The United States Department of Energy’s Next Generation Nuclear Plant (NGNP) Advanced Gas Reactor (AGR) Fuel Development and Qualification Program will be irradiating up to seven separate low enriched uranium (LEU) tri-isotopic (TRISO) particle fuel (in compact form) experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the United States Department of Energy’s lead laboratory for nuclear energy development. The ATR is one of the world’s premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. These irradiations and fuel development a...
The Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL) is one of the world’s premier...
This report presents the data qualification status of fuel irradiation data from the first four reac...
The Very High Temperature gas-cooled Reactor (VHTR), which is currently being developed, achieves si...
The United States Department of Energy’s Next Generation Nuclear Plant (NGNP) Advanced Gas Reactor (...
The United States Department of Energy’s Next Generation Nuclear Plant (NGNP) Advanced Gas Reactor (...
The United States Department of Energy’s Advanced Gas Reactor (AGR) Fuel Development and Qualificati...
The United States Department of Energy’s Advanced Gas Reactor (AGR) Fuel Development and Qualificati...
The United States Department of Energy’s Advanced Gas Reactor (AGR) Fuel Development and Qualificati...
The United States Department of Energy’s Next Generation Nuclear Plant (NGNP) Program will be irradi...
This document presents the current state of planning for the AGR-1 irradiation experiment, the first...
The United States Department of Energy’s Next Generation Nuclear Plant (NGNP) Program will be irradi...
The Advanced Gas Reactor -1 (AGR-1) experiment is the first experiment in a series of eight separate...
As part of the program to demonstrate TRISO-coated fuel for the Next Generation Nuclear Plant, a ser...
This document presents the as-run analysis of the AGR-1 irradiation experiment. AGR-1 is the first o...
The AGR-1 experiment being conducted by the US Department of Energy Advanced Gas Reactor Fuel Develo...
The Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL) is one of the world’s premier...
This report presents the data qualification status of fuel irradiation data from the first four reac...
The Very High Temperature gas-cooled Reactor (VHTR), which is currently being developed, achieves si...
The United States Department of Energy’s Next Generation Nuclear Plant (NGNP) Advanced Gas Reactor (...
The United States Department of Energy’s Next Generation Nuclear Plant (NGNP) Advanced Gas Reactor (...
The United States Department of Energy’s Advanced Gas Reactor (AGR) Fuel Development and Qualificati...
The United States Department of Energy’s Advanced Gas Reactor (AGR) Fuel Development and Qualificati...
The United States Department of Energy’s Advanced Gas Reactor (AGR) Fuel Development and Qualificati...
The United States Department of Energy’s Next Generation Nuclear Plant (NGNP) Program will be irradi...
This document presents the current state of planning for the AGR-1 irradiation experiment, the first...
The United States Department of Energy’s Next Generation Nuclear Plant (NGNP) Program will be irradi...
The Advanced Gas Reactor -1 (AGR-1) experiment is the first experiment in a series of eight separate...
As part of the program to demonstrate TRISO-coated fuel for the Next Generation Nuclear Plant, a ser...
This document presents the as-run analysis of the AGR-1 irradiation experiment. AGR-1 is the first o...
The AGR-1 experiment being conducted by the US Department of Energy Advanced Gas Reactor Fuel Develo...
The Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL) is one of the world’s premier...
This report presents the data qualification status of fuel irradiation data from the first four reac...
The Very High Temperature gas-cooled Reactor (VHTR), which is currently being developed, achieves si...