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At least 397 records · Page 22

Technical & Programmatic Solutions for Direct Disposal of DPCs: Draft Outline and Staffing Plan

This is a work planning document that describes technical and programmatic goals for disposition of spent nuclear fuel (SNF) that is currently in dry storage in dual-purpose canisters (DPCs), or will be in the foreseeable future. It then describes how those goals can be promoted by a research and development (R&D) program. The needed R&D is compared to the ongoing work supported by the U.S. Department of Energy in FY18, and planned for FY19 and beyond. Some additional R&D activities are recommended, and plans are presented for technical integration activities that address the efficacy of the Direct Disposal of DPCs program (WBS 1.08.01.03.05), and integration with the overall Disposal Research program (WBS 1.08.01.03). The planned deliverable for this work package in FY19 (M2SF-1951\1010305051-Analysis of Solutions for DPC Disposal; 6/19/19) will be the product of this workplan. The deliverable will evaluate technical options for DPC direct disposal, taking into account the range ofpast and current DPC designs in the existing fleet. It will describe a set of goals for successful disposition of spent fuel in DPCs. It will analyze the scope and timing of needed R&D activities (R&D Plan), and discuss the uses of generic and site-specific analyses. Where appropriate, it will use alternative management cases to represent how DPC direct disposal could be incorporated in the overall geologic disposal program, given uncertainties in program direction and funding.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

PV-RPM V2.0 beta - SAM Implementation. DRAFT User Instructions

This user manual is intended to provide instructions to volunteer beta testers on how to use Sandia National Laboratories (SNL) PV Reliability Performance Model (PV-RPM) features in the National Renewable Energy Laboratory (NREL) System Advisor Model (SAM) version 2017.1.17 r4 (NREL, 2017). This new feature is provided in SAM to allow users with reliability data the ability to develop and run scenarios where PV performance and costs are impacted from components that can fail stochastically. This is intended to be an advanced user feature as it requires knowledge and data regarding different PV component failure modes. It also relies heavily on the SAM LK scripting language, which is not utilized by a majority of SAM users. NREL has published a SAM LK users guide (Dobos, 2017) and has multiple online help topics and videos to get users familiar with the scripting language and what it can do. This user instruction manual will provide some background on how data collected from a PV system can be used as inputs in the PV-RPM model, which will give data owners the ability to develop their own reliability and repair distributions outside of the example provided here.

14 SOLAR ENERGY↗

Using and Developing Novel Data Analytics for Digitalized Microstructures. Draft

The primary goal of this work is to develop and implement analytic methods for quantitative analysis of microstructure. These analytic methods are demonstrated on microstructures generated by the Sandia kinAic Monte Carlo code SPPARKS. This report documents progress to that end as well as incremental work towards larger aspirations of making process-structure-property connections for complex processes such as welding and additive manufacturing.

42 ENGINEERING↗

Analytic framework for the United States cyber deterrence strategy. Final draft, 2nd submission (20 May 2015]

If the United States (U.S.) government allows cyberattacks to continue on their current trajectory of increased frequency and effect, the bonds holding our society together will be jeopardized, potentially impacting the survival of our society as we know it. Actions must be taken not only to defend against, but also to deter future cyberattacks. To achieve a credible and actionable U.S. Cyber Deterrence Strategy, the following three lines of effort are recommended for implementation by the White House: 1. Add a sixth priority to the Obama Administration's current cyberspace priorities to state: "Advance our cyber response policies and capabilities to further protect the country's national interests by deterring attacks within cyberspace." 2. Adopt the proposed Cyber Deterrence Analytic Framework as a guide for policy makers to use when determining the appropriate response to a cyberattack. 3. Implement the proposed Presidential Policy Directive outlining the United States' deterrence policy for cyber. These recommendations for establishing a U.S. Cyber Deterrence Strategy address the following key findings: As the U.S. private sector owns and operates over 90% of all of the networks and infrastructure of cyberspace, an effective policy must be communicated clearly across the government, business enterprise, and most importantly, to the people; More so than any time in our nation's history, individuals, companies, and organizations depend on cyberspace for uses ranging from social interactions to sustaining democracy; Threats existing within the cyber domain have grown both in attack vector complexity and societal impact; and, The current Presidential Executive Orders and Policy Directives related to cyber deterrence do not include a strategy for deterring attacks. The concepts presented in this paper were derived from interviews with experts in subjects ranging from deterrence philosophy, nuclear weapons implementation, U.S. cyber operations, and U.S. cyber policy. In addition, theories on deterrence strategies are explored, ranging from the 1960s to present to develop a deterrence strategy unique to cyber. Lastly, recent examples of cyberattacks are examined to provide evidence for the need to establish consequences for those individuals or countries that continue to behave nefariously within cyberspace. To form a strong foundation for a U.S. Cyber Deterrence Strategy, the U.S. must establish and clearly articulate the consequences for nations or individuals if they choose to initiate a cyberattack on the U.S. or its national interests.

