Advanced Gas Reactor (AGR)-5/6/7 is the last of a series of experiments conducted in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) in support of development and qualification of tri-structural isotropic (TRISO) low-enriched fuel for use in high-temperature gas-cooled reactors. The test train contains five separate capsules that are independently controlled and monitored. Each capsule contains multiple 12.51-mm-long compacts filled with low-enriched uranium carbide/oxide (UCO) TRISO fuel particles. The objectives of the AGR-5/6/7 experiment are to: 1. Irradiate reference-design fuel particles to support fuel qualification. 2. Establish operating margins for the fuel beyond normal operating conditions. 3. Provide irradiated-fuel performance data and irradiated-fuel samples for post-irradiation examination (PIE) and safety testing. vi Capsule 1 occurred from the fourth cycle (164B), and were rigorously mitigated to minimize fission product crosstalk between capsules. This gas line problem prevented fission product release measurement for Capsule 1 during the last three cycles and caused various fission gas leakage events into the other four capsules. By the end of the sixth cycle, 166A, a significant number of in-pile particle failures occurred in Capsule 1, causing a substantial increase in R/B values. In addition, numerous particle failures were observed in Capsule 3 and perhaps a small number of failures might have occurred in Capsule 2 during the last cycle, 168A. In contrast, no in-pile failures are likely in the top two capsules (4 and 5) based on absence of the typical spike in gross gamma counts and low failure estimates by the end of Cycle 168A using the AGR-3/4 R/B per exposed kernel model. Increased and unstable R/Bs in Capsules 4 and 5 can be contributed to fission gas leakage from Capsule 1.
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