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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.

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All sourcesNASA NTRSDOE OSTI
DOE OSTI2017

Sustainable network design for multi-purpose pellet processing depots under biomass supply uncertainty

This work develops a two-stage stochastic mixed-integer programming model to manage multi- purpose pellet processing depots under feedstock supply uncertainty. The proposed optimization model would help to minimize cost and to mitigate emissions from the supply chain network. We consider three alternative Biomass Processing and Densi cation Depot (BPDD) technologies; namely, conventional pellet processing, high moisture pellet processing, and ammonia ber expansion. These three technologies pre-process/pre-treat and densify different types of biomass into more highly densi ed intermediate products for different markets in order to improve movability and overall supply network performance in terms of costs and emissions. A hybrid decomposition algorithm was developed that combines sample average approximation with an enhanced Progressive Hedging (PH) algorithm to solve this challenging NP -hard problem. Some heuristics such as Rolling Horizon (RH) heuristic, variable xing technique were later applied to further enhance the PH algorithm. Mississippi and Alabama were selected as a testing ground and ArcGIS was employed to visualize and validate the modeling results. The results of the analysis reveal promising insights that could lead to recommendations to help decision makers achieve a more cost-effective environmentally-friendly supply chain network.

09 BIOMASS FUELS↗
DOE OSTI2013

Monitoring: The missing piece

The U.S. National Environmental Policy Act (NEPA) of 1969 heralded in an era of more robust attention to environmental impacts resulting from larger scale federal projects. The number of other countries that have adopted NEPA's framework is evidence of the appeal of this type of environmental legislation. Mandates to review environmental impacts, identify alternatives, and provide mitigation plans before commencement of the project are at the heart of NEPA. Such project reviews have resulted in the development of a vast number of reports and large volumes of project-specific data that potentially can be used to better understand the components and processes of the natural environment and provide guidance for improved and efficient environmental protection. However, the environmental assessment (EA) or the more robust and intensive environmental impact statement (EIS) that are required for most major projects more frequently than not are developed to satisfy the procedural aspects of the NEPA legislation while they fail to provide the needed guidance for improved decision-making. While NEPA legislation recommends monitoring of project activities, this activity is not mandated, and in those situations where it has been incorporated, the monitoring showed that the EIS was inaccurate in direction and/or magnitude of the impact. Many reviews of NEPA have suggested that monitoring all project phases, from the design through the decommissioning, should be incorporated. Information gathered though a well-developed monitoring program can be managed in databases and benefit not only the specific project but would provide guidance how to better design and implement future activities designed to protect and enhance the natural environment. -- Highlights: • NEPA statutes created profound environmental protection legislative framework. • Contrary to intent, NEPA does not provide for definitive project monitoring. • Robust project monitoring is essential for enhanced environmental management. • Adaptive database framework is needed to accommodate project-monitoring data.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2016

Pore growth in U-Mo/Al dispersion fuel

U-Mo/Al dispersion fuel is currently under development in the DOE’s Material Management and Minimization program to convert HEU-fueled research reactors to LEU-fueled reactors. In some demanding conditions in high-power and high-performance reactors, large pores form in the interaction layers between the U-Mo fuel particles and the Al matrix, which pose a potential to cause fuel failure. In this study, comprehension of the formation and growth of these pores was explored. As a product, a model to predict pore growth and porosity increase was developed. Well-characterized in-pile data from reduced-size plates were used to fit the model parameters. A data set of full-sized plates, independent and distinctively different from those used to fit the model parameters, was used to examine the accuracy of the model.

