The Mitsubishi Research Institute (MRI, Japan) has selected a consortium of RosRAO (project leader) and TENEX for the feasibility study of the project in the first stage of subsidized program “The project for decommissioning and handling of contaminated water (Development project of basic technologies for extraction of fuel fragments and internals (Development of small neutron detector)).
The offer of the RosRAO-led consortium is to develop an integrated high-sensitivity neutron detector with auto adjustment depending on a gamma-radiation dose rate and temperature. The goal of the project is to develop a method for most accurate search and identification of fuel fragments at Fukushima Daiichi NPP.
The decision to develop the neutron detector system will be made based on results of the said feasibility study. “Our project aims at developing search methods of the reactor space at Fukushima Daiichi NPP to identify fuel fragments by their neutron radiation. Following the project results, the Japanese side wants to gain a pilot specimen of the system for searching fuel fragments and test it in one of the plant’s units. At the present time, all project participants start pre-project studies. After them the Japanese side will make a decision on further implementation of the project,” Sergey Florya, RosRAO’s head of project office for innovations, commented.
For information:
FSUE RosRAO is a ROSATOM company managing radioactive waste and decommissioning of nuclear facilities in the Russian Federation.
TENEX is the leading foreign-trade company of ROSATOM which is an integrator of foreign sales of nuclear back-end products and services.
RosRAO plans to engage A. I. Leipunski SRC IPPE (a ROSATOM company) as the scientific supervisor of the project.
RosRAO has taken part in the project for decommissioning and handling of contaminated water since 2014. In August 2014, RosRAO, as the leader of the consortium, was selected by the Mitsubishi Research Institute for implementing the demonstration project of verification of the technology for clean-up of liquid radioactive waste from tritium.
