Reactor material testing in the INL's Advanced Test Reactor (ATR) involves modeling and simulation of each experiment to accurately determine the irradiation temperature. This paper describes thermal analysis of capsule experiments using gas gap temperature control and provides data on recent material tests that validate the modeling results. Static capsule experiments and lead-out capsule experiments are discussed. The source of temperature variation in capsule experiments and ways to mitigate these variations are also explained. Two examples of instrumented lead-out capsule experiments, TMIST-1 and UCSB-2, are presented. A comparison of measured and calculated temperatures is used to validate the thermal models and to ascertain the accura...
This report documents an effort to quantify the uncertainty of the calculated temperature data for t...
AbstractAdvanced core materials and components for nuclear reactors of a new generation are tested i...
As part of a technology program to investigate the transient heating problems associated with high-s...
A new daily as-run thermal analysis was performed at the Idaho National Laboratory on the Advanced G...
As part of the Research and Development program for Next Generation High Temperature Reactors (HTR),...
Irradiation tests of materials at HANARO have usually been conducted using a standard capsule at tem...
This report documents an effort to analyze measured and simulated data obtained in the Advanced Gas ...
The Advanced Test Reactor (ATR) is located at the Idaho National Engineering Laboratory (INEL) near ...
The Advanced Test Reactor (ATR) has long been involved in testing gas reactor materials, and has dev...
The recent growth in interest for high temperature gas reactors has resulted in an increased need fo...
The Advanced Test Reactor (ATR) has long been involved in testing gas reactor materials, and has dev...
Temperature profiles in stored irradiated LAMPRE (Los Alamos Molten Plutonium Reactor Experiment) fu...
A controlled-temperature irradiation capsule was operated containing small fueled specimens at 160O ...
The Advanced Gas Reactor-5/6/7 (AGR-5/6/7) experiment is the fourth and final experiment in the AGR ...
The objective of this project was to provide an assessment of several methods by which the temperatu...
This report documents an effort to quantify the uncertainty of the calculated temperature data for t...
AbstractAdvanced core materials and components for nuclear reactors of a new generation are tested i...
As part of a technology program to investigate the transient heating problems associated with high-s...
A new daily as-run thermal analysis was performed at the Idaho National Laboratory on the Advanced G...
As part of the Research and Development program for Next Generation High Temperature Reactors (HTR),...
Irradiation tests of materials at HANARO have usually been conducted using a standard capsule at tem...
This report documents an effort to analyze measured and simulated data obtained in the Advanced Gas ...
The Advanced Test Reactor (ATR) is located at the Idaho National Engineering Laboratory (INEL) near ...
The Advanced Test Reactor (ATR) has long been involved in testing gas reactor materials, and has dev...
The recent growth in interest for high temperature gas reactors has resulted in an increased need fo...
The Advanced Test Reactor (ATR) has long been involved in testing gas reactor materials, and has dev...
Temperature profiles in stored irradiated LAMPRE (Los Alamos Molten Plutonium Reactor Experiment) fu...
A controlled-temperature irradiation capsule was operated containing small fueled specimens at 160O ...
The Advanced Gas Reactor-5/6/7 (AGR-5/6/7) experiment is the fourth and final experiment in the AGR ...
The objective of this project was to provide an assessment of several methods by which the temperatu...
This report documents an effort to quantify the uncertainty of the calculated temperature data for t...
AbstractAdvanced core materials and components for nuclear reactors of a new generation are tested i...
As part of a technology program to investigate the transient heating problems associated with high-s...