in-pile data↗
DOE OSTI2016

Fabrication and testing of U–7Mo monolithic plate fuel with Zircaloy cladding

The Materials Management and Minimization program is developing fuel designs to replace highly enriched fuel with fuels of low enrichment. In the most challenging cases, U–(7–10wt%)Mo monolithic plate fuel are proposed. The chosen design includes aluminum-alloy cladding, which provides some challenges in fabrication and fuel/cladding interaction in service. We investigated zircaloy cladding, specifically Zry–4as an alternative cladding, and development of a fabrication method was performed by researchers with the Comisión Nacionalde Energia Atómica (CNEA) in Argentina, resulting in test fuel plates (Zry–4 clad U–7Mo) which were subsequently tested in the Advanced Test Reactor in Idaho. Because Zry–4 and U–(7–10)Mo have similar high-temperature mechanical properties, fabrication was simplified in that the fuel foil and cladding could be co-rolled and bonded. The challenge was to prevent a thermal-expansion mismatch which could destroy the fuel/cladding bond before complete bonding was achieved; the solution was to prevent the composites from cooling significantly between roll passes. Our final product performed very well in-reactor, showing good bonding, very little fuel/cladding interaction, either from fabrication or in-reactor testing, and little swelling, especially no detectable heterogeneous bubble formation at the fuel/cladding interface tested to a fission density of up to 2.54E+21

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2017

Detailed measurements of local thickness changes for U-7Mo dispersion fuel plates with Al-3.5Si matrix after irradiation at different powers in the RERTR-9B experiment

The Materials Management and Minimization program is developing fuel designs to replace highly enriched fuel with fuels of low enrichment. Swelling is an important irradiation behavior that needs to be well understood. Data from high resolution thickness measurements performed on U-7Mo dispersion fuel plates with Al-Si alloy matrices that were irradiated at high power is sparse. This paper reports the results of detailed thickness measurements performed on two dispersion fuel plates that were irradiated at relatively high power to high fission densities in the Advanced Test Reactor in the same RERTR-9B experiment. Both plates were irradiated to similar fission densities, but one was irradiated at a higher power than the other. The goal of this work is to identify any differences in the swelling behavior when fuel plates are irradiated at different powers to the same fission densities. Based on the results of detailed thickness measurments, more swelling occurs when a U-7Mo dispersion fuel with Al-3.5Si matrix is irradiated to a high fission density at high power compared to one irradiated at a lower power to high fission density.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2016

Nuclear security policy in the context of counter-terrorism in Cambodia

The risk of nuclear or dirty bomb attack by terrorists is one of the most urgent and threatening danger. The Cambodian national strategy to combat weapons of mass destruction (WMD) depicts a layered system of preventive measures ranging from securing materials at foreign sources to interdicting weapons or nuclear or other radioactive materials at ports, border crossings, and within the Cambodian institutions dealing with the nuclear security to manage the preventive programs. The aim of this study is to formulate guidance, to identify scenario of threat and risk, and to pinpoint necessary legal frameworks on nuclear security in the context of counterterrorism based on the International Atomic Energy Agency nuclear security series. The analysis of this study is guided by theoretical review, the review of international laws and politics, by identifying and interpreting applicable rules and norms establishing the nuclear security regime and how well enforcement of the regime is carried out and, what is the likelihood of the future reform might be. This study will examine the existing national legal frameworks of Cambodia in the context of counterterrorism to prevent acts of nuclear terrorism and the threat of a terrorist nuclear attack within the Cambodia territory. It will shed light on departmental lanes of national nuclear security responsibility, and provide a holistic perspective on the needs of additional resources and emphasis regarding nuclear security policy in the context of counterterrorism in Cambodia.

98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗
DOE OSTI2017

The combined and separate impacts of climate extremes on the current and future US rainfed maize and soybean production under elevated CO 2

Heat and drought stresses are two emerging climatic threats to the US maize and soybean production, yet their impacts on yields are collectively determined by the magnitude of climate change and rising atmospheric CO2 concentration. Here we present a study that quantified the current and future yield responses of US rainfed maize and soybean to climate extremes, and for the first time characterized spatial shifts in the relative importance of temperature, heat and drought stress. Crop yields are simulated using the Agricultural Production Systems sIMulator (APSIM), driven by the high-resolution (12 km) Weather Research and Forecasting (WRF) Model downscaled future climate scenarios at two time slices (1995-2005 and 2085-2094). Our results show that climatic yield gaps and interannual variability are greater in the core production area than in the remaining US by the late 21st century under both Representative Concentration Pathway (RCP) 4.5 and RCP8.5 scenarios, and the magnitude of change is highly dependent on the current climate sensitivity and vulnerability. Elevated CO2 partially offsets the climatic yield gaps and reduces interannual yield variability, and effect is more prominent in soybean than in maize. We demonstrate that drought will continue to be the largest threat to US rainfed maize and soybean production, although its dominant role gradually gives way to other impacts of heat extremes. We also reveal that shifts in the geographic distributions of dominant stressors are characterized by increases in the concurrent stress, especially for the US Midwest. These findings imply the importance of considering drought and extreme heat simultaneously for future agronomic adaptation and mitigation strategies, particularly for breeding programs and crop management.

