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DOE OSTI2017

Additions to the ICSBEP AND IRPHEP Handbooks Since NCSD 2013

Innumerable experiments have been performed worldwide to support criticality safety activities. Those experiments represent significant investments in cost, expertise, and infrastructure; as such, they represent valuable assets as the basis for recording, development, and validation of methods and nuclear data vital for modern and future criticality safety needs. Preservation and evaluation of these experimental data as benchmarks serves to provide for the best interest of the nuclear criticality safety community. High-quality integral benchmark experiments have always been a priority. There is ever growing interest in developing integral benchmark data to increasingly quantify and reduce calculational uncertainties to meet the demands of future criticality safety needs supporting next generation reactors and advanced fuel cycle concepts. The importance of drawing upon existing benchmark data is becoming more apparent be-cause of dwindling availability of critical facilities worldwide and the high cost of per-forming new experiments. Integral benchmark data from the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP Handbook) and the International Handbook of Reactor Physics Benchmark Experiments (IRPhEP Handbook) are widely utilized. Significant benchmark data have been added to those two handbooks since the last Nuclear Criticality Safety Division Topical Meeting in Wilmingt on, North Carolina (September-October 2013). This paper highlights those additions. The 2016 edition of the ICSBEP Handbook now includes data for 570 evaluations containing benchmark specifications for 4,913 critical, subcritical, or near-critical configurations, representing contributions from over 20 countries. There are a total of 7 criticality-alarm-placement/shielding evaluations containing a total of 45 benchmark configurations, and 8 fundamental physics benchmark evaluations containing a total of 215 measurements relevant to criticality safety applications. The IRPhEP Handbook now includes data from 151 experimental series (representing 50 reactor facilities) and also represents contributions from over 20 countries. Of the 151 benchmarks, five are draft contributions. Both the ICSBEP and IRPhEP are collaborative efforts that involve numerous scientists, engineers, and administrative support personnel worldwide. Continued contribution to these handbooks is expected to further provide the high-quality benchmark data necessary to compliment criticality safety activities going forward.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

DOE OSTI2018

Nuclear code case development of printed-circuit heat exchangers with thermal and mechanical performance testing

The U.S. Department of Energy has agreed to fund a three-year integrated research project to close technical gaps involved with compact heat exchangers to be used in nuclear applications. This paper introduces the goals of the project, the research institutions, and industrial partners working in collaboration to develop a draft Boiler and Pressure Vessel Code Case for this technology. Heat exchanger testing, as well as non-destructive and destructive evaluation, will be performed by researchers across the country to understand the performance of compact heat exchangers. Testing will be performed using coolants and conditions proposed for Gen IV Reactor designs. Preliminary observations of the mechanical failure mechanisms of the heat exchangers using destructive and non-destructive methods is presented. Unit-cell finite element models assembled to help predict the mechanical behavior of these high-temperature components are discussed as well. Performance testing methodology is laid out in this paper along with preliminary modeling results, an introduction to x-ray and neutron inspection techniques, and results from a recent pressurization test of a printed-circuit heat exchanger. The operational and quality assurance knowledge gained from these models and validation tests will be useful to developers of supercritical CO 2 systems, which commonly employ printed-circuit heat exchangers.

