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Title: AGR-1 Depletion Benchmark

Abstract

The AGR-1 TRISO particle irradiation test was the first Advanced Gas Reactor test irradiated in the Advanced Test Reactor (ATR) at the Idaho National Laboratory. The TRISO particle fuel was 350 μm diameter uranium oxy-carbide (UCO) kernels enriched to 19.75 wt% U-235. The particles were embedded in cylindrical graphite compacts, placed in test capsules, and irradiated over a period of three years or 13 ATR power cycles. The fuel compacts achieved burnups approaching 20% FIMA and accumulated fast fluence up to 4.25E+25 n/m 2 (E n>0.18 MeV). This report describes the AGR-1 test train, capsules, compacts, and TRISO particle fuel in sufficient detail for a physics analyst to model the AGR-1 experiment as part of a larger ATR neutron transport model and perform a depletion calculation. The intent of the data herein is to define a practical numerical TRISO particle depletion benchmark problem for the AGR 1 irradiation test.

Authors:
 [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:
1475404
Report Number(s):
INL/EXT-18-45840-Rev000
DOE Contract Number:  
AC07-05ID14517
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
42 ENGINEERING; AGR; TRISO; Advanced Test Reactor

Citation Formats

Sterbentz, James W., and Cogliati, Joshua J. AGR-1 Depletion Benchmark. United States: N. p., 2018. Web. doi:10.2172/1475404.
Sterbentz, James W., & Cogliati, Joshua J. AGR-1 Depletion Benchmark. United States. doi:10.2172/1475404.
Sterbentz, James W., and Cogliati, Joshua J. Sun . "AGR-1 Depletion Benchmark". United States. doi:10.2172/1475404. https://www.osti.gov/servlets/purl/1475404.
@article{osti_1475404,
title = {AGR-1 Depletion Benchmark},
author = {Sterbentz, James W. and Cogliati, Joshua J.},
abstractNote = {The AGR-1 TRISO particle irradiation test was the first Advanced Gas Reactor test irradiated in the Advanced Test Reactor (ATR) at the Idaho National Laboratory. The TRISO particle fuel was 350 μm diameter uranium oxy-carbide (UCO) kernels enriched to 19.75 wt% U-235. The particles were embedded in cylindrical graphite compacts, placed in test capsules, and irradiated over a period of three years or 13 ATR power cycles. The fuel compacts achieved burnups approaching 20% FIMA and accumulated fast fluence up to 4.25E+25 n/m2 (En>0.18 MeV). This report describes the AGR-1 test train, capsules, compacts, and TRISO particle fuel in sufficient detail for a physics analyst to model the AGR-1 experiment as part of a larger ATR neutron transport model and perform a depletion calculation. The intent of the data herein is to define a practical numerical TRISO particle depletion benchmark problem for the AGR 1 irradiation test.},
doi = {10.2172/1475404},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {7}
}

Technical Report:

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