AGR 3/4 Irradiation Test Final As Run Report, Revision 1

Abstract

This document presents the as-run analysis of the AGR-3/4 irradiation experiment. AGR-3/4 is the combined third and fourth planned irradiations of the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. Funding for this program is provided by the U.S. Department of Energy as part of the Idaho National Laboratory (INL) Advanced Reactor Technologies Technology Development Office program. The objectives of the AGR-3/4 experiment are to: 1. Irradiate fuel containing uranium oxycarbide (UCO) designed-to-fail (DTF) fuel particles that will provide a known source of fission products for subsequent transport through compact matrix and structural graphite materials. 2. Assess the effects of sweep gas impurities, such as CO, H 2 O, and H 2 typically found in the primary coolant circuit of high temperature gas-cooled reactors, on fuel performance and subsequent fission product transport. 3. Provide irradiated fuel and material samples for post-irradiation examination (PIE) and safety testing. 4. Support the refinement of fuel performance and fission product transport models with on-line, PIE and safety test data.

Thermocouple Testing in Support of the AGR-5/6/7 Experiment

“…The AGR-3/4 experiment was in a larger irradiation position than AGR-1 and AGR-2. This allowed for an increase in the number of capsules (12) and TCs (27) (Collin 2016). All TCs in AGR-3/4 were standard design Type N and 1 mm in diameter.…”

Determination of Average Burnup in AGR-3/4 Compacts 1-4 and 7-4

“…a The compact identification (ID) denotes the compact's location in the irradiation test train: capsule-level(Collin 2016). b Each compact in the fabrication lot (LEU03-10T-OP2/LEU03-07DTF-OP1)-Z had a unique compact ID number from 001 to 175, and physical properties data are available and referenced by compact ID number(Hunn, Trammell, and Montgomery, 2011).…”