Page Top

Hitachi

Hitachi-GE Nuclear Energy, Ltd.

Internal Pump Test Facility

We uses this facility to qualify the real pump units before installation, to demonstrate pump unites performance, and to develop pump system evaluation methodologies. In addition, it uses the facility to conduct training on installation and inspection services, as well as other activities that contribute to digital technology development.

Internal Pump Test Facility

Test Facility of Control Rod Scrammability under big Earthquake Conditions simulated

We use this facility to promote the function of a nuclear reactor urgent stop at the large earthquake and the improvement of the control rod operation simulation technique.

Cross Section of Test Facility

Multi-purpose steam source test facility (HUSTLE *1)

The facility has the capability of fulfilling two phase flow under BWR's actual pressure and temperature. By leveraging these features, the Company will secure technological advantages from key nuclear power business perspectives such as the construction of ESBWR*2 and small- and medium-sized reactors, the enhancement of power plant output, assessment of in-reactor behavior and safety issues, while also working on the development of reactor internals, and high temperature and pressure auxiliary equipment.
The testing facility flexibly supports a range of testing programs because the flow of water and steam can be adjusted as desired and a range of testing conditions can be established.

*1 HUSTLE:
Hitachi Utility Steam Test Leading facility
*2 ESBWR:
Economic Simplified BWR

Features

  • BWR's actual operating conditions (~7MPa/approx. 290℃)
  • Two-phased flow of water and steam
  • Steam recirculation made by the steam compressor

HUSTLE Test center

System configuration

Facility layout

Multi-purpose steam source testing facility