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Structural Health Monitoring of Nuclear Spent Fuel Storage Facilities

Interim storage of spent nuclear fuel from reactor sites has gained additional importance and urgency for resolving waste-management-related technical issues. To ensure that nuclear power remains clean energy, monitoring has been identified by DOE as a high priority cross-cutting need, necessary to determine and predict the degradation state of the systems, structures, and components (SSCs) important to safety (ITS). Therefore, nondestructive structural condition monitoring becomes a need to be installed on existing or to be integrated into future storage system to quantify the state of health or to guarantee the safe operation of nuclear power plants (NPPs) during their extended life span. In this project, the lead university and the collaborating national laboratory teamed to develop a nuclear structural health monitoring (n-SHM) system based on in-situ piezoelectric sensing technologies that can monitor structural degradation and aging for nuclear spent fuel DCSS and similar structures. We also aimed to identify and quantify possible influences of nuclear spent fuel environment (temperature and radiation) to the piezoelectric sensor system and come up with adequate solutions and guidelines therefore. We have therefore developed analytical model for piezoelectric based n-SHM methods, with considerations of temperature and irradiation influence on the model of sensing and algorithms in acoustic emission (AE), guided ultrasonic waves (GUW), and electromechanical impedance spectroscopy (EMIS). On the other side, experimentally the temperature and irradiation influence on the piezoelectric sensors and sensing capabilities were investigated. Both short-term and long-term irradiation investigation with our collaborating national laboratory were performed. Moreover, we developed multi-modal sensing, validated in laboratory setup, and conducted the testing on the We performed multi-modal sensing development, verification and validation tests on very complex structures including a medium-scale vacuum drying chamber and a small-scale mockup canister available for the desired testing. Our work developed the potential candidate for long term structural health monitoring of spent fuel canister through piezoelectric wafer sensors and provided the sensing methodologies based on AE and GUW methodologies. It overall provides an innovative system and methodology for enhancing the safe operation of nuclear power plant. All major accomplishments planned in the original proposal were successfully achieved.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Environmental Assessment for the Above Ground Storage Capability at the Waste Isolation Pilot Plant Draft

The Waste Isolation Pilot Plant (WIPP) is the nation’s only approved repository for the disposal of defense related/defense generated transuranic (TRU) and mixed hazardous TRU waste (henceforth called TRU waste). The mission of the WIPP Project is to realize the safe disposal of TRU waste from TRU waste generator sites in the Department of Energy waste complex. The WIPP Project was authorized by Title II, Section 213(a) of Public Law 96-164 (U. S. Congress 1979). Congress designated the WIPP facility “for the express purpose of providing a research and development facility to demonstrate the safe disposal of radioactive wastes resulting from the defense activities and programs of the United States exempted from regulation by the Nuclear Regulatory Commission (NRC).” The WIPP facility is operated by the U. S. Department of Energy (DOE). Transuranic waste that is disposed in the WIPP facility is defined by Section 2(18) the WIPP Land Withdrawal Act of 1992 (LWA) (U. S. Congress, 1992) as: “waste containing more than 100 nanocuries of alpha-emitting transuranic isotopes per gram of waste, with half-lives greater than 20 years, except for: (A) high-level radioactive waste; (B) waste that the Secretary has determined, with the concurrence of the Administrator, does not need the degree of isolation required by the disposal regulations; or (C) waste that the NRC has approved for disposal on a case-by-case basis in accordance with part 61 of title 10, Code of Federal Regulations (CFR).

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INL/EXT-17-41117-Rev000

The mission of the U.S. Department of Energy’s Office of Nuclear Energy (DOE-NE) is to advance nuclear power as a resource that is capable of meeting the nation’s energy, environmental, and national security needs by resolving technical, cost, safety, proliferation resistance, and security barriers through research, development, and demonstration. There has never been a more compelling time to develop sources of safe, clean, renewable, carbon-free base power for the United States. Over six decades of use, nuclear power has been proven to be a safe and reliable base alternative to fossil energy sources. The primary barriers to wider commercialization of nuclear power are the life-cycle costs of current plants, the long cycle associated with development of new nuclear technologies that may be more suitable for today’s energy markets, and the regulatory risk associated with this investment in new nuclear technology. While many innovative nuclear energy concepts exist that match current energy market needs, the lengthy and expensive research, development, and demonstration process and uncertain prospects for licensing discourages investment of private capital. The DOE-NE strategy both sustains the current reactor fleet and provides technology options for development of advanced nuclear energy systems. The strategy for moving innovative ideas to the marketplace centers on the Gateway for Accelerated Innovation in Nuclear (GAIN) Initiative. As the lead national laboratory for DOE-NE, Idaho National Laboratory provides much of the nuclear research, development, and demonstration capability needed to move nuclear innovation forward to deployment.

