Analysis of Individual Compact Fission Product Inventory and Burnup for the AGR-1 TRISO Experiment using Gamma Spectrometry
Jason Harp, USDOE Office of Nuclear Energy (NE)
Abstract
Open-access reader
Jason Harp, USDOE Office of Nuclear Energy (NE)
Abstract
Open-access reader
The objective of this document is to describe a method for non-destructive burnup evaluation of the AGR-1 TRISO fuel compacts using gamma spectrometry. Initially, gamma-ray spectra taken from the AGR-1 experiment TRISO fuel compacts using the Precision Gamma Scanner (PGS) system were analyzed. The spectrometry analysis included a characterization of the PGS system and the measured fission product activities for the compacts. The measured activities were compared to detailed production/depletion fuel inventory simulations of the AGR-1 experiment. Two methods for relating burnup to measured fission product activity were developed from the results of the fuel inventory simulations and applied to the measured fission product activities. Burnup derived from the PGS measurements was compared to the predicted burnup from simulation.
OpenAlex reports 19 citations for this work. Citation counts describe recorded attention and do not establish research quality.
A contribution statement is not available in the OpenAlex record.
Method details are not available in the OpenAlex metadata.
Findings are not separately available in the OpenAlex metadata.
Limitations are not available in the OpenAlex metadata.
Application details are not available in the OpenAlex metadata.
The objective of this document is to describe a method for non-destructive burnup evaluation of the AGR-1 TRISO fuel compacts using gamma spectrometry. Initially, gamma-ray spectra taken from the AGR-1 experiment TRISO fuel compacts using the Precision Gamma Scanner (PGS) system were analyzed. The spectrometry analysis included a characterization of the PGS system and the measured fission product activities for the compacts. The measured activities were compared to detailed production/depletion fuel inventory simulations of the AGR-1 experiment. Two methods for relating burnup to measured fission product activity were developed from the results of the fuel inventory simulations and applied to the measured fission product activities. Burnup derived from the PGS measurements was compared to the predicted burnup from simulation.
Key concepts: Burnup, Nuclear fission product, Fission products, Nuclear engineering, Fission, Radiochemistry, Nuclear physics, Environmental science