This report provides the data qualification status of Advanced Gas Reactor-2 (AGR-2) fuel irradiation experimental data from Advanced Test Reactor (ATR) Cycle 154B as recorded in the Nuclear Data Management and Analysis System (NDMAS). This is the last cycle of AGR-2 irradiation, as the test train was pulled from the ATR core during the outage portion of ATR Cycle 155A. The AGR-2 data streams addressed in this report include thermocouple (TC) temperatures, sweep gas data (flow rates including new Fission Product Monitoring (FPM) downstream flows from Fission Product Monitoring System (FPMS) detectors, pressure, and moisture content), and FPMS data (release rates and release-to-birth rate ratios [R/Bs]) for each of the six capsules in the AG...
This document presents the current state of planning for the AGR-1 irradiation experiment, the first...
The AGR-1 experiment was the first in a series of Advanced Gas Reactor (AGR) experiments designed to...
The Very High Temperature gas-cooled Reactor (VHTR), which is currently being developed, achieves si...
This report documents the data qualification status of AGR-2 fuel irradiation experimental data from...
This report provides the data qualification status of AGR-2 fuel irradiation experimental data from ...
This report presents the data qualification status of fuel irradiation data from the first four reac...
Projects for the very-high-temperature reactor (VHTR) program provide data in support of Nuclear Reg...
The Graphite Technology Development Program will run a series of six experiments to quantify the eff...
The AGR-1 experiment is a fueled multiple-capsule irradiation experiment that was irradiated in the ...
This document presents the as-run analysis of the AGR-1 irradiation experiment. AGR-1 is the first o...
D. A. Petti (Program Tech Lead) Date iii The AGR-1 experiment is a multiple capsule fuel irradiatio...
This report documents an effort to analyze measured and simulated data obtained in the Advanced Gas ...
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 (...
As part of the Research and Development program for Next Generation High Temperature Reactors (HTR),...
This document presents the current state of planning for the AGR-1 irradiation experiment, the first...
The AGR-1 experiment was the first in a series of Advanced Gas Reactor (AGR) experiments designed to...
The Very High Temperature gas-cooled Reactor (VHTR), which is currently being developed, achieves si...
This report documents the data qualification status of AGR-2 fuel irradiation experimental data from...
This report provides the data qualification status of AGR-2 fuel irradiation experimental data from ...
This report presents the data qualification status of fuel irradiation data from the first four reac...
Projects for the very-high-temperature reactor (VHTR) program provide data in support of Nuclear Reg...
The Graphite Technology Development Program will run a series of six experiments to quantify the eff...
The AGR-1 experiment is a fueled multiple-capsule irradiation experiment that was irradiated in the ...
This document presents the as-run analysis of the AGR-1 irradiation experiment. AGR-1 is the first o...
D. A. Petti (Program Tech Lead) Date iii The AGR-1 experiment is a multiple capsule fuel irradiatio...
This report documents an effort to analyze measured and simulated data obtained in the Advanced Gas ...
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 (...
As part of the Research and Development program for Next Generation High Temperature Reactors (HTR),...
This document presents the current state of planning for the AGR-1 irradiation experiment, the first...
The AGR-1 experiment was the first in a series of Advanced Gas Reactor (AGR) experiments designed to...
The Very High Temperature gas-cooled Reactor (VHTR), which is currently being developed, achieves si...