APSIM↗
DOE OSTI2015

UseLATEX.cmake

UseLATEX.cmake is a collection of script functions and examples for building LaTeX documents. It simplifies the process of building LaTeX documents, which requires the execution of multiple programs and the management of several input files. UseLATEX.cmake also provides several options to customize the LaTeX build process.

Moreland, Kenneth↗
DOE OSTI2015

Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1C, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2015

Mitigation of Syngas Cooler Plugging and Fouling

This Final Report summarizes research performed to develop a technology to mitigate the plugging and fouling that occurs in the syngas cooler used in many Integrated Gasification Combined Cycle (IGCC) plants. The syngas cooler is a firetube heat exchanger located downstream of the gasifier. It offers high thermal efficiency, but its’ reliability has generally been lower than other process equipment in the gasification island. The buildup of ash deposits that form on the fireside surfaces in the syngas cooler (i.e., fouling) lead to reduced equipment life and increased maintenance costs. Our approach to address this problem is that fouling of the syngas cooler cannot be eliminated, but it can be better managed. The research program was funded by DOE using two budget periods: Budget Period 1 (BP1) and Budget Period 2 (BP2). The project used a combination of laboratory scale experiments, analysis of syngas cooler deposits, modeling and guidance from industry to develop a better understanding of fouling mechanisms and to develop and evaluate strategies to mitigate syngas cooler fouling and thereby improve syngas cooler performance. The work effort in BP 1 and BP 2 focused on developing a better understanding of the mechanisms that lead to syngas cooler plugging and fouling and investigating promising concepts to mitigate syngas cooler plugging and fouling. The work effort focused on the following: • analysis of syngas cooler deposits and fuels provided by an IGCC plant collaborating with this project; • performing Jet cleaning tests in the University of Utah Laminar Entrained Flow Reactor to determine the bond strength between an ash deposit to a metal plate, as well as implementing planned equipment modifications to the University of Utah Laminar Entrained Flow Reactor and the one ton per day, pressurized Pilot Scale Gasifier; • performing Computational Fluid Dynamic modeling of industrially relevant syngas cooler configurations to develop a better understanding of deposit formation mechanisms; • performing Techno-Economic-Analysis for a representative IGCC plant to investigate the impact on plant economics, in particular the impacts on the Cost of Electricity (COE), due to plant shutdowns caused by syngas cooler plugging and fouling and potential benefits to plant economics of developing strategies to mitigate syngas cooler fouling; and • performing modeling and pilot scale tests to investigate the potential benefits of using a sorbent (fuel additive) to capture the vaporized metals that result in syngas cooler fouling. All project milestones for BP 1 and BP 2 were achieved. DOE was provided a briefing on our accomplishments in BP1 and BP2 and our proposed plans for Budget Period 3 (BP 3). Based on our research the mitigation technology selected to investigate in BP 3 was the use of a sorbent that can be injected into the gasifier with the fuel slurry to capture vaporized metals that lead to the deposit formation in the syngas cooler. The work effort proposed for BP 3 would have focused on addressing concerns raised by gasification industry personnel for the impacts on gasifier performance of sorbent injection, so that at the end of BP 3 the use of sorbent injection would be at “pre-commercial” stage and ready for use in a Field Demonstration that could be funded by industry or DOE. A Budget Continuation Application (BCA) was submitted to obtain funding for BP3 DOE but DOE chose to not fund the proposed BP3 effort.

