities Researchers Journals

Home Communities Explore

January 1, 2026Journal of the Atomic Energy Society of JapanOpen Access

Studies aimed at clarifying thermal-hydraulic behavior during the 1F accident

Ikken Sato Takuya Yamashita

View Full Paper

Ask AI

Bookmark

Share

Key Points

The aim is to understand the thermal-hydraulic behavior of fuel debris during the 1F nuclear accident.
Integrated analysis of plant investigation results and accident progression data.
Evaluation of thermal conditions during the transition of fuel debris from the reactor pressure vessel to the pedestal.
Utilization of objective data to correlate with analytical evaluations.
Estimated the most likely behavior of fuel debris under current thermal conditions.
Identified critical phases of fuel debris transition during the accident.

Implication

Analyses estimate fuel debris behavior in relation to reactor pressure and accident progression.

Abstract

No abstract yet. The journal hasn't published one we can show.

Discussion

No takes yet. Share an insight, caveat, or question.

Cite This Study

Sato et al. (2026) studied this question.

synapsesocial.com/papers/6a02c2b9ce8c8c81e9640387 https://doi.org/10.3327/jaesjb.68.5_306

View Full Paper

Ask AI

Bookmark

Share

Keep reading

Synapse has enriched 5 closely related papers on similar clinical questions. Consider them for comparative context:

1Characterization of fuel debris at JAEA Oarai Nuclear Engineering Institute-Development of analytical infrastructure and advancement of analytical technologies at the fuels monitoring facility (FMF)Original Research · 2026
2Early-phase core degradation interpretation by interaction between fuel cladding and fuel components in Fukushima Daiichi nuclear power plant Unit 22024
3Step-by-step challenge of debris characterization for the decommissioning of Fukushima-Daiichi Nuclear Power Station (FDNPS)Narrative Review · 2022 · 36 citations
4Clarification of key input parameters for site boundary dose due to criticality of fuel debris at the Fukushima Daiichi nuclear power plantOriginal Research · 2026
5MAAP code analysis for the in-vessel phase of Fukushima-Daiichi Nuclear Power Station Unit 1 and comparison of the results among Units 1 to 32024 · 6 citations

More related papers

Corrosion Challenges and Electrochemical Approaches for the Decommissioning of the Fukushima Daiichi Nuclear Power Station2026
Simulation of Iodine Spiking phenomenon during Design Extended Condition type A conditions at VVER-1000 and Generic PWR2024
Simulation of an accident in conditions of cooling system malfunction and ventilation system failure in the spent fuel storage pool of the multipurpose fast research reactor2025

More from Journal of the Atomic Energy Society of Japan

Current status and future prospects of the Horonobe international project (HIP)Thu,
第21回放射性物質輸送国際会議patram2025Thu,