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Issues
January 2025
In Progress
ISSN 2332-8983
EISSN 2332-8975
Research Papers
Nuclear Safety/Security and Beyond Design Basis Events
Development of an Artificial Intelligence-Based Predictive Anomaly Detection System to Nuclear Power Plant
Ryota Miyake, Shinya Tominaga, Yusuke Terakado, Naoyuki Takado, Toshio Aoki, Chikashi Miyamoto, Susumu Naito, Yasunori Taguchi, Yuichi Kato, Kota Nakata
ASME J of Nuclear Rad Sci. January 2025, 11(1): 011701.
doi: https://doi.org/10.1115/1.4064123
Nuclear Education and Public Acceptance
Survey Analysis of Potential Nuclear Safety Research of Thailand for International Research Collaborative Reinforcement in the 2020s
ASME J of Nuclear Rad Sci. January 2025, 11(1): 012201.
doi: https://doi.org/10.1115/1.4063162
Topics:
Safety
Use of Modeling as an Enabler for Cross-Topic Knowledge Management and Ontologies to Support Return of Experience and Replicability of Large Nuclear Projects
ASME J of Nuclear Rad Sci. January 2025, 11(1): 012202.
doi: https://doi.org/10.1115/1.4064466
Topics:
Modeling
,
Teams
,
Knowledge management
,
Workflow
,
Systems engineering
,
Design
,
Engineering disciplines
Legal Issues of Fusion Technologies
ASME J of Nuclear Rad Sci. January 2025, 11(1): 012203.
doi: https://doi.org/10.1115/1.4065066
Topics:
Liabilities
,
Nuclear fusion
,
Nuclear power
,
Radioactive wastes
,
Regulations
,
Safety
,
Nuclear fission
,
Licensing
,
Fuels
Analysis of Stakeholders' Trust Level in the Nuclear Energy Domain in Japan
Kyohei Yoshinaga, Masaki Onodera, Kosuke Shirai, Nobuaki Yoshizawa, Harunaga Yanagawa, Takamichi Kito
ASME J of Nuclear Rad Sci. January 2025, 11(1): 012204.
doi: https://doi.org/10.1115/1.4064778
Topics:
Nuclear power
Technical Briefs
Development of Risk Informed Aging Management Program in Decommissioning
ASME J of Nuclear Rad Sci. January 2025, 11(1): 014501.
doi: https://doi.org/10.1115/1.4065139
Topics:
Maintenance
,
Nuclear decommissioning
,
Nuclear power stations
,
Safety
,
Fire
,
Risk
Email alerts
RSS Feeds
Operation Optimization Framework for Advanced Reactors Using a Data Driven Digital Twin
ASME J of Nuclear Rad Sci
Investigation of Metal–H2O Systems at Elevated Temperatures: Part III: Solubility Data and New Zr Pourbaix Diagrams at 298.15 K and 373.15 K
ASME J of Nuclear Rad Sci (April 2025)
Investigation of Metal-H2O Systems at Elevated Temperatures: Part II. SnO2(s) Solubility Data and New Sn Pourbaix Diagrams at 298.15 K and 358.15 K
ASME J of Nuclear Rad Sci (April 2025)
Investigation of Metal–H2O Systems at Elevated Temperatures: Part I. Development of a Solubility Apparatus Specialized for Super-Ambient Conditions
ASME J of Nuclear Rad Sci (April 2025)
Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications
ASME J of Nuclear Rad Sci