42 ENGINEERING↗

DOE OSTI2019

WBS 4.1.2.31 Bioproduct Transition System Dynamics

Bioproducts are chemicals derived from a biomass feedstock; they can be produced on their own or as co-products of a biorefinery that also produces biofuels. Bioproducts have historically been difficult to scale up and bring to market, despite a broad understanding developed within BETO of the various conversion processes that can be used to produce bioproducts. Expanding the bioproducts industry by bringing more bioproducts to market would have a variety of positive impacts. Growth in the bioproducts industry would support the biofuels industry by enabling biorefinery co-products that yield additional revenue streams, allowing biofuel selling prices to be reduced and expanding the biofuels market. A larger bioproducts industry also has the potential to reduce carbon and other emissions associated with the U.S. chemical sector and contribute to increased price stability in some areas of the chemical market by shifting portions of the chemical sector away from reliance on fossil feedstocks. The key barrier to realizing these positive impacts is a lack of knowledge around the factors that prevent or enable bioproducts to reach the commercial market. To date, there has been essentially no research done on how successful bioproducts (commercially produced bioproducts that have captured market share) become successful, why failed bioproducts fail, and what the similarities and differences are between successful and failed bioproducts. The current project addresses this knowledge gap with a decision support tool that can be used by investors, technology developers and government agencies to bring more bioproducts to market, thereby simultaneously growing the bioproducts and biofuels industries. Development of the decision support tool was based on research on the technology development process and success rates in analogous industries, data gathered during previous BETO-funded projects, and a series of interviews with subject-matter experts within BETO, the bioproducts industry, and the investment community. This information formed a knowledge base around how bioproducts are developed from applied research to commercial scale was assembled, which was used to build the Bioproduct Transition Dynamics (BTD) model, a system dynamics (SD) model that tracks bioproduct development projects from applied research through the 'valley of death' of piloting and demoing to commercial scale production. The end-of-project goal is to release the BTD, along with supporting documentation, as a transparent open-source model that will inform decisions around bioproduct development and investments and enable more bioproducts to reach the market. The BTD takes as inputs techno-economic data on specific bioproducts, behavioral parameters for developers and investors, expectations around government support, and exogenous market factors. Model outputs include bioproduct technological progress over time, a cash flow statement for the development project, and market share estimates. Following initial model development, a sensitivity analysis was performed on a subset of model inputs to determine, first, if the BTD could be used to answer analysis questions of interest to BETO, and second, which of the inputs considered were most influential on bioproduct success. Results indicate that the BTD can be used to identify scenarios that enable bioproduct development, and that 'soft' or semi-quantitative factors play a large role in determining if a bioproduct will reach the market. A workshop was also held for subject-matter experts and prospective BTD users in July 2018. The workshop covered BTD model logic, input data and assumptions as well as the sensitivity analysis results and a discussion of potential use cases. Workshop feedback was used to identify additional model development tasks and was incorporated into a draft technical report completed in September 2018. BTD model development, validation and application will continue through 2019.

09 BIOMASS FUELS↗

DOE OSTI2019

A REPORT: “HIGH-DENSITY U-MO/AL AND U3SI2/AL DISPERSION FUELS FOR HIGH-POWER RESEARCH REACTORS”

An introduction to a new report on high-density U-Mo/Al and U3Si2/Al dispersion fuels for high power research reactors that ANL is drafting is given in this paper. The main objective of this report is to produce a stand-alone data compilation that can be used by fuel designers, fuel performance analyzers, and fuel safety evaluators, as well as reactor operators. It is also intended to build a foundation for an eventual U-Mo/Al dispersion fuel qualification report that supports the licensing of this fuel for high-power research reactors. U-silicide dispersion fuel is also included in the report for potential applications beyond the ranges of the fuel licensed in NUREG-1313 (Safety Evaluation Report for U3Si2/Al). The contents and framework of the dispersion fuel report is described. A gap analysis provides a summary of the areas where sufficient data and information are not currently available.

Research reactor fuel, U-Si, U-Mo↗

DOE OSTI2019

Regulatory Design for Transport Security Regulations of Nuclear and Other Radioactive Material

A cornerstone within a nuclear security regime of a country is a legislative and regulatory framework that both regulates the individuals using radioactive and nuclear materials, but also regulates the regulators for their commitments under International Law. When drafting nuclear law and regulations, both technical and legal expertise is needed to ensure the regulation meets the technical requirements for security, but also is legally enforceable within a country’s jurisdiction. While the Primary Nuclear Law, or Enabling Act provides establishes the Competent Authority and responsibilities for nuclear security, regulatory development is where the proverbial, rubber meets the road for requirements. The regulations provide instruction for inspections, authorizations, and managed activities, such as use storage, and transport. Transport Security regulatory development for radioactive and nuclear material is complex because the regulation maybe multi-jurisdictional, multi-modal, and involve multiple stakeholders. Development of transport security regulations requires coordination with other ministerial stakeholders, transport operators, and alignment to international treaties and conventions outside the nuclear domain. This paper provides a brief discussion of the challenges associated with regulatory development for transport security regulations for nuclear and other radioactive materials in transport. The paper will briefly identify key stakeholders, international law involved, and current efforts by the International Atomic Energy Agency (IAEA) in supporting Member States in regulatory development. While active in that regulations are necessary for a robust nuclear security regime, regulatory development is more a slow-burn than an active activity in nuclear security.

