DETERMINATION OF THE QUANTITY OF I-135 RELEASED FROM THE AGR-1 TEST FUELS AT THE END OF ATR OPERATING CYCLE 138B

J. K. Hartwell ; D. M. Scates ; J. B. Walter ; M. W. Drigert

关键词: S;    GAS FLOW;    IRRADIATION;    REACTOR SHUTDOWN;    SHUTDOWN;    TEST REACTORS fission product release;    gamma-ray spectroscopy;    TRISO fuel;   

DOI  :  10.2172/911968
RP-ID  :  INL/EXT-07-12455
PID  :  OSTI ID: 911968
Others  :  TRN: US0800247

学科分类：核能源与工程

美国|英语

来源: SciTech Connect

【 摘 要 】

The AGR-1 experiment is a multiple fueled-capsule irradiation experiment being conducted in the Advanced Test Reactor (ATR) in support of the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. The experiment began irradiation in the ATR with a cycle that reached full power on December 26, 2006 and ended with shutdown of the reactor for a brief outage on February 10, 2007 at 0900. The AGR-1 experiment will continue cyclical irradiation for about 2.5 years. In order to allow estimation of the amount of radioiodine released during the first cycle, purge gas flow to all capsules continued for about 4 days after reactor shutdown. The FPMS data acquired during part of that shutdown flow period has been analyzed to elucidate the level of 135I released during the operating cycle.