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DOE OSTI2018

Urban Dispersion Virtual Workshop: Designing the Next Generation Urban Dispersion Field Programs

The overarching objective of this workshop is to start the process of planning and implementing the “Next Generation of Urban Dispersion Studies”. We have organized this program to bring people interested in this complex problem together. We have representation from different disciplines, different agencies, and different academic institutions. The workshop is organized around several questions: • What are the needs of the emergency response community and how do we design models and experiments to address them? • What model improvements do the user communities need? • How do we design tracer release and sampling to address questions temporal (e.g., diurnal and seasonal variation) and spatial (e.g., land/urban/water gradients) for the broadest applicability? • What are the next-generation measurements needed to improve the data sets? • How do we implement the next generation urban dispersion experiments? The Virtual workshop format is exciting. We view this as an experiment which, if successful, will bring a large group of people together from the community to design the next generation urban experiments. We have many agencies participating: DOE-BER, DHS, FEMA, NNSA, NARAC, DTRA, NYPD, and NIST. The registration list includes over 40 people including participants from well beyond the US including Spain and Canada.

54 ENVIRONMENTAL SCIENCES↗

DOE OSTI2018

Primary Assessment Technologies FY2017 Milestone Report: NDSE Development Using DPF

A new diagnostic technique for a neutron-based measurement of dynamic subcritical experiments is currently under development. The technique, referred to as a Neutron Diagnosed Subcritical Experiment (NDSE), requires that a short intense burst of neutrons be directed into a subcritical fissile object and a precision measurement of the emitted fission gamma rays be made as a function of time. Recent advances in a dense plasma neutron source and gamma ray detectors have been integrated together at the Nevada National Security Site to provide a NDSE technique development and testing capability. The first set of NDSE demonstration experiments have now been completed using static objects constructed with large quantities of highly enriched uranium. The acquired data reveal the expected sensitivity to changes in neutronic properties of fissile objects and illustrate that the diagnostic approach is viable. As expected for any new measurement technique, many areas for improvement have been identified during static object testing and continued maturation of the diagnostic is planned before implementation on a dynamic subcritical experiment.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

DOE OSTI2018

Strategy for Safety-Related Digital I&C Qualification

Digital I&C qualification continues to be a major impediment to addressing the reliability and obsolescence issues of the legacy analog I&C systems of the operating LWR fleet. In particular, the issue of digital common cause failure (CCF) has been difficult to address and has been the reason that some nuclear plant licensees have deferred upgrades of these critical plant systems and have rather opted to maintain them with considerable engineering and maintenance efforts. This is getting more and more difficult in the face of declining analog technology suppliers and dwindling supplies of spare parts and support for many critical components. To remain a viable energy source for the nation, the nuclear fleet must reduce its operating costs to a competitive level. Digital technology is the foremost means of implementing performance improvements and cost reductions for this purpose. This has been demonstrated over and over again in other industry sectors, as well as in conventional generation facilities. However, due to the special nature of nuclear energy, these digital I&C qualification barriers remain and must be resolved in order to modernize these plants and transform the business model to one that is competitive. The purpose of this report is to present an assessment of digital I&C qualification issues and address gaps in qualification methods and processes that would potentially benefit from Department of Energy (DOE)-sponsored research and development. Two new qualification methods are described that are recommended for further Department of Energy-sponsored research and development. They are 1) Testability – the exhaustive (100%) testing of certain digital devices addressing all combinations of inputs and internal states, and 2) Elimination of CCF triggers – ensuring that any latent digital defects are not concurrently triggered in redundant and back-up safety systems. In addition this report presents a strategy for full nuclear plant modernization based on four interrelated elements that together address the remaining barriers to prudent implementation. These four elements are 1) End-State Architecture, 2) Cost-Benefit Analysis, 3) Regulatory Approval, and 4) Implementation Sequence Plan.