29 ENERGY PLANNING, POLICY, AND ECONOMY↗

Bench Scale Study of Coating Formulations for Abatement of Mercury Vapor and Recovery of Mercury Spills

A sealant formulation has been developed that effectively mitigates human exposure to elemental mercury vapor evolving from spilled mercury. The sealant may be dispensed using a fogging methodology (for industrial settings) or a common spray bottle (for home or school settings). In parallel, the potential for Hg recovery using strippable coatings was evaluated. Four liquid coatings were evaluated: one fogging fixative (FX2) developed at INL for the containment of surface and airborne contamination and three commercially available strippable decontamination gels (Carboset 441, Encor 449, and Stripcoat TLC Free). Bench scale mercury vapor abatement tests were conducted in an enclosure using FX2 with the addition of a mercury absorbent and a mercury reactant. Testing with FX2 showed the reactant contributed significantly to reducing the rate of mercury evaporation. The reactant had a minimal impact on the mercury evaporation rate for the strippable coatings. The potential of strippable coatings to remove/recover mercury was inferred from the adhesive and cohesive performance of sprayable dilutions of the coatings applied to porous and non-porous surfaces. Testing provided the following results: • Mercury vapor concentration was reduced by a factor of 40 using the reactant enhanced FX2 solution, as well as with dilutions of Carboset and Encor. Dilute Stripcoat was less effective at reducing Hg evaporation. • A 100× reduction in Hg evaporation rate was achieved using a coating of FX + the Hg reactant (a.k.a. FX Hg), compared to uncoated Hg. • A 2× reduction in the Hg vapor accumulation rate was achieved using FX Hg, compared to the strippable coatings. • Strippability and adhesion tests show that dilutions of Carboset and Stripcoat can be stripped from a variety of indoor surfaces. Dilute Encor was not strippable. Results suggest FX Hg and dilute Carboset will likely reduce Hg vapor concentrations, in an indoor setting, to a level at or below the Occupational Safety and Health Administration 8-hour human exposure limit (0.1 mg/m3). FX Hg dispensed via fogging would increase worker safety during remediation and demolition of industrial facilities with high levels of elemental mercury contamination. When applied via spray bottle, FX Hg may provide a safe and convenient method for the mitigation of Hg vapor in residential or commercial settings (e.g., offices, homes, schools). This approach would be most beneficial where recovery of the spilled Hg is impractical. A sprayed then stripped application of dilute Carboset may provide a safe and convenient method for recovery of small Hg spills in residential and commercial settings. Further testing is required to determine if liquid Hg sufficiently adheres to the strippable coating to be recovered in this way. If it can be dispensed as a fog, dilute Carboset could be employed to recover Hg contamination in industrial settings. Testing of the foggability of dilute Carboset is required to assess this potential.

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ESH001 Environment Safety and Health Policy

Sandia performs work safely, in a manner that ensures adequate protection for the Members of the Workforce, the public, and the environment; is accountable for the safe performance of work; exercises a degree of care commensurate with the work and associated hazards; and integrates environment, safety, and health management into work planning and execution.

99 GENERAL AND MISCELLANEOUS↗

Innovative Plutonium Waste Forms: Acceptability to Shipp to WIPP

The mission of the Waste Isolation Pilot Plant in New Mexico is the safe and permanent disposition of transuranic radioactive waste from atomic energy defense activities of the United States. The plant consists of an underground repository in a salt formation that is free of flowing water, easily mined, impermeable, and geologically stable. The salt rock naturally seals fractures and closes openings over time. The repository is now anticipated to receive a greater amount of plutonium materials than originally envisioned. An engineered waste form for safe and efficient transport and long-term disposal of plutonium materials is an urgent need. An optimal waste form could also reduce the disposition life cycle and its associated costs to the taxpayer.

