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Reductions without Regret: Defining the Needed Capabilities

This is the second of three papers (in addition to an introductory summary) aimed at providing a framework for evaluating future reductions or modifications of the U.S. nuclear force, first by considering previous instances in which nuclear-force capabilities were eliminated; second by looking forward into at least the foreseeable future at the features of global and regional deterrence (recognizing that new weapon systems currently projected will have expected lifetimes stretching beyond our ability to predict the future); and third by providing examples of past or possible undesirable outcomes in the shaping of the future nuclear force, as well as some closing thoughts for the future. This paper begins with a discussion of the current nuclear force and the plans and procurement programs for the modernization of that force. Current weapon systems and warheads were conceived and built decades ago, and procurement programs have begun for the modernization or replacement of major elements of the nuclear force: the heavy bomber, the air-launched cruise missile, the ICBMs, and the ballistic-missile submarines. In addition, the Nuclear Weapons Council has approved a new framework for nuclear-warhead life extension not fully fleshed out yet that aims to reduce the current number of nuclear explosives from seven to five, the so-called "3+2" vision. This vision includes three interoperable warheads for both ICBMs and SLBMs (thus eliminating one backup weapon) and two warheads for aircraft delivery (one gravity bomb and one cruise-missile, eliminating a second backup gravity bomb). This paper also includes a discussion of the current and near-term nuclear-deterrence mission, both global and regional, and offers some observations on future of the strategic deterrence mission and the challenges of regional and extended nuclear deterrence.

98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗

Fuel Fabrication Capability Research and Development Plan

The purpose of this document is to provide a comprehensive review of the mission of the Fuel Fabrication Capability (FFC) within the Global Threat Reduction Initiative (GTRI) Convert Program, along with research and development (R&D) needs that have been identified as necessary to ensuring mission success. The design and fabrication of successful nuclear fuels must be closely linked endeavors.

GTRI↗

Simulation information regarding Sandia National Laboratories trinity capability improvement metric.

Sandia National Laboratories, Los Alamos National Laboratory, and Lawrence Livermore National Laboratory each selected a representative simulation code to be used as a performance benchmark for the Trinity Capability Improvement Metric. Sandia selected SIERRA Low Mach Module: Nalu, which is a uid dynamics code that solves many variable-density, acoustically incompressible problems of interest spanning from laminar to turbulent ow regimes, since it is fairly representative of implicit codes that have been developed under ASC. The simulations for this metric were performed on the Cielo Cray XE6 platform during dedicated application time and the chosen case utilized 131,072 Cielo cores to perform a canonical turbulent open jet simulation within an approximately 9-billion-elementunstructured- hexahedral computational mesh. This report will document some of the results from these simulations as well as provide instructions to perform these simulations for comparison.

Agelastos, Anthony Michael↗

"Multiscale Capabilities for Exploring Transport Phenomena in Batteries": Ab Initio Calculations on Defective LiFePO 4

We have began the project “Multiscale Capability for Exploring Transport Phenomena in Battery”, which is sponsored by Laboratory Directed Research and Development Program at Lawrence Livermore National Laboratory in February 2012 as the subcontract was approved. We have been performing first-principles quantum-mechanical calculations to first establish the general modeling framework. It was found that it is essential to employ advanced Density Functional Theory (DFT) calculations with Hubbard U correction, in order to describe the battery material, in particular, LiFePO4 (Figure 1). The presence of localized d-electrons at Fe ion sites requires the better treatment of non-local correlation beyond that of standard DFT. As our aim was to first identify and investigate key transport/reaction mechanisms affecting the performance of Lithium-ion based batteries, we have began out work by characterizing the standard structures and how the defects influence the important electronic structure.

25 ENERGY STORAGE↗

Final report on NA22 Project: A Comprehensive Capability to Use Prompt Fission Signatures to Detect SNM

The objective of this project is to provide a general capability that will facilitate detection of high-sensitivity nuclear material for both active interrogation and passive systems. Currently these systems are able to use only a small fraction of the information carried by particles emitted during ssion. Our improvements in physics modeling and simulation tools would enable exhaustive use of prompt ssion signatures. In particular, this project will provide a computationally e cient event-by-event description of ssion that explicitly describes all of the correlations associated with the production and subsequent decay of fragments formed in ssion. We will use existing data to validate our model as far as possible, including trying to make use of data from current NA22 funded projects. Once complete, we will make our code, FREYA, publicly available either as a standalone code or as a module in Monte Carlo transport codes.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

Advancing Analytical Capabilities to Study Nuclear Materials and Its Implications for Innovative Nuclear Materials Research

We propose the acquisition of the latest precession electron nanodiffraction (PED) DigiSTAR system from Nanomegas to enable and improve our capabilities to gain simultaneous insight about material structure and chemistry at the nanoscale in materials of interest to DOE-NE. This acquisition is directed towards data collection at low length scales to support model validation and DOE-NE’s modeling and simulation efforts.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Laser Safety Gram 0035 Advanced Radiographic Capabilities

This revision covers the addition of a short pulse alignment laser to the ARC Diagnostic Table (ADT). The Advanced Radiographic Capabilities (ARC) is a diagnostic that can redirect up to four NIF beam lines (Q35T) through two compressor vessels, splitting each beam line into two beamlets, and generating up to eight distinct pulses with a pulse-width on the order of 10s of picoseconds (figure 1). The up to eight generated pulses will be staggered to backlighter targets in order to create an x-ray movie of the compression phase leading up to ignition and other purposes.