42 ENGINEERING↗

DOE OSTI2019

Cumulative Impact Evaluation Technical Approach Document

This document presents the technical approach for developing a set of tools to perform a cumulative impact evaluation (CIE) on the effects of cleanup decisions regarding groundwater quality in the Hanford Site Central Plateau. Due to the complexity and large number of waste sites in noncontiguous source operable units (OUs), the computational tools used for the CIE must be capable of representing a range of site conditions and source terms in the vadose zone while also efficiently computing the impact that cleanup decisions have on the underlying aquifer. These tools will support remedial and closure decisions across the Central Plateau by providing cumulative information, but without replacing or displacing any part of those decision processes. The objective of this document is to describe the major components required for the CIE, the approach for developing these tools, and the plan for implementation. The Central Plateau has more than 1,300 waste sites, active and inactive burial grounds, and active and inactive waste processing facilities that are regulated under a combination of the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA); the Resource Conservation and Recovery Act of 1976 (RCRA); and other waste disposal regulatory frameworks. Figure 1-1 shows the source OUs on the Central Plateau and illustrates the geographical intermixing of sites within different source OUs. Groundwater OUs have several overlying source OUs, and actions taken within source OUs may affect groundwater across the entire Central Plateau. Waste site proximity between and within source OUs has resulted in contaminants commingling in the vadose and saturated zones in complex ways (Figure 1-2). Plume commingling requires cleanup decisions to be evaluated considering the surrounding waste sites and existing groundwater contamination, therefore demonstrating the need to evaluate cumulative impacts from the vadose zone to groundwater. Soil (vadose zone) and groundwater (saturated zone) contamination across the Central Plateau is undergoing investigation and remediation, and decisions need to be made regarding how to most efficiently disposition and remediate sites. Because contaminants intermingle among the OUs, decisions should be evaluated considering the context of the surrounding sites and facilities and not in isolation. Thus, the CIE of Central Plateau groundwater contamination should consider the integrated effects of numerous contaminant sources and prospective remedies. For this CIE, cumulative impacts of an action (e.g., groundwater remediation or placement of an evapotranspiration barrier over a waste site) will be viewed as the total effects on groundwater from that action, considering all other activities or likely future activities for source or groundwater OUs.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2017

China Green Low-Carbon City Index

54 ENVIRONMENTAL SCIENCES↗

DOE OSTI2020

Model MC&A for Pebble Bed Reactors (Technical Direction No. 5 Task 2.6 Letter Report)

In preparation for non-light water reactor (non-LWR) activities, US Nuclear Regulatory Commission (NRC) staff are advancing risk-informed and performance-based licensing approaches and addressing key policy issues. One non-LWR reactor concept is a pebble bed reactor (PBR). This reactor design uses spherical fuel elements (pebbles) that are continually added to and removed from the reactor core. The free movement of the fuel in this design presents new challenges for material control and accounting (MC&A) programs. Therefore, an assessment of MC&A program features and measures for a PBR was performed to help NRC staff develop associated MC&A regulations or regulatory guides. The current regulatory framework for non-LWR fuel cycles excludes support for licensing reviews for MC&A programs for PBRs. Licensing reviews of an MC&A program for PBRs can be facilitated by (1) a model MC&A program for a PBR based on identification and assessment of MC&A program features and recommended measures for a reference PBR and (2) a methodology for assessing MC&A performance that can help assess different MC&A program features and measures. This report supports the NRC’s non-LWR Vision and Strategy Near-Term Implementation Action Plans.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

DOE OSTI2021

US Climate Variability and Predictability Project. Final Report

The primary goal of the US Climate Variability and Predictability (CLIVAR) Project Office is to enable science community planning and implementation of research activities to advance the program mission to understand and predict climate variability and change on intraseasonal-to-centennial timescales, through observations and modeling, with emphasis on the role of the ocean and its interaction with other elements of the Earth system, and to serve the climate community and society through the coordination and facilitation of research on outstanding climate questions.

54 ENVIRONMENTAL SCIENCES↗

DOE OSTI2020

Validation of an Advanced High-Pressure PEM Electrolyzer and Composite Hydrogen Storage

One of the challenges associated with transitioning our nation’s transportation economy to any alternative fuel is bringing fuel production, storage, transportation, and end-customer delivery infrastructure online. There are challenges associated with planning and implementing hydrogen fueling stations at locations relevant to the parallel effort of bringing the related transportation vehicles into the market. There are additional challenges associated with the operation of hydrogen fueling stations and reducing operating costs through energy reduction. Through calculation and design efforts it was concluded that elevating the pressure of a PEM cell stack and further developing hydrogen processing equipment that support elevated pressures while maintaining similar characteristics to their current production counterparts will yield in energy savings and by extension cost reductions. In this report, the design of a 57-bar (827-psig) electrolysis system and electrolysis cell stack is described. Furthermore, the fabrication, component verification, and integrated testing are summarized. Prior to this development effort, Proton had demonstrated thousand of hours of durability on 30-bar (435-psig) differential pressure PEM electrolysis hardware. Proton has sold and installed many of these 30-bar devices at customer sites. Through this project, Proton has developed and tested 57-bar PEM electrolysis, thereby extending the proven capability of PEM electrolysis as a hydrogen generation and electrochemical compression device. A design and validation effort to arrange hydrogen processioning equipment for refueling OEM vehicles was also undertaken within this project. By arranging equipment within two 6-meter ISO shipping containers and further developing NFPA 2 Hydrogen Technologies Code to support containerized hydrogen equipment, efforts to site, install, and commission, and approve hydrogen fueling stations were reduced and now provide a groundwork for future installations.