29 ENERGY PLANNING, POLICY, AND ECONOMY↗

Update to Waste Form Performance Constraints and OWL Status and Inventory Content. Draft

This report provides (1) an updated set of inputs (Sections 1 through 4) on various additional waste forms (WF) for the generic Defense Waste Repository (DWR) inventory represented in the generic disposal system analyses (GDSA); (2) summaries of evaluations initiated to refine particular characteristics of particular WF for future use (Section 5); and (3) status updates (Section 6) for the Online Waste Library (OWL) inventory content, data entry checking process, and external OWL BETA testing initiated in fiscal year 2017. As such, this report represents completion of both deliverables M3SF-17SNO10501022 (SFWD-SFWST-2017-000047 — this actual report) and M4SF-17SN010501012 (SFWD-SFWST-2017- 000112 — to be completed by reference to the first milestone report in the PICSNE system).

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Post-Fire Safe Shutdown Capability. An Inspector's Handbook. Draft Report

The Nuclear Regulatory Commission's (NRC) current fire protection regulatory framework was initiated in response to a cable fire that occurred at the Browns Ferry Nuclear Power Station in 1975. Following the issuance of several guidance documents, in 1981 the Commission codified deterministic requirements to provide reasonable assurance that fire would not jeopardize reactor safety (10 CFR 50.48 "Fire Protection" and Appendix R to 10 CFR 50). Since then, the results of plant operating experience, NRC inspection activities and cable fire testing programs have served to clarify the application of these requirements. In 2004, the NRC amended 10 CFR Part 50.48 to add a new subsection, 10 CFR 50.48(c), that endorses, with exceptions, the National Fire Protection Association's 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants — 2001 Edition," as a voluntary alternative for demonstrating compliance with Appendix R. To date, approximately half of all operating plants have transitioned to a risk-informed approach under 10 CFR 50.48(c). Regardless of the selected approach, each operating nuclear power plant should establish a comprehensive fire protection program that includes features needed to minimize the likelihood and consequence of firesl. To achieve this objective, fire protection programs integrate the NRC's long-held safety concept of defense-in-depth (DID) by providing multiple barriers against potentially unacceptable consequences of fire. To minimize the frequency and size of fires, the first lines of defense include controls for fire prevention, such as controlling combustibles and ignition sources and fire mitigation features, such as fire detection and suppression systems. In the unlikely event that a fire should start and continue to grow in spite of these features, appropriate fire protection features, such as fire-rated barriers are provided as necessary to ensure the accomplishment of essential shutdown functions. This handbook was specifically developed for NRC inspectors that may be assigned to perform elements of Inspection Procedure (IP) 71111.05T, "Fire Protection (Triennial)," including, (a) "Protection of Safe Shutdown Capabilities," (e) "Alternative Shutdown Capability," and (f) "Circuit Analyses." Thus, the document concentrates solely on the final element of defense-in-depth— ensuring reactor safety will not be compromised in the event of a serious fire. In addition to describing how the NRC's regulatory framework has evolved since the Browns Ferry Fire, the handbook illustrates the content and scope of various analyses typically referenced in a plant's fire protection licensing basis and includes techniques and insights for assessing the plant's conformance to those criteria.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

Draft Report: Results of Stainless Steel Canister Corrosion Studies and Environmental Sample Investigations

This progress report describes work being done at Sandia national Laboratories (SNL) to assess the localized corrosion performance of container/cask materials used in the interim storage of used nuclear fuel. The work involves both characterization of the potential physical and chemical environment on the surface of the storage canisters and how it might evolve through time, and testing to evaluate performance of the canister materials under anticipated storage conditions.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

MELCOR Computer Code Manuals Volume 3: MELCOR Assessment Problems [Draft]

MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light-water reactor nuclear power plants. MELCOR is being developed at Sandia National Laboratories (SNL) for the U.S. Nuclear Regulatory Commission (NRC) as a second-generation plant risk assessment tool and the successor to the Source Term Code package. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. These include thermal-hydraulic response in the reactor coolant system (RCS), reactor cavity, containment, and confinement buildings; core heatup, degradation, and relocation; core-concrete attack; hydrogen production, transport, and combustion; and fission product release and transport behavior. Current uses of MELCOR include estimation of severe accident source terms and their sensitivities and uncertainties in a variety of applications. This publication of the MELCOR computer code manuals corresponds to MELCOR 2.0, released to users in September 2008. Volume 1 contains a primer that describes MELCOR's phenomenological scope, organization (by package), and documentation. The remainder of Volume 1 contains the MELCOR User's Guides, which provide the input instructions and guidelines for each package. Volume 2 contains the MELCOR Reference Manuals, which describe the phenomenological models that have been implemented in each package. Volume 3, MELCOR Assessment Problems, presents a portfolio of test and sample problems consisting of both analyses of experiments and of full plant problems. These analyses will be repeated with future releases of MELCOR in order to provide a metric on code predictions as new versions are released.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

High Performance Computing - Power Application Programming Interface Specification. Version 1.1 [DRAFT]

Measuring and controlling the power and energy consumption of high performance computing systems by various components in the software stack is an active research area [13, 3, 5, 10, 4, 21, 19, 16, 7, 17, 20, 18, 11, 1, 6, 14, 12]. Implementations in lower level software layers are beginning to emerge in some production systems, which is very welcome. To be most effective, a portable interface to measurement and control features would significantly facilitate participation by all levels of the software stack. We present a proposal for a standard power Application Programming Interface (API) that endeavors to cover the entire software space, from generic hardware interfaces to the input from the computer facility manager.

97 MATHEMATICS AND COMPUTING↗