42 ENGINEERING↗

Fuel Fabrication Capability Research and Development Plan

The purpose of this document is to provide a comprehensive review of the mission of the Fuel Fabrication Capability (FFC) within the Global Threat Reduction Initiative Convert Program, along with research and development (R&D) needs that have been identified as necessary to ensuring mission success. The design and fabrication of successful nuclear fuels must be closely linked endeavors. Therefore, the overriding motivation behind the FFC R&D program described in this plan is to foster closer integration between fuel design and fabrication to reduce programmatic risk. These motivating factors are all interrelated, and progress addressing one will aid understanding of the others. The FFC R&D needs fall into two principal categories, 1) baseline process optimization, to refine the existing fabrication technologies, and 2) manufacturing process alternatives, to evaluate new fabrication technologies that could provide improvements in quality, repeatability, material utilization, or cost. The FFC R&D Plan examines efforts currently under way in regard to coupon, foil, plate, and fuel element manufacturing, and provides recommendations for a number of R&D topics that are of high priority but not currently funded (i.e., knowledge gaps). The plan ties all FFC R&D efforts into a unified vision that supports the overall Convert Program schedule in general, and the fabrication schedule leading up to the MP-1 and FSP-1 irradiation experiments specifically. The fabrication technology decision gates and down-selection logic and schedules are tied to the schedule for fabricating the MP-1 fuel plates, which will provide the necessary data to make a final fuel fabrication process down-selection. Because of the short turnaround between MP-1 and the follow-on FSP-1 and MP-2 experiments, the suite of specimen types that will be available for MP-1 will be the same as those available for FSP-1 and MP-2. Therefore, the only opportunity to explore parameter space and alternative processing is between now and 2016 when the candidate processes are down-selected in preparation for the MP-1, FSP-1, and MP-2 plate manufacturing campaigns. A number of key risks identified by the FFC are discussed in this plan, with recommended mitigating actions for those activities within FFC, and identification of risks that are impacted by activities in other areas of the Convert Program. The R&D Plan does not include discussion of FFC initiatives related to production-scale manufacturing of fuel (e.g., establishment of the Pilot Line Production Facility), rather, the goal of this plan is to document the R&D activities needed ultimately to enable high-quality and cost-effective production of the fuel by the commercial fuel fabricator. The intent is for this R&D Plan to be a living document that will be reviewed and updated on a regular basis (e.g., annually) to ensure that FFC R&D activities remain properly aligned to the needs of the Convert Program. This version of the R&D Plan represents the first annual review and revision.

Convert Program↗

After Action Report: Specific Manufacturing Capability 2014 Evaluated Drill October 29, 2014

On October 29, 2014, the Specific Manufacturing Capability (SMC) facility located at the Idaho National Laboratory (INL) conducted its annual evaluated emergency drill. As a result, this after action report is required by DOE O 151.1C, “Comprehensive Emergency Management System.” The SMC facility, in coordination with other onsite organizations, and the Department of Energy Idaho Operations Office (DOE ID) conducted an annual facility emergency drill to demonstrate the ability to implement the requirements of DOE O 151.1C, “Comprehensive Emergency Management System.” The INL contractor, Battelle Energy Alliance, LLC (BEA) in coordination with other onsite organizations, conducted operations and demonstrated proper response measures to mitigate an event and protect the health and safety of onsite personnel, the environment, and property. Report data was collected from multiple sources, including documentation generated during drill response, critiques conducted immediately after terminating the drill, and evaluation critiques.

99 GENERAL AND MISCELLANEOUS↗

Report on High-Contrast Advanced Radiographic Capability Review

The Advanced Radiographic Capability (ARC) project at the National Ignition Facility (NIF) is designed to generate picosecond duration, kilo-Joule laser pulses to produce xrays for backlighting NIF experiments. The baseline concept (Figure 1), utilizing a single NIF beam quad, diverts the beamline(s) using insertable pick-off mirrors to a compressor chamber in the target bay and focuses it to target chamber center. When fully implemented, ARC will use a quad of NIF beamlines to deliver eight Petawatt-class, high-intensity pulses in a split aperture configuration (2 short pulse apertures per NIF beamline). These short pulses will be adjustable in energy (up to 13.2 kJ in full implementation), delays (0-80 ns) and pulse durations (1-50 ps) and can be individually pointed to targets. ARC will enable dynamic, multi-frame x-ray imaging (radiography) on NIF for applications in laser driven fusion and other high-energy density science missions. The near-term missions in support of the SSP program are described below.