Fialkoff, Marc↗

DOE OSTI2019

Perspectives on Regulatory Design and Development for Transport Security of Nuclear and other Radioactive Materials

The responsibility for nuclear security rests entirely with the State but the International Atomic Energy Agency (IAEA) recognizes that a cornerstone in the development of a nuclear security regime is the development of regulations that address security of nuclear material and other radioactive material in transport. While the IAEA provides recommendations and guidance for security of materials in transport through Nuclear Security Series (NSS) documents, the challenge of integrating those recommendations into a Member State’s national legal framework is significant. Specifically, the development of transport security regulations requires coordination between both legal and technical experts within the country’s competent authority and multiple governmental agencies, as well as input from transport operators and other stakeholders. In addition to these interactions, the regulations must reflect the legal traditions of the Member State to fit within its overall national legal framework. Recognizing the challenge, the IAEA has requested input from international legal and technical experts to develop a methodology for drafting regulations on transport security of nuclear material and other radioactive material. This paper discusses the progress made so far in developing the methodology and provides a perspective on the need for transport security regulations and the challenges associated with their development. Ultimately, the goal of this paper is to introduce the IAEA-proposed methodology and to facilitate the discussion of this methodology with Member States that need support in developing their transport security regulations.

Ladsous, David↗

DOE OSTI2019

IAEA Guidance on Managing the Interface between Safety and Security for Normal Commercial Shipments of Radioactive Material

Regulations governing the safe transport of radioactive material have been developed and maintained at the international and national levels for more than six decades. Following the events of 9/11, a similar effort was initiated for security during the transport of radioactive material; however, safety and security provisions have generally been developed independent of each other. The responsibility for nuclear security within a State rests entirely with the State but as part of an international effort to address the provisions that complement or conflict with each other in the interface between safety and security during transport, the International Atomic Energy Agency (IAEA) convened a series of consultancy meetings beginning in October 2016, to (a) identify the needs and develop a plan to address those needs for the transport of low-activity radioactive material (defined for the purposes of this effort as “Normal Commercial Shipments”) with respect to the interface between transport safety and transport security, (b) develop guidance on the interface between transport safety and transport security, and (c) development of a model workshop that will inform IAEA Member States of the interface between transport safety and security. Specifically, the materials addressed in the IAEA Technical Report Series, TRS No. 1001 (in preparation), are those that are limited to low activity radioactive material (including nuclear materials) with activities below 3000 A2 – as defined in the IAEA transport safety regulations – or activities below 10 D – as defined in the Code of Conduct on the Safety and Security of Radioactive Sources – depending on the radionuclide(s) involved. Emphasis was placed in the Technical Report on these materials since, worldwide, little effort has focused on security for their transport and such guidance could prove beneficial to regulators and operators in many developing countries. An IAEA Technical Report has been drafted and is currently undergoing final steps for publication. The Technical Report will address the issues identified during the consultancy meetings, with a focus on the needs and methods for clarifying safety–security interfaces. This paper will introduce the structure and contents of the Technical Report and provide an update on its progress toward publication. A separate PATRAM 2019 paper will outline the workshop materials developed to date.

Ladsous, David↗

DOE OSTI2020

Multiphase Reacting Flow Simulations and Optimization of Commercial-Scale Aerobic Bioreactors

Aerobic bioreactors are widely used in the synthesis of value-added products in pharmaceutical and biotechnology industries, wherein microbial bioreactions aid in the conversion of sugars to macromolecules. These reactors are also being actively investigated as a cost-effective pathway for the production of low-value commodities such as biofuels and animal feed. Reactor scale-up is one of the important challenges when designing these systems. Gas and liquid phase transport, mass-transfer, and mixing physics at large length scales can significantly affect microbial conversion rates, particularly when the microbial reaction requires a narrow set of conditions. These phenomena are difficult to study in small-scale bench-top reactors that are typically well-mixed. Predictive computational fluid dynamics (CFD) based simulations can therefore aid in the design and optimization of these reactors. This work presents multiphase Euler-Euler CFD simulations of commercial-scale (~ 500 m3) aerobic bioreactors. Our mathematical model treats the gas and liquid as interpenetrating phases. This approach reduces the computational complexity of tracking individual gas bubbles that are several orders of magnitude smaller than reactor dimensions. We solve the Reynolds averaged Navier-Stokes (RANS) multiphase equations that account for phase and chemical species transport, interphase mass and momentum transfer and uses a phenomenological model for oxygen uptake by microbes. We use a customized solver derived from open-source CFD toolbox, OpenFOAM, to perform these simulations, which has been validated against small-scale reactors in our previous work. This work examines the performance of three different reactor designs, viz. bubble column reactor, airlift reactor with an internal draft tube, and a stirred-tank reactor with Rushton impellers. Reactor oxygen mass-transfer coefficient, gas hold-up, and oxygen distribution are critically analyzed among reactors, and sensitivity studies pertaining to gas flow rates and reactor geometry will be presented.