08 HYDROGEN↗

DOE OSTI2021

INTERFUEL: FAST - Updates for FY 2021 Reporting

This presentation presents an overview of coming changes to how federal agencies with motor vehicles will submit required information about the motor vehicles, fueling centers, and electric vehicle supply equipment (EVSE) inventory through the Federal Automotive Statistical Tool (FAST). The presentation provides information on changes throughout the FAST system as well as changes planned for implementation later this fall. This presentation is intended for delivery via WebEx/GoToMeeting at the September 15, 2021 meeting of the DOE-sponsored INTERFUEL working group. FAST is a web-based information management tool developed by INL and funded by GSA's Office of Government-wide Policy and DOE's Federal Energy Management Program.

99 GENERAL AND MISCELLANEOUS↗

DOE OSTI2017

China Green Low-Carbon City Index: Report on the Performance of 100+ Cities (2010-2015)

The main purpose of the new China Green Low-Carbon City Index (CGLCI, or City Index ) is to evaluate the status of green and low-carbon development for a large number of Chinese cities. Chinese cities are formulating plans and implementing programs to address national initiatives, especially the national low-carbon pilot program for 36 cities and six provinces. However, there is not yet an established framework for measuring, reporting, or evaluating low-carbon progress across Chinese cities, despite the development of a number of Chinese and international city indicator systems. The new China City Index highlights energy use and carbon emissions of Chinese cities, along with environmental and socio-economic indicators. We selected metrics (indicators) that have data available in China’s statistical system, are commonly used internationally, and reflect Chinese policy goals. (See Table ES-1.) We then benchmarked and ranked Chinese cities in terms of their status and progress, identified potential areas for improvement, and identified top-runners. By “low-carbon” we mean reducing emissions of carbon dioxide (CO 2 ) and methane (CH 4 ), with a focus on energy-related CO 2 . The term “carbon” is used as short-hand for these GHGs throughout the report. By “green” we recognize multiple environmental parameters related to urbanization and climate change: air quality, water use, solid waste, transport networks, and urban green space. In early 2017, China expanded its low-carbon pilot cities program, adding 45 more cities.

54 ENVIRONMENTAL SCIENCES↗

DOE OSTI2022

Evaluation of the Impact of Additional Manganese from the Recycle Collection Tank (RCT) Glycolate Destruction Process on Glass Properties

The Defense Waste Processing Facility (DWPF) is planning to implement glycolic acid as a reductant within the waste processing flowsheet. An assessment of the glycolic acid flowsheet has revealed the potential for thermolytic production of hydrogen in the Concentration, Storage and Transfer Facilities (CSTF) from glycolate entrained in the DWPF recycle stream. To mitigate this potential scenario, a glycolate destruction process utilizing sodium permanganate (NaMnO 4 ) is being developed for use in the DWPF Recycle Collection Tank (RCT). The RCT is fed by the Slurry Mix Evaporator Condensate Tank (SMECT) and the Off-Gas Condensate Tank (OGCT). The SMECT could receive glycolate via a foamover from the Sludge Receipt and Adjustment Tank (SRAT) or the Slurry Mix Evaporator (SME), and the OGCT could receive glycolate via carryover of sludge particles in the purge from the melter during surge conditions. The use of NaMnO 4 additions in the RCT will result in additional manganese (Mn) in the waste stream and needs to be evaluated.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

