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Possibility of transmutation of {sup 90}Sr and {sup 137}Cs in a high-intensity photon flux accelerator device

Journal Article · · Transactions of the American Nuclear Society
OSTI ID:75899

Most of the effort and research on the transmutation of radioactive waste have been focused on the utilization of high neutron flux in advanced power reactors or n hybrid accelerator/subcritical systems. Some of the studies indicated that it might be not so economical to transmute {sup 90}Sr and {sup 137}Cs in these systems. Also these isotopes have a slight effect on the issues of geologic storage time because of their relatively short natural half-life ({approximately} 30 yr), but they might significantly affect the working protocol for a waste management period nearly comparable to the human life span. A novel approach to fission product transmutation is presented in this paper that is based on photon-neutron interaction. The high-energy photon flux accelerator proposed for transmutation of {sup 90}Sr and {sup 137}Cs consumes about an order of magnitude less power than those proposed by Los Alamos National Laboratory (LANL) for the transmutation of nuclear waste in an intense thermal neutron source. Furthermore, this system can be linked to one of the proposed systems and improve the overall transmutation performance of the fission product, especially of these two problematic isotopes.

OSTI ID:
75899
Report Number(s):
CONF-940602--
Journal Information:
Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 70; ISSN 0003-018X; ISSN TANSAO
Country of Publication:
United States
Language:
English

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