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Mon. Mar 27, 2017

Tue. Mar 28, 2017

Wed. Mar 29, 2017

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Room B 16-102 Building No.16

Room D 16-204 Building No.16

Room E 16-205 Building No.16

Room F 16-206 Building No.16

Room G 16-207 Building No.16

Room H 16-303 Building No.16

Room I 16-304 Building No.16

Room J 16-305 Building No.16

Room K 16-306 Building No.16

Room L 16-503 Building No.16

Room M 16-504 Building No.16

Over view Report

Joint Session

Technical division and Network

Board and Committee

Other Session

II. Radiation, Accelerator and Beam Technologies

III. Fission Energy Engineering

IV. Nuclear Fuel Cycle and Nuclear Materials

V. Fusion Energy Engineering

Planning Lecture (Free Entry)

Planning Lecture

Oral presentation

General Meeting

Fusion neutronics

Nuclear Fusion Engineering (First wall and Divertor)

Tritium technology (production and measurement)

Tritium technology (production and recovery)

Shielding materials, detector, code and material standard

Code and material standard

Outline of MEXT R&D programs for nuclear technology Around the International Programs

Shielding Materials

Minor actinide nuclear data 1

Minor actinide nuclear data 2

「核データ部会」第35回全体会議

Current Status and Future Perspective of the Verification and Validation (V&V) of JENDL and Nutronics Calculation Codes by use of the Benchmark Problems and Integral Experiments

Charged particle reaction

MA Transmutation

Strategy of Reactor Type

Core Neutronics Evaluation

Reports of the 10 year steps and the new trial on dialogue between students and seniors

Core Design 2 (Breeder Reactor)

Core Design 3

Design of He piping of HTTR and transport cask for accelerator target

Monitoring and Inspection

Plant Pre-operational Testing

「原子力発電部会」第31回全体会議

New Regulatory Approach to Strengthen Nuclear Power Station Safety

Water sealing technology for F1 1

Water sealing technology for F1 2

Development of minor actinide recovery processes 1

Development of minor actinide recovery processes 2

Denitration, high-level liquid waste, pyro-processing

「再処理・リサイクル部会」第32回全体会議

Expert Committee on Reprocessing Technologies for Future Generations How should be reprocessing technologies for future generations?

Separation and recovery of uranium, plutonium, thorium

Safety improvement in reprocessing facilities

Irradiation Effect

Pressure Vessel Materials

「若手連絡会（YGN）」第22回全体会議

Zirconium Alloys

Elemental Analysis

Accident Progression Analysis

Thermal Hydraulics Extension

Why should PRA standards be performance specification?

Two-Phase Flow and Phase Change 3

Nuclide separation and recovery 1

Nuclide separation and recovery 2

「バックエンド部会」第46回全体会議

Challenges for management of radioactively contaminated wastes and volume reduction and reuse/recycling of removed soil derived from the activities for environmental remediation after the Fukushima Daiichi Nuclear Power Station accident

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Date

2017 Annual Meeting