Laboratory Overview

Nuclear power generation is attracting renewed attention as a green energy source for a decarbonized society, and it is desired that the safety of nuclear facilities be improved. Research Group for Corrosion Resistant Materials is contributing to improvement of the reliability and safety of nuclear equipment by “elucidating corrosion mechanisms,” “investigating reproducible testing methods and life prediction methods,” and “developing highly durable materials” to ensure that metal materials used in the nuclear field do not lose their original functions due to degradation caused by corrosion.

Research on Corrosion Protection of Materials for Nuclear Fuel Reprocessing Facilities

In nuclear fuel reprocessing facilities, several kinds of metals are used in highly corrosive boiling nitric acid, and it is concerned that safety of the facilities will be reduced due to corrosion. In order to improve the safety of the facility, understanding of the corrosion mechanism and novel high corrosion resistant materials are desired.

• Research on corrosion mechanism of stainless steel in boiling nitric acid solution with radioactive ion species
• Development of ultra-high purity stainless steel with high corrosion resistance
• Development of intergranular corrosion calculation model for stainless steel

Research on Corrosion Protection of Structural Materials in Nuclear Reactors

Localized corrosion, as typified by stress corrosion cracking of in-core structural materials, is one of the problems in nuclear reactors, which are exposed to high temperature, high pressure water environment and strong radiation.

• Research on corrosion behavior of stainless steel in high temperature and high-pressure water
• Evaluation of effect of water radiolysis products on corrosion of stainless steel
• Research on mechanism of stress corrosion cracking in high-temperature, high-pressure water
• Development of electrochemical test equipment in a simulated core environment

Research on Decommissioning of Fukushima Daiichi Nuclear Power Plant

Decommissioning work at the Fukushima Daiichi Nuclear Power Plant (1F) is performed in a severe corrosive environment that differs from normal operation. In order to ensure the safety of decommissioning work over a long period of time, understandings of corrosion specific to 1F is desired.

• Research on corrosion mechanism of structural materials accelerated by products of water radiolysis
• Research on corrosion mechanism of structural materials in liquid film environment of reactor containment vessel wall
• Development of inhibitor to prevent corrosion of nuclear structural materials

Research on Target Window Material Evaluation Technique for Accelerator Driven System

In order to develop Accelerator Driven System (ADS), which reduce the volume and hazardousness of radioactive waste, it is important to establish corrosion inhibition technique for steel materials in a lead-bismuth environment.

• Research on appropriate lead-bismuth use environment (temperature and oxygen concentration)
• Research and development of sensor technology for oxygen concentration control and measurement