| Autor: |
Beddingfield, D. H., LaFleur, A. M. |
| Předmět: |
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| Zdroj: |
Proceedings of the Institute of Nuclear Materials Management Annual Meeting; 2009, p1-10, 10p, 1 Diagram, 4 Charts, 6 Graphs |
| Abstrakt: |
Advanced fuel-cycle developments around the world currently under development are exploring the possibility of disposing of 241Am from spent fuel recycle processes by burning this material in fast reactors. For safeguards practitioners, this approach could potentially complicate both fresh- and spent-fuel safeguards measurements. The increased (α,n) production in oxide fuels from the 241Am increases the uncertainty in coincidence assay of Pu in MOX assemblies and will require additional information to make use of totals-based neutron assay of these assemblies. We have studied the behavior of 241Am-bearing MOX fuel in the fast reactor system and the effect on neutron and gamma-ray source-terms for safeguards measurements. In this paper, we will present the results of simulations of the behavior of 241Am in a fast breeder reactor system. [ABSTRACT FROM AUTHOR] |
| Databáze: |
Supplemental Index |
| Externí odkaz: |
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