09 BIOMASS FUELS↗

DOE OSTI2020

Elevated-temperature cyclic properties of advanced manufactured materials

Microreactor developers at the 2019 GAIN Microreactors workshop expressed a need for advanced manufacturing to fabricate microreactor components. Powder metallurgy (PM) hot isostatic pressing (HIP) is more mature than other advanced manufacturing techniques for the following reasons: 1. a code case exists for Section III, Division 1, Subsection NB components of light water reactors to be manufactured using PM HIP Alloy 316L, and 2. tensile and creep properties have been shown to be equivalent to wrought material for Type 316 stainless steel and Grade 91. Thus, PM HIP is more readily deployable in the near term. Elevated-temperature cyclic properties of PM-HIP materials, however, have not been established. The scope of testing for Code qualification could be significantly reduced compared to a new material for the following reasons: 1. only a limited amount of time consuming creep testing would be required, and 2. testing of fatigue and creep-fatigue behavior could be reduced if it can be demonstrated that the properties are comparable to wrought material. The objective of this work package is to develop an understanding of the relationship of advanced materials processing on the material characteristics as they relate to elevated-temperature component design and construction. This will be achieved by the following: • Elevated-temperature fatigue and creep-fatigue testing of PM HIP and wrought Alloy 316L. • Fracture and microstructural characterization of the PM HIP and wrought Alloy 316L. • Analysis of the elevated-temperature fatigue and creep-fatigue properties of PM HIP Alloy 316L. • Draft a report evaluating the elevated-temperature fatigue and creep-fatigue properties of PM HIP Alloy 316L. • Pursue procurement of Alloy 316H and Grade 91 manufactured using PM HIP. • Initiate scoping studies of the procured Alloy 316H or Grade 91 manufactured using PM HIP contingent upon successful material procurement.

36 MATERIALS SCIENCE↗

DOE OSTI2020

2019 ASHRAE Handbook: HVAC Applications - Chapter 37 - Energy Use and Management

Handbook is a highly-regarded engineers reference book for heating, ventilating, air conditioning, and energy engineers. Building energy and water use metrics were developed for 53 commercial and residential building types. Supporting narrative was drafted and provided along with multiple tables of building performance metrics for publication in this ASHRAE handbook. ORNL (T. Sharp) developed the building performance metrics in Tables 2, 3, and 4 and authored the narrative about them. T. Sharp also authored the section on "Benchmarking Water Use" and developed building water use metrics published in Table 5.

Sharp, Terry↗

DOE OSTI2019

Application of the Licensing Modernization Project Approach to the Authorization of the Versatile Test Reactor

The Licensing Modernization Project (LMP) has created a risk-informed, performance-based process for nonlight water reactor licensing under the U.S. Nuclear Regulatory Commission (NRC). Adoption of the LMP process has been recommended by the Advisory Committee on Reactor Safeguards (ACRS) [2] and the NRC has issued a draft regulatory guide [3]. The LMP process utilizes risk information to justify the regulatory treatment of event sequences, the classification of structures, systems, and components (SSCs), and to assist with the evaluation of defense-in-depth (DID). The Versatile Test Reactor (VTR) seeks to leverage the efforts of the LMP to develop a risk-informed, performance-based approach for reactor authorization under the U.S. Department of Energy (DOE). Due to differing rules and regulations between the NRC and DOE, modifications to the LMP process are necessary for the VTR authorization approach. However, the goals regarding risk-informed event categorization, SSC classification, and DID evaluation, remain the same.

Grabaskas, David↗

DOE OSTI2017

The Phase-2 Upgrade of the CMS Tracker

This is a draft version of the CMS TDR devoted to the upgrade of the CMS tracker in view of the HL-LHC running. The final document will be uploaded in a future occasion. This version is only meant to start the procedure and get the LHCC report number, so that we can conclude the preparation of the final document.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

DOE OSTI2021

The 2021 Annual CSEWG Meeting at Nuclear Data Week(s)

From November 15-19, 2021, CSEWG held its annual meeting during Brookhaven National Laboratory’s Nuclear Data Week(s)1. The combined event was held via zoom (due to COVID travel restrictions) and there were 175 registered attendees. This was CSEWG’s 3rd fully virtual meeting and, by all accounts, it was a success. The timetable and talks are available at https://indico.bnl.gov/event/13121/overview for registered participants. This meeting began with the welcoming of the new ENDF Library Manager, Gustavo Nobre, the announcement that ENDF/B-VIII.1’s release will be delayed until February 2024 due to COVID induced delays, and the adoption of a draft Code of Conduct. This last point is notable since CSEWG is known for its lively physics and engineering discussions. However, as professionals, we must endeavor to keep our discussions civil, collegial, and inclusive.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