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Oxyhydroxides on aluminum spent nuclear fuel: formation studies and removal practices to prevent radiolytic gas production

Aluminum-clad nuclear fuel has been at the forefront in research and commercial reactors. After being removed from the reactor, the spent nuclear fuel is placed in large-volume water basins (wet storage) that are constantly monitored for water quality to minimize corrosion/deterioration. The water provides both radiation shielding and cooling for the freshly removed fuel. It is highly desired to have a pathway for fuel to be transitioned to dry storage in sealed casks, so that spent nuclear fuel can be safely transported and dispositioned in a permanent repository, and basin capacity can be made available for temporary wet storage of fresher spent fuel. A challenge for safe, road-ready dry storage is the hydrated aluminum oxides (oxyhydroxides) that are prevalent on aluminum spent nuclear fuel that has been stored under water for years. If water is released from the oxyhydroxides during dry storage, it can create corrosion within the storage canister, and hydrogen can be generated through radiolysis of the oxyhydroxides, causing pressurization and flammability risks. The focus of this project is to develop knowledge of the oxyhydroxide growth and production of gases through radiolysis and to apply empirical models for predicting these phenomena. The expertise developed will be used to formulate conditions and parameters for oxyhydroxide removal/dehydration from fuel cladding through vacuum or forced-air gas drying, to prevent problems during permanent dry storage.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Seventy-Five Years of Nuclear Criticality Safety Documents - A Bibliography

A collection of nuclear criticality documents was begun in the 1970s at the University of California’s Lawrence Livermore Laboratory (now Lawrence Livermore National Laboratory). Documents in this bibliography are dated as early as 1940. The early documents described experimental work that was of vital importance to the safe use of fissile materials at nuclear reactors, the facilities for preparing or transporting nuclear fuel, or its eventual storage. The experiments were of direct value to support safe operations with fissile material, but they were also needed for validating early physics data and calculational methods and then for validating computational methods used in criticality safety evaluations. Bibliographic information from the past seventy-five years have been entered into a computerized bibliographic database. The database continues to expand. Publications were issued several decades ago based on the information collected at that time. Our new publication is based on a current “snapshot” of the present status of the database. Contributions of information or corrections to this bibliography will be appreciated.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

Planificacion de un Sector Energetico Resiliente: Como Asegurar Electricidad Confiable, Segura y Asequible (Spanish Translation)

This is the Spanish translation of 'Planning a Resilient Power Sector: Ensuring Reliable, Secure, Safe, and Affordable Electricity' (NREL/TP-7A40-71543). Decision makers around the globe are exploring strategies to ensure the reliable, secure, safe, and affordable supply of electricity to power economic growth and achieve development goals. Vulnerabilities of the power sector to natural hazards (e.g., acts of nature, severe weather, and climate variabilities), technological hazards (e.g., accidents and system or structure failures), and threats or human-caused incidents (e.g., intentional cyber-attacks or acts of terror) can impede the provision of the energy services necessary to achieve these goals. Although decision makers cannot prevent an act of nature such as an earthquake, they can anticipate, prepare for, and adapt to potential vulnerabilities through planning. The purpose of power sector resilience planning is to identify vulnerabilities and devise strategies to mitigate them. This document reviews some of the hazards that power sectors face and how decision makers can plan to increase resilience.

29 ENERGY PLANNING, POLICY, AND ECONOMY↗

Radiological Consequences of Beam Loss at Front End by FLUKA during Top-off Injection into the Storage Ring for PROJECT Beamlines

NSLS-II plans to run the top-off mode operation in the near future. Particle tracking simulations proved that an errant injected electron beam can be confined to the beam-line frontend inside the storage ring tunnel by use of appropriate apertures and interlocks. Photon shutter collimator 2 (C2) was selected as the safe point (i.e. electron beam can’t travel beyond the safe point). FLUKA simulations have been carried out with the current beamline front ends and ratchet wall configurations to independently verify the previous calculations performed [1].

36 MATERIALS SCIENCE↗

Control Room Modernization End-State Design Philosophy

The Control Room Modernization (CRM) research effort is a part of the Light-Water Reactor Sustainability (LWRS) Program, which is a research and development program sponsored by Department of Energy (DOE) and performed in close collaboration with industry research and development programs that provides the technical foundations for licensing and managing the long-term, safe, and economical operation of current nuclear power plants. One of the primary missions of the LWRS program is to help the U.S. nuclear industry adopt new technologies and engineering solutions that facilitate the continued safe operation of the plants and extension of the current operating licenses. This report describes the background and technical basis for an end-state vision design philosophy for and advanced hybrid control room.