DOE OSTI2022

MELCOR Accident Progression and Source Term Demonstration Calculations for a FHR

MELCOR is an integrated thermal hydraulics, accident progression, and source term code for reactor safety analysis that has been developed at Sandia National Laboratories for the United States Nuclear Regulatory Commission (NRC) since the early 1980s. Though MELCOR originated as a light water reactor (LWR) code, development and modernization efforts have expanded its application scope to include non-LWR reactor concepts. Current MELCOR development efforts include providing the NRC with the analytical capabilities to support regulatory readiness for licensing non-LWR technologies under Strategy 2 of the NRC's near- term Implementation Action Plans. Beginning with the Next Generation Nuclear Project (NGNP), MELCOR has undergone a range of enhancements to provide analytical capabilities for modeling the spectrum of advanced non-LWR concepts. This report describes the generic plant model developed to demonstrate MELCOR capabilities to perform fluoride-salt-cooled high-temperature reactor (FHR) safety evaluations. The generic plant model is based on publicly-available FHR design information. For plant aspects (e.g., reactor building leak rate and details of the cover-gas system) that are not described in the FHR references, the analysts made assumptions needed to construct a MELCOR full-plant model. The FHR model uses a TRi-structural ISOtropic (TRISO)-particle fuel pebble-bed reactor with a primary system rejecting heat to two coiled tube air heat ex changers. Three passive direct reactor auxiliary cooling systems provide heat removal to supplement or replace the emergency secondary system heat removal during accident conditions. Surrounding the reactor vessel is a low volume reactor cavity that insulates the reactor with fire bricks and thick concrete walls. A refractory reactor liner system provides water cooling to reduce the concrete wall temperatures. Example calculations are performed to show the plant response and MELCOR capabilities to characterize a range of accident conditions. The accidents selected for evaluation consider a range of degraded and failed modes of operation for key safety functions providing reactivity control, the primary system decay heat removal and also a piping leak of the line to the coolant drain tank.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

DOE OSTI2022

MELCOR Accident Progression and Source Term Demonstration Calculations for a Heat Pipe Reactor

MELCOR is an integrated thermal hydraulics, accident progression, and source term code for reactor safety analysis that has been developed at Sandia National Laboratories for the United States Nuclear Regulatory Commission (NRC) since the early 1980s. Though MELCOR originated as a light water reactor (LWR) code, development and modernization efforts have expanded its application scope to includ e non-LWR reactor concepts. Current MELCOR development efforts include providing the NRC with the analytical capabilities to support regulatory readiness for licensing non-LWR techno logies under Strategy 2 of the NRC?s near- term Implementation Action Plans. Beginning with the Next Generation Nuclear Project (NGNP), MELCOR has undergone a range of enha ncements to provide analytical capabilities for modeling the spectrum of advanced non-LWR concepts. This report describes the generic plant model developed to demonstrate MELCOR capabilities to perform heat pipe reactor (HPR) safety evaluations. The generic plant mode l is based on a publicly-available Los Alamos National Laboratory (LANL) Megapower design as modified in the Idaho National Laboratory (INL) Design A description. For plant aspects (e.g., reactor building size and leak rate) that are not described in the LANL and INL references , the analysts made assumptions needed to construct a MELCOR full-plant model. The HP R uses high assay, low-enrichment uranium (HALEU) fuel with steel cladding that uses heat pipes to transfer heat to a secondary Brayton air cycle. The core region is surrounded by a stainless-steel shroud, alumina reflector, core barrel and boron carbide neutron shield. The reactor is secured inside a below-grade cavity, with the operating floor located above the cavity. Example calculations are performed to show the plant response and MELCOR capabilities to characterize a range of accident conditions. The accidents selected for evaluation consider a range of degraded and failed modes of operation for key safety functions providing re activity control, the primary and secondary system heat removal, and the effectiveness of th e confinement natural circulation flow into the reactor cavity (i.e., a flow blockage).

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

DOE OSTI2022

MELCOR Accident Progression and Source Term Demonstration Calculations for a HTGR

MELCOR is an integrated thermal hydraulics, accident progression, and source term code for reactor safety analysis that has been developed at Sandia National Laboratories for the United States Nuclear Regulatory Commission (NRC) since the early 1980s. Though MELCOR originated as a light water reactor (LWR) code, development and modernization efforts over the past decades have expanded its application scope to include non-LWR reactor concepts. Current MELCOR development efforts include providing the NRC with the analytical capabilities to support regulatory readiness for licensing non-LWR technologies under Strategy 2 of the NRC's near-term Implementation Action Plans. Beginning with the Next Generation Nuclear Project (NGNP), MELCOR ha s undergone a range of enhancements to provide analytical capabilities for modeling the spectrum of advanced non-LWR concepts. This report describes the generic plant model developed to demonstrate MELCOR capabilities to perform high-temperature gas reactor (HTGR) safety evaluations. The generic plant model is based on publicly available PMBR-400 design information. For plant aspects (e.g., reactor building size and leak rate) that are not described in the PBMR-400 references, the analysts made assumptions needed to construct a MELCOR full-plant model. The HTGR model uses a TRi-structural ISOtropic (TRISO)-particle fuel pebble-bed reactor with a primary system rejecting heat to a recuperative heat exchange r. Surrounding the reactor vessel is a reactor cavity contained within a confinement room cooled by the Reactor Cavity Cooling System (RCCS). Example calculations are performed to show the plant response and MELCOR capabilities to characterize a range of accident conditions. The accidents selected for evaluation consider a range of degraded and failed modes of operation for key safety functions providing reactivity control, primary system heat removal and reactor vessel decay heat removal, and confinement cooling.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

