International Development of Safeguards and Security by Design of Nuclear Facilities and Processes

2010 
The application of safeguards and security by design (SBD) for new nuclear facilities has the potential to reduce security risks and proliferation hazards, whilst improving major plant design characteristics including operational efficiency and minimization of lifecycle cost. Overcoming delays to facility licensing may become a key feature. This is supportive of the expected significant future expansion of nuclear power generation consistent with low worldwide environmental impact. This paper reviews international work being conducted to develop a structured approach to ensure the timely, and cost effective integration of international safeguards and other nonproliferation barriers with national material control and accountability, physical protection, and safety objectives into the overall design process for a nuclear facility, from initial planning through design, construction and operation. The paper analyzes developments being made by various nuclear sectors and organizations with the intent to improve communication and aid overall progress. The paper also seeks to place SBD into the context of other integration approaches being applied to safeguards, safety and security, that more strongly affect later phases of the facility lifecycle. SBD applies to a wide range of facility types in the nuclear fuel cycle but in terms of applicability to design of new plants may have most immediate application to proposed new enrichment and recycling facilities. It examines studies of the SBD process for various regulatory environments and illustrates their differences. As with most design procedures, there is tension between complexity and readiness of adoption by designers, operator/owners and regulators since, as now judged by industry, SBD must show both facility improvements and cost savings for the operator. More fundamentally, increased weighting of safeguards and security aspects, including proliferation resistance of nuclear fuel cycle facilities, may possibly be accorded to selection amongst conceptual alternatives during the early stage of facility design. This may evolve as further facilities are constructed.
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