99 GENERAL AND MISCELLANEOUS↗

Vacuum Sanitation Energy Efficiency Retrofits Project

The Alaska Native Tribal Health Consortium (ANTHC) is a non-profit Tribal health organization designed to meet the unique health needs of Alaska Native and American Indian people living in Alaska. In partnership with communities and health organizations across the state, ANTHC provides health services to over 175,000 Alaska Native and American Indian people. Part of ANTHC’s mission includes ensuring that Native Alaskan communities have access to clean and safe water and sewer services. ANTHC works with communities to provide safe drinking water and healthy wastewater services that directly supports the health of Alaska Native people. To ensure water and sewer facilities operate sustainably, ANTHC Alaska Rural Utility Collaborative (ARUC) and Tribal Utility Support (TUS) programs provide operations and maintenance services on rural sanitation facilities. A key component of many water and sanitation systems in rural Alaskan villages is the vacuum sewer system, which is typically installed in places where the topography is primarily flat, and the elevation differential is not enough for a gravity powered sewer system to function without freezing during the winter. The vacuum sewer system is also the most costly and energy intensive form of sewer system, due to many factors including: large horsepower vacuum pumps needed for operation, potential for frequent vacuum leaks which increase the pump’s run-times, manpower needed to maintain pipe grade throughout the system, and the amount of heat needed to be added to the above ground pipes to keep them from freezing. The Vacuum Sanitation Energy Efficiency Retrofits Project implemented strategies to reduce the operating costs for vacuum sewer systems located in the remote Alaskan communities of Alakanuk, Kotlik, and Noorvik. A variety of deep energy efficiency retrofits were installed to reduce the amount of diesel fuel and electricity required to operate these systems which use large amounts of energy to pump, heat, and collect sewage from the community.

20 FOSSIL-FUELED POWER PLANTS↗

Final Report For PDRD SR16009: Durable Water Splitting Using Thermochemical Cycles Of Nanostructured Metal Oxides

The Tritium Facility process for stripping tritium from the glovebox atmosphere currently relies on the use of hot magnesium beds (mag beds) to “crack” tritiated water, releasing hydrogen isotopes as a gas. This is a safe and effective process for recovering hydrogen isotopes from water for further processing. However, due to the thermodynamic properties of magnesium, mag beds are single use - once the magnesium metal is converted to magnesium oxide the bed must be replaced. Replacing mag beds is a labor-intensive and operationally complex task. In order to streamline operations and reduce costs, it is desirable to develop a reusable system that recovers hydrogen isotopes from water, while safely sequestering oxygen in a stable form. The following document reviews the results from the Plant Directed Research, Development, and Demonstration (PDRD) project “Durable Water Splitting using Thermochemical Cycles of Nanostructured Metal Oxides” (SR16009), which had the specific goal of developing a process for stripping tritium from the glovebox atmosphere that eliminates magnesium beds.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Materials and Fuels Complex Five-Year Mission Strategy FY19 - FY23

The mission of the U.S. Department of Energy’s Office of Nuclear Energy (DOE-NE) is to advance nuclear power as a resource that is capable of meeting the nation’s energy, environmental, and national security needs by resolving technical, cost, safety, proliferation resistance, and security barriers through research, development, and demonstration (RD&D). There has never been a more compelling time to develop sources of safe, clean, renewable, carbon-free base power for the United States. Over six decades of use, nuclear power has been proven to be a safe and reliable base alternative to fossil energy sources. The primary barriers to wider commercialization of nuclear power are the life-cycle costs of current plants, the long cycle associated with development of new nuclear technologies that may be more suitable for today’s energy markets, including the management and disposition of used nuclear fuel, and the regulatory risk associated with this investment in new nuclear technology. These barriers can be addressed, in good part, by development of new technology that is simpler and therefore simpler to license, and by establishing new technology development approaches that more quickly establish design and safety bases that provide risk-averse investors and regulators the confidence they need for new technology to enter the market. While many innovative nuclear energy concepts exist that match current energy market needs, the lengthy and expensive research, development, and demonstration process and uncertain prospects for licensing discourages investment of private capital.

