Post-irradiation characterization of a high burnup mixed oxide fuel rod with minor actinides

نویسندگان

چکیده

The Advanced Fuels Campaign performed a series of irradiation tests minor actinide-bearing mixed oxide fuel (MA-MOX), the so-called AFC-2C&D experiments, to investigate transmutation long-lived transuranic actinide isotopes contained in spent nuclear via fast reactor technology at burnups exceeding 10 % fission initial metallic atoms. This manuscript reports test results derived from one five MA-MOX rodlets taken higher burnup AFC-2D irradiation. includes both non-destructive investigations, such as gamma and neutron spectrometry, destructive gas release, ceramography, chemical analysis. In addition, microstructure was investigated using advanced electron microscopy techniques including backscatter diffraction (EBSD) transmission (TEM). It observed with EBSD that pellet had subdivision grains TEM migration cladding material into 5 metal precipitates which could have been than desired oxygen/metal ratio. also showed an enrichment Cr clad interaction (FCCI) layer.

برای دانلود باید عضویت طلایی داشته باشید

برای دانلود متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

منابع مشابه

Modelling of Fission Gas Behaviour in High Burnup Nuclear Fuel

The safe and economic operation of nuclear power plants (NPPs) requires that the behaviour and performance of the fuel can be calculated reliably over its expected lifetime. This requires highly developed codes that treat the nuclear fuel in a general manner and which take into account the large number of in uences on fuel behaviour, e.g. thermal, mechanical, chemical, etc. Although many mature...

متن کامل

Nitride Fuel and Pyrochemical Process Developments for Transmutation of Minor Actinides in Jaeri

The Japan Atomic Energy Research Institute (JAERI) has proposed the concept of the transmutation of minor actinides (MA: Np, Am and Cm) with accelerator-driven systems (ADS), where MA nitride is adopted as a fuel material of a sub-critical core, because nitride fuel has the advantage of accommodating various MAs with a wide range of composition besides superior thermal and neutronic properties....

متن کامل

Mass Balance of the Pu and Minor Actinides Recycling Metal Fuel System

The mass flow of Plutonium and minor actinides is calculated for a future LWR-FBR fuel cycle model, in which a certain scale of power generation by LWRs is continued for a long period before the replacement by FBRs begins. The burnup of the LWR spent fuel is considered to be higher than the current standard. It is assumed that all the Plutonium and minor actinides recovered from LWRs are kept a...

متن کامل

ذخیره در منابع من


  با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید

ژورنال

عنوان ژورنال: Journal of Nuclear Materials

سال: 2022

ISSN: ['1873-4820', '0022-3115']

DOI: https://doi.org/10.1016/j.jnucmat.2022.153545