47 OTHER INSTRUMENTATION↗
DOE OSTI2016

2014 Annual Site Environmental Report Summary Pamphlet for Sandia National Laboratories New Mexico.

This ASER Summary Pamphlet presents the environmental protection, restoration, and monitoring programs in place at SNL/NM during calendar year 2014. It also discusses Sandia’s compliance with environmental regulations, and it highlights significant environmental program efforts and accomplishments. The environmental programs and waste management activities at SNL/NM meet or exceed the requirements of federal, state, and local environmental regulations, as well as DOE directives in the contract between Sandia and DOE. This document, prepared in accordance with and as required by DOE Order 231.1B, Environment, Safety, and Health Reporting, is a key component of DOE’s efforts to keep the public informed about environmental conditions throughout the DOE/NNSA nuclear weapons complex.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2016

Long-Term Monitoring of Desert Land and Natural Resources and Application of Remote Sensing Technologies

Monitoring environmental impacts over large, remote desert regions for long periods of time can be very costly. Remote sensing technologies present a promising monitoring tool because they entail the collection of spatially contiguous data, automated processing, and streamlined data analysis. This report provides a summary of remote sensing products and refinement of remote sensing data interpretation methodologies that were generated as part of the U.S. Department of the Interior Bureau of Land Management Solar Energy Program. In March 2015, a team of researchers from Argonne National Laboratory (Argonne) collected field data of vegetation and surface types from more than 5,000 survey points within the eastern part of the Riverside East Solar Energy Zone (SEZ). Using the field data, remote sensing products that were generated in 2014 using very high spatial resolution (VHSR; 15 cm) multispectral aerial images were validated in order to evaluate potential refinements to the previous methodologies to improve the information extraction accuracy.

47 OTHER INSTRUMENTATION↗
DOE OSTI2016

TA-55 and Sigma Overview

These are slides from a facility overview presentation for visiting agencies to Los Alamos National Laboratory (LANL). The TA-55 Plutonium Facility (PF-4) is discussed in detail. PF-4 is a unique resource for US plutonium programs. The basic design is flexible and has adapted to changing national needs. It is a robust facility with strong safety and security implementation. It supports a variety of national programs. It will continue for many years into the future. Sigma is then discussed in detail, which handles everything from hydrogen to uranium. It has been in long term service to the Nation (nearly 60 years). It has a flexible authorization basis to handle almost the entire periodic table. It has a wide breadth of prototyping and characterization capabilities. It has integrated program and line management.

36 MATERIALS SCIENCE↗
DOE OSTI2017

GridAPPS-D Conceptual Design v1.0

The purpose of this document is to provide a conceptual design of the distribution system application development platform being developed for the U.S. Department of Energy’s Advanced Distribution Management System (ADMS) Program by the Grid Modernization Laboratory Consortium project GM0063. The platform will be referred to as GridAPPS-D. This document provides a high level, conceptual view of the platform and provides related background and contextual information. This document is intended to both educate readers about the technical work of the project and to serve as a point of reference for the project team. The document will be updated as the project progresses.

97 MATHEMATICS AND COMPUTING↗
DOE OSTI2018

Underground Test Area Calendar Year 2017 Quality Assurance Report Nevada National Security Site, Nevada

This report is required by the Underground Test Area (UGTA) Activity Quality Assurance Plan (QAP) (NNSA/NFO, 2015) and identifies the UGTA quality assurance (QA) activities for calendar year (CY) 2017 (January 1, 2017, through December 31, 2017). UGTA organizations—U.S. Department of Energy (DOE) Environmental Management (EM) Nevada Program conduct QA activities throughout the CY. The activities include conducting oversight assessments (OAs) for UGTA Activity QAP compliance, identifying findings and completing corrective actions, evaluating laboratory performance, reviewing technical work, and publishing documents.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2019

Underground Test Area Activity Preemptive Review Guidance Nevada National Security Site, Nevada