DOE OSTI2022

LANL Tritium Supply and Demand Model

The LANL Tritium Supply and Demand Model provides the capability to investigate the adequacy of future tritium supply subject to stockpile demand for variousscenarios. The tool includes the ability to change stockpile demand factors and adjust tritium production plans, while accounting for Tritium decay. The model has been used numerous times to identify potential tritium shortfalls and advocate for changes to tritium production planning and implementation.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

DOE OSTI2023

Republic of Korea–United States Green Shipping Corridor Prefeasibility Study: Cargo Flows

This prefeasibility study, as a part of the decarbonization efforts through the Mission Innovation Zero Emission Shipping Mission, was conducted to provide a high-level assessment of the opportunities and challenges in planning and implementing green shipping corridors between major commercial seaports in the United States of America (USA) and the Republic of Korea (ROK). For each country, three major ports were included in the scope of this study: Seattle, Tacoma, and Everett (all in Washington State) for the USA and Busan, Ulsan, and Masan for the ROK. This prefeasibility study report focuses on describing operation characteristics of major vessel and cargo flows between the two countries. Vessel shipments directly affect energy use and demand. Therefore, it is critically important to understand which major vessel types and cargo types are operated or transported within the selected scope and to identify potential target segments for green shipping. Furthermore, this prefeasibility study also discusses limitations and additional assessments that need to be further analyzed in the next stage of the feasibility study. The summary findings and observations discussed in this report are not intended to be used to determine the final target corridors, but to guide later, deeper assessments of their potential impacts and challenges. In the following section, the data sources used in this study are discussed. Section 0 shows the overall vessel trades between the USA and ROK, considering all ports in the two countries. Then, a more detailed analysis by vessel type and cargo flow is presented in Sections 3–6 based on only the three-to-three ports between the two countries. Finally, Section 7 summarizes the findings with suggested target segmentations for the vessel types and discusses other limitations to be considered during the later feasibility stage.

42 ENGINEERING↗

DOE OSTI2023

Federal Automotive Statisical Tool: FAST Changes & Data Call Preparation (INTERFUEL - September 2023) [Slides]

This presentation presents an overview of and timeline for coming changes to how federal agencies with motor vehicles will submit required information about the motor vehicles, fueling centers, and electric vehicle supply equipment (EVSE) inventory through the Federal Automotive Statistical Tool (FAST). The presentation provides information on changes throughout the FAST system as well as changes planned for implementation in FY 2023 and later. This presentation is intended for delivery via WebEx/GoToMeeting at the September 13, 2023 meeting of the DOE-sponsored INTERFUEL working group. FAST is a web-based information management tool developed and maintained by Idaho National Laboratory and funded by GSA's Office of Government-wide Policy and DOE's Federal Energy Management Program.

33 ADVANCED PROPULSION SYSTEMS↗

DOE OSTI2022

INTERFUEL: FY22 Federal Fleet Reporting [Slides]

This presentation presents an overview of and timeline for coming changes to how federal agencies with motor vehicles will submit required information about the motor vehicles, fueling centers, and electric vehicle supply equipment (EVSE) inventory through the Federal Automotive Statistical Tool (FAST). The presentation provides information on changes throughout the FAST system as well as changes planned for implementation in FY 2023 and later. This presentation is intended for delivery via WebEx/GoToMeeting at the September 14, 2022 meeting of the DOE-sponsored INTERFUEL working group. FAST is a web-based information management tool developed and maintained by Idaho National Laboratory and funded by GSA's Office of Government-wide Policy and DOE's Federal Energy Management Program.

99 GENERAL AND MISCELLANEOUS↗