42 ENGINEERING↗

Fuel Fabrication Capability WBS 01.02.01.05 - HIP Bonding Experiments (Final Report)

The goals of this project were to demonstrate reliable, reproducible solid state bonding of aluminum 6061 alloy plates together to encapsulate DU-10 wt% Mo surrogate fuel foils. This was done as part of the CONVERT Fuel Fabrication Capability effort in Process Baseline Development . Bonding was done using Hot Isotatic Pressing (HIP) of evacuated stainless steel cans (a.k.a HIP cans) containing fuel plate components and strongbacks. Gross macroscopic measurements of HIP cans prior to HIP and after HIP were used as part of this demonstration, and were used to determine the accuracy of a finitie element model of the HIP bonding process. The quality of the bonding was measured by controlled miniature bulge testing for Al-Al, Al-Zr, and Zr-DU bonds. A special objective was to determine if the HIP process consistently produces good quality bonding and to determine the best characterization techniques for technology transfer.

36 MATERIALS SCIENCE↗

A Process and Environment Aware Sierra/SolidMechanics Cohesive Zone Modeling Capability for Polymer/Solid Interfaces

The performance and reliability of many mechanical and electrical components depend on the integrity of polymer-to-solid interfaces. Such interfaces are found in adhesively bonded joints, encapsulated or underfilled electronic modules, protective coatings, and laminates. The work described herein was aimed at improving Sandia’s finite element–based capability to predict interfacial crack growth by 1) using a high fidelity nonlinear viscoelastic material model for the adhesive in fracture simulations, and 2) developing and implementing a novel cohesive zone fracture model that generates a mode-mixity dependent toughness as a natural consequence of its formulation (i.e., generates the observed increase in interfacial toughness with increasing crack-tip interfacial shear). Furthermore, molecular dynamics simulations were used to study fundamental material/interfacial physics so as to develop a fuller understanding of the connection between molecular structure and failure. Also reported are test results that quantify how joint strength and interfacial toughness vary with temperature.

36 MATERIALS SCIENCE↗

SIGMA Release v1.2 - Capabilities, Enhancements and Fixes

In this report, we present details on SIGMA toolkit along with its component structure, capabilities, and feature additions in FY15, release cycles, and continuous integration process. These software processes along with updated documentation are imperative to successfully integrate and utilize in several applications including the SHARP coupled analysis toolkit for reactor core systems funded under the NEAMS DOE-NE program.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

Plutonium Oxide Process Capability Work Plan

Pacific Northwest National Laboratory (PNNL) has been tasked to develop a Pilot-scale Plutonium-oxide Processing Unit (P3U) providing a flexible capability to produce 200g (Pu basis) samples of plutonium oxide using different chemical processes for use in identifying and validating nuclear forensics signatures associated with plutonium production. Materials produced can also be used as exercise and reference materials.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Dynamic Analytical Capability to Better Understand and Anticipate Extremist Shifts Within Populations under Authoritarian Regimes.

The purpose of this work is to create a generalizable data- and theory-supported capability to better understand and anticipate (with quantifiable uncertainty): 1) how the dynamics of allegiance formations between various groups and society are impacted by active conflict and by third-party interventions and 2) how/why extremist allegiances co-evolve over time due to changing geopolitical, sociocultural, and military conditions.

Bernard, Michael Lewis↗

Postdoc capability awareness AOT

This is a summary of the LANL accelerator operations and technology division prepared for the postdoc programmatic capability awareness workshop in engineering and applied sciences.

43 PARTICLE ACCELERATORS↗

New simulation capability for gamma ray mirror experiments

This report provides a description of the simulation toolkit developed at Lawrence Livermore National Laboratory to support the design of nuclear safeguards experiments using grazing incidence multilayer mirrors in the energy band of uranium (U) and plutonium (Pu) emission lines. This effort was motivated by the data analysis of a scoping experiment at the Irradiated Fuels Examination Facility (IFEL) at Oak Ridge National Laboratory in FY13 and of a benchmark experiment at the Idaho National Laboratory (INL) in FY14 that highlighted the need for predictive tools built around a ray-tracing capability. This report presents the simulation toolkit and relevant results such as the simulated spectra for TMI, MOX, and ATM106 fuel rods based on spent fuel models provided by Los Alamos National Laboratory and for a virgin high 240 Pu-content fuel plate, as well as models of the IFEL and INL experiments implemented in the ray tracing tool. The beam position and height were validated against the INL ~60 keV americium data. Examples of alternate configurations of the optics or experimental set-up illustrate the future use of the simulation suite to guide the next IFEL experimental campaign.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