This report is a revision to the preemptive review (PER) guidance originally released as U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) document DOE/NV--1552 in 2016 (NNSA/NFO, 2016). PER committees review various products, including data, documents, software/codes, analyses, and models. PER committees provide technical recommendations to support regulatory decisions that are the responsibility of the DOE Environmental Management (EM) Nevada Program and NDEP. PERs are designed to be adaptable to the varying requirements of individual CAU studies. Their goals include the following: Maintaining high technical standards; ensuring work is technically adequate, competently performed, and documented consistent with other programmatic documents; and verifying that established quality requirements are satisfied. Helping focus CAU studies on UGTA Activity objectives identified in the FFACO by implementing Section 3 of Appendix VI, which includes the UGTA Strategy Flowchart (Figure 3-2) and Process Flow Diagram Dictionary for the UGTA CAUs (Table 3-1). Providing a mechanism for early identification of technical and/or strategy issues that could affect successfully implementing the UGTA strategy. Providing assurance to NDEP that work in progress and final reports are technically sound. Providing independent reviews that allow for a better understanding of the technical work, and result in products that are transparent and sufficient to allow the DOE EM Nevada Program to meet regulatory objectives.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2019

An Architectural Survey of the Test Cell C Historic District, Area 25, Nevada National Security Site, Nye County, Nevada

The U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) has authorized an updated recording and evaluation of Test Cell C. This facility is part of the former Nuclear Rocket Development Station (NRDS) in Area 25 of Nevada National Security Site (NNSS) in Nye County, Nevada (formerly the Nevada Test Site [NTS]). Future alterations to the facility are anticipated to meet current and future National Weapons Science, Global and Homeland Security Programs, and Environmental Management mission requirements. Therefore, this survey was done to comply with requirements of Section 106 of the National Historic Preservation Act and its implementing regulations, 36 C.F.R. Part 800. An architectural survey of 35.75 acres was completed by Desert Research Institute (DRI). This area also represents the potential Test Cell C Historic District and is identified by NNSA/NFO as the Area of Potential Effect (APE) within which the undertaking may directly cause alterations to the character of historic properties. One resource, Building 25-3210 (SHPO Resource No. B2444), within this area was previously surveyed by DRI. It was found eligible for inclusion in the National Register of Historic Places (NRHP or National Register) under Criteria A and C, and Consideration G. Mitigation of this building was completed prior to its demolition. The APE for reasonably foreseeable effects that may indirectly cause alterations later in time, be farther removed in distance, or be cumulative is the unrecorded NRDS historic district. The present survey updates the previous survey to present standards and expands it to include the entire Test Cell C complex. This includes updated recording and evaluation of the remains of 25-3210 and its 32 previously unrecorded and unevaluated Accessory Resources. The entire complex was recorded as the Test Cell C Historic District (SHPO Resource No. D346), which is eligible for the National Register at the National Level under Criteria A, C, and D. All nine architectural resources in the district are recommended as contributing elements of the Test Cell C Historic District (Figure 2). Of these, four (25-3210 Resource No. B2444, 25-3220 SHPO Resource No. B18110, 25-3226 SHPO Resource No. B18111, and 25-3230-32 SHPO Resource No. B18114) are recommended as individually eligible to the National Register under Criteria A and C, and one (KIWI-TNT [Transient Nuclear Test] SHPO Resource No. S2287) is recommended as individually eligible under Criteria A, C, and D. The remaining four resources (25-3214 SHPO Resource No. B18109, 25-3228 SHPO Resource No. B18112, 25-3229 SHPO Resource No. B18113, and 25-3233 SHPO Resource No. 18115) are not recommended as individually eligible. In addition, the Test Cell C Historic District is regarded as a contributor to the potential national significance of the NRDS Historic District. In 2010, the NTS became the NNSS. Because of the nature of the discussion in the Historic Context below, “NTS” is used throughout that section, otherwise “NNSS” is used to refer to the site. The survey area is located in unplatted sections of T13S R51E Mount Diablo Baseline and Meridian (projected) in Area 25 of the NNSS. It is within the NRDS in Jackass Flats, which has long been recognized as a potential historic district. An oblique aerial photo of the Test Cell C complex is shown on the cover of this report.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2020

Proposed guidance for preparing and reviewing a molten salt non-power production or utilization facility application

