U.S. Department of EnergyOffice of Scientific and Technical Information
As-Run Thermal Analysis for the AGC-4 Experiment Irradiated in the ATR
Abstract
The Advanced Graphite Capsule (AGC) irradiation experiment will provide irradiation creep rate data for the new graphite proposed for the Next Generation Nuclear Plant (NGNP) program. The fourth experiment in the series (AGC-4) was designed to irradiate various types of graphite specimens at a temperature of 900 ºC and targeted displacements per atom (DPA) of 6. This experiment has been irradiated in the east flux trap of the Advanced Test Reactor (ATR) during the cycles of 157D, 158A, 162A, 162B, 164A, 164B, 166A, and 166B. Temperatures were monitored using twelve thermocouples (TC) located at various elevations in the reactor core, and variable helium-argon gas mixtures were used for gas gap temperature control of the specimens. The purpose of this Engineering Calculation and Analysis Report (ECAR) is to calculate the specimen temperature after the model is calibrated by the measured TC data with the as-run heating rates of the components, DPA of the graphite, and the gas mixture compositions during the experiment. As-run specimen mean temperature and the tolerance will be obtained.
- Publication Date:
- Research Org.:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1781408
- Report Number(s):
- INL/MIS-21-62386-Rev000
- DOE Contract Number:
- DE-AC07-05ID14517
- Resource Type:
- Program Document
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Next Generation Nuclear Plant; irradiation creep rate data
Citation Formats
Brookman, Jason V. As-Run Thermal Analysis for the AGC-4 Experiment Irradiated in the ATR. United States: N. p., 2021.
Web.
Brookman, Jason V. As-Run Thermal Analysis for the AGC-4 Experiment Irradiated in the ATR. United States.
Brookman, Jason V. 2021.
"As-Run Thermal Analysis for the AGC-4 Experiment Irradiated in the ATR". United States. https://www.osti.gov/servlets/purl/1781408.
@article{osti_1781408,
title = {As-Run Thermal Analysis for the AGC-4 Experiment Irradiated in the ATR},
author = {Brookman, Jason V},
abstractNote = {The Advanced Graphite Capsule (AGC) irradiation experiment will provide irradiation creep rate data for the new graphite proposed for the Next Generation Nuclear Plant (NGNP) program. The fourth experiment in the series (AGC-4) was designed to irradiate various types of graphite specimens at a temperature of 900 ºC and targeted displacements per atom (DPA) of 6. This experiment has been irradiated in the east flux trap of the Advanced Test Reactor (ATR) during the cycles of 157D, 158A, 162A, 162B, 164A, 164B, 166A, and 166B. Temperatures were monitored using twelve thermocouples (TC) located at various elevations in the reactor core, and variable helium-argon gas mixtures were used for gas gap temperature control of the specimens. The purpose of this Engineering Calculation and Analysis Report (ECAR) is to calculate the specimen temperature after the model is calibrated by the measured TC data with the as-run heating rates of the components, DPA of the graphite, and the gas mixture compositions during the experiment. As-run specimen mean temperature and the tolerance will be obtained.},
doi = {},
url = {https://www.osti.gov/biblio/1781408},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2021},
month = {4}
}