Sentence examples for qualification of fuel from inspiring English sources

As part of the High Temperature Reactors (HTR) R&D program, a series of irradiation tests, designated as Advanced Gas-cooled Reactor (AGR), have been defined to support development and qualification of fuel design, fabrication process, and fuel performance under normal operation and accident conditions.

The approach is described as four phases, with emphasis on selecting a reference fuel concept, evaluating and improving the fuel to develop a fuel specification for a reference design, obtaining data to support a licensing safety case for the fuel, and final qualification of the fuel for a specific application.

The first step toward building of this facility is development and qualification of the fuel for the reactor.

The irradiation performance of U3Si dispersion fuel in an Al matrix, U3Si-Al, under the Hi-Flux Advanced Neutron Application Reactor (HANARO) design full-power condition of 30 MW was tested for full-power qualification of the fuel.

Some of these programs are focused on development and qualification of a fuel design that consists of a uranium molybdenum (U Mo) alloy dispersed in an aluminum matrix as one option for reactor conversion.

Some of these programs are focused on assisting with the development and qualification of a fuel design that consists of a uranium molybdenum (U Mo) alloy dispersed in an aluminum matrix as one option for reactor conversion.

Currently, the program is focused on assisting with the development and qualification of a fuel design that consists of a uranium molybdenum (U Mo) alloy dispersed in an aluminum matrix.

To support the drafting, development, implementation and monitoring of European energy and transport policy, the Institute for Energy and Transport of the European Commissions Joint Research Centree conducts pre-competitive research in the areas of experimental qualification of advanced fuels and materials as well as simulation and modelling of reactor safety and material performance.

AGR-2, the second irradiation of the US program for qualification of the NGNP fuel, is open to international participation within the scope of the Generation IV International Forum.

A series of advanced gas reactor (AGR) irradiation tests is being conducted in the advanced test reactor (ATR) at Idaho National Laboratory INLL) in support of development and qualification of tristructural isotropic (TRISO) fuel used in the High temperature gas-cooled reactor (HTGR).

One aspect of fuel development and qualification is to demonstrate an appropriate understanding of the extent of fission product release from the fuel under anticipated service environments.