Nuclear power technologies

Fuji Electric Nuclear power

Three core technologies

Remote handling　technology

Radioactive waste treatment technology

Nuclear reactor engineering technology

Two features

1.

Cooperated with the Japan Atomic Energy Agency for research on the core design and safety analysis of the first high temperature gas-cooled reactor (HTTR, High Temperature Engineering Test Reactor) in Japan.
2.

Supplied internal structure and fuel handling equipment for the HTTR reactor.

High-temperature gas-cooled reactors

A high-temperature gas-cooled reactor has an inherently high level of safety, by removing high-temperature heat energy near 1,000°C and preventing core meltdown accidents even if the coolant is lost. We have a track record of providing reactor internal structures and fuel handling equipment for the HTTR test reactor.

Products

HTTR core support structure
HTTR fuel handling equipment
HTTR fuel handling machine
HTTR ex-vessel fuel transfer machine
HTTR spent fuel storage facility

Experimental equipment and commissioned testing

Large structural equipment verification test loop (HENDEL)
Seismic resistance testing on hearth floor

Criticality test equipment

Criticality test equipment is used to obtain the data necessary for the design, operation and safety evaluation of nuclear reactors, and it is an extremely low output nuclear reactor. We designed, manufactured and installed fast critical assembly (FCA) and deuterium critical assembly (DCA) equipment. The mating face of the FCA split core was manufactured with particularly high accuracy.

Product

Criticality test equipment

Track record

Fast critical assembly (FCA)
Deuterium critical assembly (DCA)

Nuclear fusion reactor related equipment

We are developing a superconducting power transmission system (current lead, superconducting bus line) for the nuclear fusion reactor experimental facilities that are being developed worldwide as a future energy source. This is a superconducting power transmission system for the Large Helical Device of the National Institute for Fusion Science, and is a system that supplies electric power with superconducting wire from the ambient temperature end through the current lead to the terminal of the superconducting coil. The system consists of nine flexible transfer tubes.