Research Group for High Temperature Science on Fuel Materials

Location F JAEA > Nuclear Science and Engineering Center > Fuels and Material Engineering Division > Research Group for High Temperature Science on Fuel Materials


Research Activities

High-level radioactive liquid waste (HLLW) produced in a reprocessing plant contains minor actinides (MA; Np, Am, Cm) besides numerous fission products. It is well known that most of MA nuclides are alpha-emitters with the long half-lives and/or large decay heat. From the viewpoint of mitigating the long-term toxicity of radioactive waste and the burden of final disposal of radioactive waste, an advanced fuel cycle with partitioning and transmutation (PT), in which MA are partitioned from HLLW and burnt in a transmutation system such as a fast reactor (FR) or accelerator driven system (ADS), has been investigated.

Our group has been carrying out the R&D on the preparation of transuranium (TRU) compounds such as the oxide, nitride, chloride and alloy, the measurement of thermal properties, the fuel fabrication technology, and the evaluation of irradiation behavior in order to support the development of an advanced fuel cycle with PT.

Furthermore, basic properties on the TRU compounds have been measured by use of Moesbauer spectroscopy, nuclear magnetic resonance (NMR), X-ray absorption fine structure (XAFS) and so on under collaboration with domestic partners.

Research activities related to MA-recycling

Nitride Fuel Property Database

From the point of view of reducing the radiotoxicity and volume of radioactive wastes, transmutation of long-lived radioactive nuclides such as minor actinides (MAs) to short-lived radioactive or stable ones using an Accelerator Driven System (ADS) have been developed. Understanding the behavior of nitride fuels containing MAs during the irradiation in ADS is one of the most important issues in designing and developing the fuels. A database of material properties for nitride nuclear fuels, therefore, has been developed, in which numerical data of fundamental properties, such as thermal expansion, thermal conductivity, are formulated using the data evaluated in JAEA and reported already. And the fuel behavior can be analyzed by introducing this database into a fuel performance code of@the nitride fuel developed in JAEA.

To the Nitride Fuel Property Database, please click here.

Copyright (C) Fuels and Materials Engineering. All rights reserved.