Focus on


Prototype Fast Breeder Reactor MONJU

1. Safety Assessment
2. Design Review using Plant Data
3. Technical Support for Operation






Mission


Our mission is to support the safety of MONJU by safety analysis and plant engineering research.
Our purpose (PDF)

Organization


We have six research groups under two departments.
Organization chart (PDF)

Location


We promote research activities taking advantage of the location close to Monju plant.
Access map (PDF)

Research and development


Nuclear Safety, Probabilistic Risk Assessment, Severe Accident Analysis, Thermal-Hydraulics, Reactor Physics, Sodium Technology and Non-Destructive Testing
R&D introduction

Publication


Research are presented in academic papers, conferences and JAEA reports.
JAEA publication

Cooperation


We collaborate with institutes and companies and participate in activities with local communities.
Local activities (PDF)




R&D introduction


Development of Multi-coil RF-ECT Sensor for JSFR SG Tubes -->PDF in Japanese

Large Scale ECT to Simulate ISI of Ferromagnetic SG Tubes of FBR -->PDF

Multi-Frequencies ECT Algorithms to Remove Sodium Noise in ISI of Ferromagnetic SG Tubes of FBR -->PDF

Experimental Study on Cavitation Inception in a Flowing Liquid Metal System -->PDF in Japanese

FEM Comparisons between RF-ECT Signals in Quasi-Static or Transient and Linear or Nonlinear Regimes for In-service Inspection of magnetic SG tubes in FBR -->PDF

Reactive Wetting of Metallic Plated Steels by Liquid Sodium -->PDF in Japanese

Evaluation of The Hydrogen Behavior by Fast Reactor Tritium Behavior Analysis Code(TTT) -->PDF in Japanese

Adjustment of 241Am Cross Section with Monju Reactor Physics Data -->PDF file in Japanese

Criticality Evaluation for the Monju Restart Core -->PDF file in Japanese

Control Rod Worth Evaluation for the Monju Restart Core -->PDF file in Japanese

Isothermal Temperature Coefficient Evaluation for the Monju Restart Core -->PDF file in Japanese

Evaluation of MONJU Core Damage Risk with Change of AOT Using Probabilistic Method -->PDF file in Japanese

Plant Dynamics Evaluation of a Monju Ex-vessel Fuel Storage System during a Station Blackout -->PDF file in Japanese

Evaluation on Core Cooling Capability in Monju by Natural Circulation under an Earthquake And Subsequent Tsunami -->PDF file in Japanese

List of Related Papers -->PDF file

External Review


Severe Accident Management Review Committee based on The 2011 Tohoku Earthquake
External specialists reviewed the safety principle and core coolability of Monju in case of beyond design base earthquake and tsunami.
May - September, 2011
-->Japanese page





Monju safety comprehensive evaluation committee
External specialists comments severe accident analysis and safety measures of Monju.
Ongoing from November, 2011
-->Japanese page



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