GNEP ? Material Transportation, Storage & Disposal Analysis FY-07 Summary Report (open access)

GNEP ? Material Transportation, Storage & Disposal Analysis FY-07 Summary Report

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Date: October 4, 2007
Creator: Halsey, W.; Wigeland, R.; Nutt, M.; Bauer, T.; Smith, J. D.; Sorensen, K. et al.
System: The UNT Digital Library
Progress reports for Gen IV sodium fast reactor activities FY 2007. (open access)

Progress reports for Gen IV sodium fast reactor activities FY 2007.

An important goal of the US DOE Sodium Fast Reactor (SFR) program is to develop the technology necessary to increase safety margins in future fast reactor systems. Although no decision has been made yet about who will build the next demonstration fast reactor, it seems likely that the construction team will include a combination of international companies, and the safety design philosophy for the reactor will reflect a consensus of the participating countries. A significant amount of experience in the design and safety analysis of Sodium Fast Reactors (SFR) using oxide fuel has been developed in both Japan and France during last few decades. In the US, the traditional approach to reactor safety is based on the principle of defense-in-depth, which is usually expressed in physical terms as multiple barriers to release of radioactive material (e.g. cladding, reactor vessel, containment building), but it is understood that the 'barriers' may consist of active systems or even procedures. As implemented in a reactor design, defense-in-depth is classed in levels of safety. Level 1 includes measures to specify and build a reliable design with significant safety margins that will perform according to the intentions of the designers. Level 2 consists of additional design …
Date: October 4, 2007
Creator: Cahalan, J. E. & Tentner, A. M.
System: The UNT Digital Library