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Title: Fission Product Inventory and Burnup Evaluation of the AGR-2 Irradiation by Gamma Spectrometry

Abstract

Gamma spectrometry has been used to evaluate the burnup and fission product inventory of different components from the US Advanced Gas Reactor Fuel Development and Qualification Program's second TRISO-coated particle fuel irradiation test (AGR-2). TRISO fuel in this irradiation included both uranium carbide / uranium oxide (UCO) kernels and uranium oxide (UO 2) kernels. Four of the 6 capsules contained fuel from the US Advanced Gas Reactor program, and only those capsules will be discussed in this work. The inventories of gamma-emitting fission products from the fuel compacts, graphite compact holders, graphite spacers and test capsule shell were evaluated. These data were used to measure the fractional release of fission products such as Cs-137, Cs-134, Eu-154, Ce-144, and Ag-110m from the compacts. The fraction of Ag-110m retained in the compacts ranged from 1.8% to full retention. Additionally, the activities of the radioactive cesium isotopes (Cs-134 and Cs-137) have been used to evaluate the burnup of all US TRISO fuel compacts in the irradiation. The experimental burnup evaluations compare favorably with burnups predicted from physics simulations. Predicted burnups for UCO compacts range from 7.26 to 13.15 % fission per initial metal atom (FIMA) and 9.01 to 10.69 % FIMA for UOmore » 2 compacts. Measured burnup ranged from 7.3 to 13.1 % FIMA for UCO compacts and 8.5 to 10.6 % FIMA for UO 2 compacts. Results from gamma emission computed tomography performed on compacts and graphite holders that reveal the distribution of different fission products in a component will also be discussed. Gamma tomography of graphite holders was also used to locate the position of TRISO fuel particles suspected of having silicon carbide layer failures that lead to in-pile cesium release.« less

Authors:
 [1];  [1];  [1]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1369626
Report Number(s):
INL/EXT-16-39777
TRN: US1703375
DOE Contract Number:  
AC07-05ID14517
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY; URANIUM DIOXIDE; URANIUM; CESIUM 137; EMISSION COMPUTED TOMOGRAPHY; CESIUM 134; NUCLEAR FUELS; COMPARATIVE EVALUATIONS; FISSION PRODUCTS; SILVER 110; CERIUM 144; CERIUM 154; EUROPIUM 134; EUROPIUM 154; AGR-2; PIE; TRISO

Citation Formats

Harp, Jason Michael, Stempien, John Dennis, and Demkowicz, Paul Andrew. Fission Product Inventory and Burnup Evaluation of the AGR-2 Irradiation by Gamma Spectrometry. United States: N. p., 2016. Web. doi:10.2172/1369626.
Harp, Jason Michael, Stempien, John Dennis, & Demkowicz, Paul Andrew. Fission Product Inventory and Burnup Evaluation of the AGR-2 Irradiation by Gamma Spectrometry. United States. https://doi.org/10.2172/1369626
Harp, Jason Michael, Stempien, John Dennis, and Demkowicz, Paul Andrew. Thu . "Fission Product Inventory and Burnup Evaluation of the AGR-2 Irradiation by Gamma Spectrometry". United States. https://doi.org/10.2172/1369626. https://www.osti.gov/servlets/purl/1369626.
@article{osti_1369626,
title = {Fission Product Inventory and Burnup Evaluation of the AGR-2 Irradiation by Gamma Spectrometry},
author = {Harp, Jason Michael and Stempien, John Dennis and Demkowicz, Paul Andrew},
abstractNote = {Gamma spectrometry has been used to evaluate the burnup and fission product inventory of different components from the US Advanced Gas Reactor Fuel Development and Qualification Program's second TRISO-coated particle fuel irradiation test (AGR-2). TRISO fuel in this irradiation included both uranium carbide / uranium oxide (UCO) kernels and uranium oxide (UO2) kernels. Four of the 6 capsules contained fuel from the US Advanced Gas Reactor program, and only those capsules will be discussed in this work. The inventories of gamma-emitting fission products from the fuel compacts, graphite compact holders, graphite spacers and test capsule shell were evaluated. These data were used to measure the fractional release of fission products such as Cs-137, Cs-134, Eu-154, Ce-144, and Ag-110m from the compacts. The fraction of Ag-110m retained in the compacts ranged from 1.8% to full retention. Additionally, the activities of the radioactive cesium isotopes (Cs-134 and Cs-137) have been used to evaluate the burnup of all US TRISO fuel compacts in the irradiation. The experimental burnup evaluations compare favorably with burnups predicted from physics simulations. Predicted burnups for UCO compacts range from 7.26 to 13.15 % fission per initial metal atom (FIMA) and 9.01 to 10.69 % FIMA for UO2 compacts. Measured burnup ranged from 7.3 to 13.1 % FIMA for UCO compacts and 8.5 to 10.6 % FIMA for UO2 compacts. Results from gamma emission computed tomography performed on compacts and graphite holders that reveal the distribution of different fission products in a component will also be discussed. Gamma tomography of graphite holders was also used to locate the position of TRISO fuel particles suspected of having silicon carbide layer failures that lead to in-pile cesium release.},
doi = {10.2172/1369626},
url = {https://www.osti.gov/biblio/1369626}, journal = {},
number = ,
volume = ,
place = {United States},
year = {2016},
month = {9}
}