Advanced Safeguards Approaches for New Fast Reactors [electronic resource].
- Washington, D.C. : United States. Dept. of Energy. ; Oak Ridge, Tenn. : distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 2007
- Physical description
- Pacific Northwest National Laboratory (U.S.) Researcher
- United States. Dept. of Energy. Sponsor
- United States. Dept. of Energy. Office of Scientific and Technical Information. Distributor
- Dougan, A. Author
- Tolk, K. Author
- Bean, Robert Author
- Boyer, Brian Author
- Ehinger, Michael H. Author
- Durst, Philip C. Author
- Therios, Ike Author
- Wallace, Rick L. Author
- Kovacic, Don N. Author
- This third report in the series reviews possible safeguards approaches for new fast reactors in general, and the ABR in particular. Fast-neutron spectrum reactors have been used since the early 1960s on an experimental and developmental level, generally with fertile blanket fuels to “breed” nuclear fuel such as plutonium. Whether the reactor is designed to breed plutonium, or transmute and “burn” actinides depends mainly on the design of the reactor neutron reflector and the whether the blanket fuel is “fertile” or suitable for transmutation. However, the safeguards issues are very similar, since they pertain mainly to the receipt, shipment and storage of fresh and spent plutonium and actinide-bearing “TRU”-fuel. For these reasons, the design of existing fast reactors and details concerning how they have been safeguarded were studied in developing advanced safeguards approaches for the new fast reactors. In this regard, the design of the Experimental Breeder Reactor-II “EBR-II” at the Idaho National Laboratory (INL) was of interest, because it was designed as a collocated fast reactor with a pyrometallurgical reprocessing and fuel fabrication line – a design option being considered for the ABR. Similarly, the design of the Fast Flux Facility (FFTF) on the Hanford Site was studied, because it was a successful prototype fast reactor that ran for two decades to evaluate fuels and the design for commercial-scale fast reactors.
- Publication date
- Published through SciTech Connect.
- Dougan, A.; Tolk, K.; Bean, Robert; Boyer, Brian; Ehinger, Michael H.; Durst, Philip C.; Therios, Ike; Wallace, Rick L.; Kovacic, Don N.
- Funding Information