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High-Level Considerations for Access and Access Controls by Design

Bland, Jesse J.; Evans, Alan S.; Goolsby, Tommy D.; Horowitz, Steven M.; Monthan, Chad W.; Osborn, Douglas M.; Rivers, Joe; Rodgers, Thomas W.; White, Jake; Williams, Adam D.

The design and construction of a nuclear power plant must include robust structures and a security boundary that is difficult to penetrate. For security considerations, the reactors would ideally be sited underground, beneath a massive solid block, which would be too thick to be penetrated by tools or explosives. Additionally, all communications and power transfer lines would also be located underground and would be fortified against any possible design basis threats. Limiting access with difficult-to-penetrate physical barriers is a key aspect for determining response and staffing requirements. Considerations considered in a graded approach to physical protection are described.

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An Enhanced Safeguards Approach for Accelerator Driven Systems utilized to Close the Fuel Cycle

Farley, David R.; Uribe, Eva U.; Horowitz, Steven M.; Solodov, Alexander A.

Further to our previous safeguards approach for Accelerator Driven Systems, which focused on estimates of fissile material production using relevant proton accelerator systems and corresponding safeguards needs for fuel storage, the subcritical reactor, and spent fuel storage material balances areas, this report is more expansive and considers utilization of ADS for either burning of transuranics or breeding of fissile materials. We find that the recycled fuels likely intended for ADS will be thermally and radioactively hot to such a degree that it is likely reprocessing and fuel fabrication will have to be co - located with the ADS reactor facility to avoid impractical hot fuel transportation issues. As such, we consider in detail the full ADS system to include material balance areas for spent fuel receiving, reprocessing, storage & cooling, fuel fabrication, subcritical reactor area, and waste storage & handling. Furthermore, aqueous - based separation methods like PUREX cannot tolerate the intense heat of the ADS fuels, so pyroprocessing will likely be required. With these considerations, we developed an Enhanced Safeguards Approach for ADS beyond the work done in our first report, and conclude that significant diagnostic development is needed , a nd provide safeguards recommendations. We have also included an appendix regarding some country programs, in particular the Chinese ADANES burner/breeder program a nd the Indian thorium - based breeder program.

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High-Level Considerations for Access and Access Controls by Design

Bland, Jesse J.; Evans, Alan S.; Goolsby, Tommy D.; Horowitz, Steven M.; Monthan, Chad W.; Osborn, Douglas M.; Rivers, Joe; Rodgers, Thomas W.; White, Jake; Williams, Adam D.

Nuclear power plants must be, by design and construction, robust structures and difficult to penetrate. Ideally, for security, the reactors would be sited underground, beneath a massive solid block, too thick to be penetrated by tools or explosives with all communications and power transfer lines also underground and fortified. Limiting access with difficult-to-penetrate physical barriers is going to be key for determining response and staffing requirements.

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High-Level Considerations for Access and Access Controls by Design

Bland, Jesse J.; Evans, Alan S.; Goolsby, Tommy D.; Horowitz, Steven M.; Monthan, Chad W.; Osborn, Douglas M.; Rivers, Joe; Rodgers, Thomas W.; White, Jake; Williams, Adam D.

Nuclear power plants must be, by design and construction, robust structures and difficult to penetrate. Limiting access with difficult-to-penetrate physical barriers is going to be key for staffing reduction. Ideally, for security, the reactors would be sited underground, beneath a massive solid block, too thick to be penetrated by tools or explosives with all communications and power transfer lines also underground and fortified. Having the minimal possible number of access points and methods to completely block access from these points if a threat is detected will greatly help us justify staffing reduction.

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Biometric Access Control System Industrialization

Koskelo, Markku; Kadner, Steven; Horowitz, Steven M.

The Biometric Access Control System Industrialization project was initiated as Project 2 under the umbrella Cooperative Research and Development Agreement (CRADA) No. SC 14/01816.00.00 between National Technology and Engineering Solutions of Sandia (NTESS) and AQUILA on July 16, 2019. The purpose of this project has been to evaluate alternatives to the more traditional biometric access control methods, such as fingerprints and retinal scanners.

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Effective Access Monitoring at Geological Repositories

Finch, Robert F.; Horowitz, Steven M.; Smartt, Heidi A.; Shoman, Nathan; Rechard, Robert P.; Haddal, Risa

Access points at a deep, mined geological repository (GR) for the disposal of spent nuclear fuel (SNF) and other nuclear wastes present potential diversion paths for nuclear material. Because C/S measures are not likely to be used underground, access to a GR will require unprecedented reliance on C/S measures to maintain continuity of knowledge (CoK) on SNF buried underground. We develop a model GR based on common features of GR designs from national programs in order to develop and optimize C/S measures for GR access points that maximize confidence that CoK is maintained on SNF underground. Critical access points identified in this study are surface entrances to (1) the GR ramp (2) the excavation shaft, (3) the main elevator shaft, and (4) the ventilation shaft. The first three are considered critical detection points (DPs), whereas the fourth is considered a non-critical DP. The reason for the distinction is due to the different design capabilities of shaft components: the first three (ramp, excavation shaft, main elevator) are all capable of being used to move material from the underground to the surface, whereas the ventilation shaft is not. Such capabilities are verified during periodic design information verification (DIV) inspections.

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System Studies for Global Nuclear Assurance & Security: 3S Risk Analysis for Small Modular Reactors (Volume I)—Technical Evaluation of Safety Safeguards & Security

Williams, Adam D.; Osborn, Douglas M.; Bland, Jesse J.; Cardoni, Jeffrey N.; Cohn, Brian C.; Faucett, Christopher F.; Gilbert, Luke J.; Haddal, Risa H.; Horowitz, Steven M.; Majedi, Mike M.; Snell, Mark K.

Coupling interests in small modular reactors (SMR) as efficient and effective method to meet increasing energy demands with a growing aversion to cost and schedule overruns traditionally associated with the current fleet of commercial nuclear power plants (NPP), SMRs are attractive because they offer a significant relative cost reduction to current-generation nuclear reactors—increasing their appeal around the globe. Sandia's Global Nuclear Assurance and Security (GNAS) research perspective reframes the discussion around the "complex risk" of SMRs to address interdependencies between safety, safeguards, and security. This systems study provides technically rigorous analysis of the safety, safeguards, and security risks of SMR technologies. The aim of this research is three-fold. The first aim is to provide analytical evidence to support safety, safeguards, and security claims related to SMRs (Study Report Volume I). Second, this study aims to introduce a systems-theoretic approach for exploring interdependencies between the technical evaluations (Study Report Volume II). The third aim is to demonstrate Sandia's capability for timely, rigorous, and technical analysis to support emerging complex GNAS mission objectives.

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Results 1–25 of 28
Results 1–25 of 28