Advanced Safeguards Approaches for New TRU Fuel Fabrication Facilities

Durst, Philip C. ; Ehinger, Michael H. ; Boyer, Brian ; Therios, Ike ; Bean, Robert ; Dougan, A. ; Tolk, K.

Pacific Northwest National Laboratory (U.S.)

关键词: Irradiation;    Reprocessing;    Iaea;    Curium;    Neptunium;   

DOI  :  10.2172/940231
RP-ID  :  PNNL-17151
RP-ID  :  AC05-76RL01830
RP-ID  :  940231

美国|英语

来源: UNT Digital Library

【 摘 要 】

This second report in a series of three reviews possible safeguards approaches for the new transuranic (TRU) fuel fabrication processes to be deployed at AFCF – specifically, the ceramic TRU (MOX) fuel fabrication line and the metallic (pyroprocessing) line. The most common TRU fuel has been fuel composed of mixed plutonium and uranium dioxide, referred to as “MOX”. However, under the Advanced Fuel Cycle projects custom-made fuels with higher contents of neptunium, americium, and curium may also be produced to evaluate if these “minor actinides” can be effectively burned and transmuted through irradiation in the ABR. A third and final report in this series will evaluate and review the advanced safeguards approach options for the ABR. In reviewing and developing the advanced safeguards approach for the new TRU fuel fabrication processes envisioned for AFCF, the existing international (IAEA) safeguards approach at the Plutonium Fuel Production Facility (PFPF) and the conceptual approach planned for the new J-MOX facility in Japan have been considered as a starting point of reference. The pyro-metallurgical reprocessing and fuel fabrication process at EBR-II near Idaho Falls also provided insight for safeguarding the additional metallic pyroprocessing fuel fabrication line planned for AFCF.