99 GENERAL AND MISCELLANEOUS↗

Integrated Commercial Carbon Capture and Storage (CCS) Prefeasibility Study at Rock Springs Uplift, Wyoming (Final Report)

To establish the potential of safe, long-term commercial-scale carbon capture & storage (CCS) in southwestern Wyoming, the University of Wyoming formed a CCS coordination team (CCT) to complete a Phase I CarbonSAFE pre-feasibility study adjacent to the region’s largest coal-fired power plant, the Jim Bridger Plant (JBP). The study’s primary objective was to evaluate the potential of storing 50+ million metric tons of anthropogenic carbon dioxide (CO 2 ) in stacked reservoirs over a period of 25 years. In addition, this integrated study evaluated related aspects of carbon capture utilization & storage (CCUS) at the study site, including: (1) the CO 2 character of post-combustion flue gas from JBP and the technical capacity for retrofitting proven commercial-scale CO 2 capture technology relative to CO 2 source character and technological constraints; (2) utilization of the existing CO 2 pipeline network in the immediate vicinity of JBP for enhanced oil recovery (CO 2 -EOR) and utilizing that network as part of a regional hub for CO 2 storage from other anthropogenic sources; (3) assessment of the challenges and benefits of meeting all of CarbonSAFE programmatic Phase I goals relative to Wyoming’s carbon management regulatory framework; and (4) assessment of the community and environmental factors that may impact CCS at JBP. With respect to storage, we analyzed the potential of stacked Mesozoic reservoirs at the study site, focusing on the Entrada and Nugget sandstones. The reservoir response to injection simulations varied greatly between formations, though they both were capable of CO 2 storage. The Entrada Sandstone is relative thin (~40’) and heterogeneous; storage using one injection and production well was limited to 1.2 Mt over 25 years at the study site. The Nugget Sandstone is much thicker (> 400’) and generally homogeneous; storage using one injection and production well approached 15.0 Mt over 25 years; this scenario suggests that the storage potential in the Nugget Sandstone is close to the estimated P90 calculation of 9.6 Mt/mi 2 as models indicate a storage potential of 8.3 Mt/mi 2 at saturation. Both reservoirs’ storage capacity benefited greatly from coupling an injection well with an offset production well; total storage capacity increased and reservoir pressure stayed below critical thresholds. This indicates that implementing a pressure management strategy at the study site would optimize storage and decrease risk. Seals associated with the targeted reservoirs were shown to be capable of retaining the potential storage volumes, and the site benefits from multiple seal redundancies (i.e. > 7,000’ of seal formations). Furthermore, assessment of different reservoir variables (e.g., fluid composition, pressure, etc.) indicates all reservoirs at the study site are isolated. Storage assessments from Mesozoic reservoirs were coupled with simulations from the site’s Paleozoic reservoirs (the Weber Sandstone and Madison Limestone), which were the focus of previous study. The fully integrated stacked reservoir pre-feasibility studies suggest that the Nugget and Madison formations alone could safely store 50 million metric tons of CO 2 within the study site. Furthermore, both formations are true saline reservoirs near JBP, making them ideal target reservoirs for CO 2 sequestration. Analysis of Wyoming’s laws and regulations confirm that the State has a favorable policy environment for CCS/CCUS. The project’s economic models estimated that the following revenues collectively are sufficient to finance the project over its lifespan if CO 2 utilization is coupled with CCS via the following strategies: (1) sales of CO 2 for EOR (approximately $69 million/year); (2) use of CO 2 tax credits such as amended §45Q and §48A (approximately $484 million total); and (3) sales of low-carbon electricity and marketable carbon offset/credits into carbon-constrained markets (approximately $11-$17 million/year) to West Coast consumers. These revenue estimates are broadly consistent with other studies that concluded arbitrage in JBP retail electricity sales between California and Wyoming could help to support the cost of deploying CCS at JBP. The models also indicate that maintaining a successful business case for long-term CCS -- wherein associated capture, transportation and operational costs are fully addressed at JBP -- is reliant on numerous external factors that complicate predictions. This study suggests that this site meets the CarbonSAFE program’s requirements of being able to feasibly store 50+ million metric tons of CO 2 over 25 years within the site’s stacked reservoirs, especially if coupled with pressure management strategies. This study suggests that the Nugget Sandstone and the Madison Limestone are two of the best reservoirs in the State with respect to overall storage capacity. In addition, the site’s proximity to existing CO 2 transportation networks, CO 2 -EOR opportunities, ability to sell to markets that value low-carbon electricity, Wyoming’s existing carbon regulatory framework, and a public that is well-educated with respect to energy markets and issues collectively increase the potential for implementing commercial-scale CCS adjacent to the JBP. With respect to the available technical and non-technical site data, and the reservoir quality at the study site, we suggest that this site is capable of moving directly into Phase III of the CarbonSAFE program.

