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Title: Validation of the Physics Analysis used to Characterize the AGR-1 TRISO Fuel Irradiation Test

The results of a detailed physics depletion calculation used to characterize the AGR-1 TRISO-coated particle fuel test irradiated in the Advanced Test Reactor (ATR) at the Idaho National Laboratory are compared to measured data for the purpose of validation. The particle fuel was irradiated for 13 ATR power cycles over three calendar years. The physics analysis predicts compact burnups ranging from 11.30-19.56% FIMA and cumulative neutron fast fluence from 2.21?4.39E+25 n/m2 under simulated high-temperature gas-cooled reactor conditions in the ATR. The physics depletion calculation can provide a full characterization of all 72 irradiated TRISO-coated particle compacts during and post-irradiation, so validation of this physics calculation was a top priority. The validation of the physics analysis was done through comparisons with available measured experimental data which included: 1) high-resolution gamma scans for compact activity and burnup, 2) mass spectrometry for compact burnup, 3) flux wires for cumulative fast fluence, and 4) mass spectrometry for individual actinide and fission product concentrations. The measured data are generally in very good agreement with the calculated results, and therefore provide an adequate validation of the physics analysis and the results used to characterize the irradiated AGR-1 TRISO fuel.
Authors:
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Publication Date:
OSTI Identifier:
1183493
Report Number(s):
INL/CON--14-33982
TRN: US1500170
DOE Contract Number:
DE-AC07-05ID14517
Resource Type:
Conference
Resource Relation:
Conference: International Congress on Advances in Nuclear Power Plants (ICAPP 2015), Nice (France), 3-6 May 2015
Research Org:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE)
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; VALIDATION; MASS SPECTROSCOPY; IRRADIATION; COMPARATIVE EVALUATIONS; EXPERIMENTAL DATA; HTGR TYPE REACTORS; FISSION PRODUCTS; ACTINIDES; ATR REACTOR; BURNUP; NUCLEAR FUELS; COATED FUEL PARTICLES; SIMULATION; FUEL WIRES; COMPUTER CALCULATIONS advanced gas reactors; TRISO