Development of non-power molten salt reactors (MSRs) are under consideration to further establish an MSR experience base, support the requirements of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.43(e), and provide any additional analyses needed for development of a full-scale MSR. Guidance provided in this report is based on MSRs operating with liquid fuel (i.e., fuel dissolved within a molten salt). These reactors, unless owned by the DOE or DOD, will require licensing by the US Nuclear Regulatory Commission (NRC) staff. Standard review plan (SRP) guidance for large light water reactors (LWRs) is available in NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants; Light Water Reactor (LWR) Edition. However, NRC staff observed that NUREG-0800 is very cumbersome to apply to non-power reactors “because of the great differences in complexity and hazards between non-power reactors and nuclear power plants.” Therefore, a program to develop performance-based guidance applicable to non-power reactors was initiated. In 1996, NUREG-1537, Parts 1 and 2, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, was published. Part 1, the format and content guide, suggests a uniform format for presenting information in non-power reactor applications that is acceptable to the NRC staff, but conformance with the format and content is not required. Part 2, the SRP, ensures the quality and uniformity of the staff review of an application. Unfortunately, the application guidelines and SRP do not provide adequate guidance for all advanced non-LWR technologies and applications. This discrepancy eventually led to the 2012 development of interim staff guidance (ISG) for NUREG-1537, which includes criteria for describing and reviewing aqueous homogeneous reactors (AHRs). Specifically, NUREG-1537 ISG, 2012 expanded the original document to address three areas: 1. updated criteria for heterogeneous non-power reactors, 2. criteria for licensing AHRs, and 3. criteria for licensing a Part 50-licensed isotope production facility. In 2015, the US Department of Energy (DOE) opted to build on the AHR NUREG-1537 ISG experience by performing a gap analysis of the guidance that would be used to license a non-power MSR. MSRs represent one of the advanced non-LWR technologies selected by DOE for development through a multiyear cost share award with Southern Company Services. Under this Advanced Reactor Concepts 2015 (DOE Advanced Reactor Concepts [ARC] 15) award program, the DOE tasked Oak Ridge National Laboratory (ORNL) to evaluate the guidance changes that the NRC may need to consider when licensing an MSR non-power reactor. ORNL staff, with support from Boston Government Services, LLC, focused on five system-related chapters in NUREG-1537 that were considered most relevant to inform the effort that would be required for a non-power MSR applicant. ORNL documented this review in a technical report, ORNL/TM-2018/834, Proposed Guidance for Preparing and Reviewing Molten Salt Non-Power Reactor License Applications (NUREG-1537). The report was subsequently shared with industry and the NRC. The 2018 review was limited in scope, focusing on key system chapters based on the expected significance of each chapter relative to expected differences in addressing advanced non-LWR technologies, specifically non-power MSRs, compared with heterogeneously fueled non-power reactors. In the ORNL report, proposed generic adaptations were suggested for the following NUREG-1537 chapters: Chapter 4, “Reactor Description”; Chapter 5, “Reactor Coolant Systems”; Chapter 6, “Engineered Safety Features”; Chapter 9, “Auxiliary Systems”; Chapter 11, “Radiation Protection Program and Waste Management” The inclusion of Chapter 11 in the previous review effort was intended to provide guidance for categorizing the waste-handling process for an MSR operating with homogenous fuel. The introductions from Parts 1 and 2 of the 2012 NUREG-1537 ISG provide guidance for the application and review of production facilities. After a period of operation, non-power MSRs with homogenous fuel will include gaseous and soluble fission products. The gaseous fission products will be collected and held for decay in an off-gas system. There might also be an initiative to polish or filter the soluble fission products in the fuel salt by some mechanical or chemical means. The treatment and handling of fission products in the non-power MSR fuel salt and the description of this process in the safety analysis report (SAR) must be very precise to avoid the waste treatment facility being construed as a co-located special nuclear material (SNM) fuel cycle facility (see Section 2.3 of this report). Subsequent to the release of ORNL/TM-2018/834, NRC staff expressed a desire to continue the regulatory gap analysis that was begun in that report. This would provide additional clarity and information addressed in certain sections of the original report, while also providing new guidance on certain topics not addressed in the original report. This revision would benefit the NRC staff reviewing applications involving non-power MSR designs and would help developers understand how the NRC staff might approach the review of such applications. The focus of this report is to provide infrastructure support to the NRC staff for the regulatory review of non-power MSRs.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