01 COAL, LIGNITE, AND PEAT↗

Los Alamos National Laboratory Nuclear Material Management and Storage Program: Storage Health Metrics

The Strategic Materials Sustainment Program (SMSP) supports activities needed to manage the National Nuclear Security Administration’s (NNSA) inventory of strategic materials. As part of the SMSP, the Nuclear Material Management and Storage (NMM&S) program at the Los Alamos National Laboratory (LANL) is responsible for: (1) safe and secure storage of the SMSP strategic materials and others, (2) analysis, forecasting, and management of accountable nuclear materials; and (3) disposition of nuclear material through the Office of Nuclear Materials Integration (ONMI). The nuclear material management (NMM) mission is to ensure efficient nuclear material management lifecycle activities at LANL. The storage program function includes the management of storage capabilities across the site, supply chain management of nuclear materials, storage requirements integration, and nuclear container management (i.e., procurement, compliance, and safety). This report identifies key performance indicators (KPI) and describes the criteria and metrics used to assess the health of the storage component of the NMM&S program. “Health” is the ability of a process, system, facility, or program to safely and reliably accomplish its required mission. A health assessment provides timely identification of significant risks to enable mission performance. Significant risks identified are most effectively mitigated, avoided, or eliminated by evaluating and coordinating with stakeholders to specifically target, document, and often proceduralize strategies directed towards risk reduction. An effective health assessment involves status measurements of specific metrics that are tied directly to representative KPIs for a program. This document will baseline the KPI, criteria, and specific metrics that will be used to measure the “health” of the LANL Storage Program (i.e., NMM is not included).

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Oxyhydroxides on Aluminum Spent Nuclear Fuel: Formation Studies and Removal Practices to Prevent Radiolytic Gas Production

Aluminum-clad Spent Nuclear Fuel (ASNF) forms hydrated oxides or (oxy)hydroxides on the cladding due to water exposure during irradiation and storage. This poses challenges to sealed (road-ready) dry storage due to risks of release of bound water and decomposition releasing hydrogen and or oxygens. To assess the risks, it is necessary to understand the (oxy)hydroxides’ growth/formation and morphology as the precursor state for drying and their gas generation from radiolysis. This will help determine safe (oxy)hydroxide loadings on dry-stored fuel as well as methods of removal. In this work, (oxy)hydroxides were grown on aluminum alloy substrates and the resulting layers studied for morphology and thickness; radiolysis studies were performed on powders to correlate morphology and particle size to gas generation, and drying studies were performed on powders and adherent oxide films. These experiments will be used to guide development of drying strategies for safe dry storage.

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Co-op at Sandia National Laboratories (July - December 2019, Final Report)

This co-op was performed at Sandia National Laboratories (SNL) within the Weapon Surety Engineering 11 Department (9435), which is a customer-focused organization that provides engineering and system analysis expertise to ensure a safe deterrent throughout the entire weapon lifecycle. Engineers in 9435 develop a deep knowledge in both component and system function to support rigorous evaluation and mitigation of potential failure modes. They operate across multiple engineering disciplines (mechanical, electrical, computer, materials and systems engineering) with opportunities to develop crossdisciplinary capability. The team supports a variety of stockpile systems and is part of the product teams during development, design and production, as well as advanced concept and exploratory efforts. 9435 engineers use their extensive component and system knowledge, as well as experimental data and modeling, to ensure products function as intended with assured safety. Members of the department learn the function of multiple components, how those components integrate within the system and apply surety principles and processes to ensure a safe, secure, reliable, and effective U.S. nuclear deterrent.

42 ENGINEERING↗