DOE OSTI2021

Introducing PRIMRE's MRE Software Knowledge Hub (February 2021)

This paper focuses on the role of the Marine Renewable Energy (MRE) Software Knowledge Hub on the Portal and Repository for Information on Marine Renewable Energy (PRIMRE). The MRE Software Knowledge Hub provides online services for MRE software users and developers, and seeks to develop assessments and recommendations for improving MRE software in the future. Online software discovery platforms, known as the Code Hub and the Code Catalog, are provided. The Code Hub is a collection of open-source MRE software that includes a landing page with search functionality, linked to files hosted on the MRE Code Hub GitHub organization. The Code Catalog is a searchable online platform for discovery of useful (open-source or commercial) software packages, tools, codes, and other software products. To gather information about the existing MRE software landscape, a software survey is being performed, the preliminary results of which are presented herein. Initially, the data collected in the MRE software survey will be used to populate the MRE Software knowledge hub on PRIMRE, and future work will use data from the survey to perform a gap analysis and develop a vision for future software development. Additionally, as one of PRIMRE's roles is to support development of MRE software within project partners, a silo of knowledge relating to best practices has been gathered. An early draft of new guidance developed from this knowledge is presented.

gap analysis↗

DOE OSTI2022

Updated Waste Management System Analysis Tool Requirements and Enhancements

Draft presentation for presentation to Nuclear Waste Technical Review Board Winter/Spring Meeting March 2nd NOTE: FYI this presentation is almost the same as the presentation that will be uploaded soon entitled 'Next Generation System Analysis Model: Recently Added Features and Future Plans' for the Waste Management 2022 conference.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

DOE OSTI2022

U.S. Solar System Decommissioning Policies

In the United States, cumulative installed utility-scale solar photovoltaic (PV) capacity reached more than 60 gigawatts (GW)dc at the end of 2020. Federal and state renewable energy and net-zero emissions policies will continue to drive solar development in the United States with installed utility-scale PV projected to quadruple (240 GWdc) by 2030. Although more than 75% of all U.S. installed utility-scale PV came online in the last 5 years, federal, state, and local governments are planning for system decommissioning. Our research found that as of April 2021, one federal agency, the Bureau of Land Management (BLM), and 15 U.S. states have solar decommissioning policies in place. North Carolina is also in the process of drafting solar decommissioning regulations, and at least 4 states (Maine, Pennsylvania, West Virginia, Texas) proposed solar decommissioning bills in the 2021 legislative session. This presentation looks at U.S. federal and state solar decommissioning policies who they apply to, when they apply, the requirements/responsibilities, and what the impacts are.

circular economy↗

DOE OSTI2022

Global Energy Policy to Achieve the United States’ Nationally Determined Contributions: Potential Pathway

In 2021, the United States declared its Nationally Determined Contribution (NDC) in preparation for the COP26 climate summit, setting goals to achieve zero emission electricity by 2035, and reducing net emissions by 50–52% compared to 2005 levels. The current U.S. energy policies were found to not be adequate to meet these goals, thus it is necessary to draft a pathway to achieving these goals through policy changes. This study focused on foreign energy policies to analyze the most effective policies in a host of sectors. By identifying the most ambitious and effective policies from around the world in each sector, this study was able to suggest a policy pathway that can potentially achieve both of goals set in the NDC. In guiding the development of the proposed policy pathway, this study analyzed policies from Australia, Canada, California, China, Denmark, France, Germany, Japan, Russia, South Korea, Sweden, the United Kingdom, and the United States. This study found that the most drastic CO2 reductions came from low-carbon electricity policy, but contributions were also made from carbon capture, reforestation, hydrogen, energy efficiency, and climate smart agriculture.

29 ENERGY PLANNING, POLICY, AND ECONOMY↗

DOE OSTI2022

Projections of Environmental Impacts of Biofuels Across Scenarios Using Prospective LCA

This work showcases a collaboration between leading institutions focusing on integrated assessment modeling (IAM) and life cycle assessment (LCA), sponsored - among others - by the International Energy Agency's Technology Collaboration Program on Bioenergy, Task 45. It presents draft results of a prospective LCA for biofuels across world regions, using regional IAM scenario outputs, and life cycle inventories for country-specific pathways.

bioenergy↗