The purpose of this effort was to provide the basis for a model that effectively predicts nitride fuel behavior. Material property models developed for the uranium nitride fuel system have been used to approximate the general behavior of nitride fuels with specific property models for the transuranic nitride fuels utilized as they become available. The AFCI fuel development program now has the means for predicting the behavior of the transuranic nitride fuel compositions. The key data and models needed for input into this model include: Thermal conductivity with burnup Fuel expansion coefficient Fuel swelling with burnup Fission gas release with burnup. Although the fuel performance model is a fully functional FEA analysis tool, it is limit...
Uranium mononitride (UN) is an advanced material for the non-oxide nuclear fuel considered as a prom...
A fundamental step in understanding the effects of irradiation on metallic uranium and uranium dioxi...
Uranium mononitride (UN) is an attractive fuel for a range of reactors, including, with adequate pro...
Nitride fuels have always been considered a good candidate for GENIV reactors, as well as space reac...
Due to the character of the original source materials and the nature of batch digitization, quality ...
An understanding of the relationship between the processing, properties, and performance of any pote...
Nitride and carbide nuclear fuels receive renewed interest worldwide since the beginning of the Gene...
Preliminary results have been obtained on a research program confirming the attainment of reliable p...
This study assesses the neutronic, thermal-hydraulic, and fuel performance aspects of using nitride...
Developing new fuels and qualifying them for large-scale deployment in power reactors is a lengthy a...
Nuclear fuel undergoes various changes in its properties and composition as it is irradiated in a nu...
The US National Energy Policy of 2001 advocated the development of advanced fuel and fuel cycle tech...
The US Department of Energy (DOE) established the Spent Nuclear Fuel Project (SNF Project) to addres...
Knowledge on fuel enthalpy and its temperature derivative, the heat capacity, are important quantiti...
Nitrides and carbides are the object of renewed interest as candidate fuels or matrices for minor ac...
Uranium mononitride (UN) is an advanced material for the non-oxide nuclear fuel considered as a prom...
A fundamental step in understanding the effects of irradiation on metallic uranium and uranium dioxi...
Uranium mononitride (UN) is an attractive fuel for a range of reactors, including, with adequate pro...
Nitride fuels have always been considered a good candidate for GENIV reactors, as well as space reac...
Due to the character of the original source materials and the nature of batch digitization, quality ...
An understanding of the relationship between the processing, properties, and performance of any pote...
Nitride and carbide nuclear fuels receive renewed interest worldwide since the beginning of the Gene...
Preliminary results have been obtained on a research program confirming the attainment of reliable p...
This study assesses the neutronic, thermal-hydraulic, and fuel performance aspects of using nitride...
Developing new fuels and qualifying them for large-scale deployment in power reactors is a lengthy a...
Nuclear fuel undergoes various changes in its properties and composition as it is irradiated in a nu...
The US National Energy Policy of 2001 advocated the development of advanced fuel and fuel cycle tech...
The US Department of Energy (DOE) established the Spent Nuclear Fuel Project (SNF Project) to addres...
Knowledge on fuel enthalpy and its temperature derivative, the heat capacity, are important quantiti...
Nitrides and carbides are the object of renewed interest as candidate fuels or matrices for minor ac...
Uranium mononitride (UN) is an advanced material for the non-oxide nuclear fuel considered as a prom...
A fundamental step in understanding the effects of irradiation on metallic uranium and uranium dioxi...
Uranium mononitride (UN) is an attractive fuel for a range of reactors, including, with adequate pro...