This report documents an effort to analyze measured and simulated data obtained in the Advanced Gas Reactor (AGR) fuel irradiation test program conducted in the INL's Advanced Test Reactor (ATR) to support the Next Generation Nuclear Plant (NGNP) R&D program. The work follows up on a previous study (Pham and Einerson, 2010), in which statistical analysis methods were applied for AGR-1 thermocouple data qualification. The present work exercises the idea that, while recognizing uncertainties inherent in physics and thermal simulations of the AGR-1 test, results of the numerical simulations can be used in combination with the statistical analysis methods to further improve qualification of measured data. Additionally, the combined analysis...
The Very High Temperature gas-cooled Reactor (VHTR), which is currently being developed, achieves si...
This document presents the current state of planning for the AGR-1 irradiation experiment, the first...
Installation of new monitoring equipment in Nuclear Power Plants (NPPs) is often difficult and expen...
As part of the Research and Development program for Next Generation High Temperature Reactors (HTR),...
This report documents an effort to quantify the uncertainty of the calculated temperature data for t...
This paper describes the development and application of statistical analysis techniques to support t...
This document presents the as-run analysis of the AGR-1 irradiation experiment. AGR-1 is the first o...
This report documents the data qualification status of AGR-2 fuel irradiation experimental data from...
A new daily as-run thermal analysis was performed at the Idaho National Laboratory on the Advanced G...
This report provides the data qualification status of AGR-2 fuel irradiation experimental data from ...
This report provides the data qualification status of Advanced Gas Reactor-2 (AGR-2) fuel irradiatio...
This report presents the data qualification status of fuel irradiation data from the first four reac...
The Advanced Gas Reactor-5/6/7 (AGR-5/6/7) experiment is the fourth and final experiment in the AGR ...
Reactor material testing in the INL's Advanced Test Reactor (ATR) involves modeling and simulation o...
Projects for the very-high-temperature reactor (VHTR) program provide data in support of Nuclear Reg...
The Very High Temperature gas-cooled Reactor (VHTR), which is currently being developed, achieves si...
This document presents the current state of planning for the AGR-1 irradiation experiment, the first...
Installation of new monitoring equipment in Nuclear Power Plants (NPPs) is often difficult and expen...
As part of the Research and Development program for Next Generation High Temperature Reactors (HTR),...
This report documents an effort to quantify the uncertainty of the calculated temperature data for t...
This paper describes the development and application of statistical analysis techniques to support t...
This document presents the as-run analysis of the AGR-1 irradiation experiment. AGR-1 is the first o...
This report documents the data qualification status of AGR-2 fuel irradiation experimental data from...
A new daily as-run thermal analysis was performed at the Idaho National Laboratory on the Advanced G...
This report provides the data qualification status of AGR-2 fuel irradiation experimental data from ...
This report provides the data qualification status of Advanced Gas Reactor-2 (AGR-2) fuel irradiatio...
This report presents the data qualification status of fuel irradiation data from the first four reac...
The Advanced Gas Reactor-5/6/7 (AGR-5/6/7) experiment is the fourth and final experiment in the AGR ...
Reactor material testing in the INL's Advanced Test Reactor (ATR) involves modeling and simulation o...
Projects for the very-high-temperature reactor (VHTR) program provide data in support of Nuclear Reg...
The Very High Temperature gas-cooled Reactor (VHTR), which is currently being developed, achieves si...
This document presents the current state of planning for the AGR-1 irradiation experiment, the first...
Installation of new monitoring equipment in Nuclear Power Plants (NPPs) is often difficult and expen...