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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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At least 163 records · Page 9
All sourcesNASA NTRSDOE OSTI
DOE OSTI2017

Energy Savings Analysis of the Proposed Revision of the Washington D.C. Non-Residential Energy Code

This report presents the results of an assessment of savings for the proposed Washington D.C. energy code relative to ASHRAE Standard 90.1-2010. It includes annual and life cycle savings for site energy, source energy, energy cost, and carbon dioxide emissions that would result from adoption and enforcement of the proposed code for newly constructed buildings in Washington D.C. over a five year period.

Commercial Energy Code↗
DOE OSTI2018

Proposed Guidance for Preparing and Reviewing Molten Salt Nonpower Reactor Licence Applications (NUREG-1537)

Development of non-power molten salt reactor (MSR) test facilities is under consideration to support the analyses needed for development of a full-scale MSR. These non-power MSR test facilities will require review by the US Nuclear Regulatory Commission (NRC) staff. This report proposes chapter adaptations for NUREG-1537 in the form of interim staff guidance to address preparation and review of molten salt non-power reactor license applications. The proposed adaptations are based on a previous regulatory gap analysis of select chapters from NUREG-1537 for their applicability to non-power MSRs operating with a homogeneous fuel salt mixture.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2019

Final Energy Savings Analysis of the Proposed NYStretch-Energy Code 2018

In 2017, New York State Energy Research and Development Authority (NYSERDA) developed its 2016 Stretch Code Supplement to the 2016 New York State Energy Conservation Construction Code. Since2017, NYSERDA has continued to develop the 2018 edition, as part of the efforts to achieve a statewide Net Zero Energy Code by 2028. To support this effort, Pacific Northwest National Laboratory (PNNL)conducted energy simulation analysis to quantify the energy savings of proposed commercial provisions of the NYStretch-Energy Code 2018 compared to ANSI/ASHRAE/IES1 Standard 90.1-2013. Specifically, PNNL collaborated with New Buildings Institute (NBI), and developed energy-efficiency measures (EEMs) from national model codes and standards, high-performance building codes and standards, regional energy codes, and measures being proposed as part of the ongoing NYStretch-Energy code development process. PNNL analyzed these measures using whole building energy simulation for selected prototype commercial and multifamily buildings representing buildings in New York State.

29 ENERGY PLANNING, POLICY, AND ECONOMY↗
DOE OSTI2019

Final Energy Savings Analysis of the Proposed NYStretch-Energy Code 2018

In 2017, New York State Energy Research and Development Authority (NYSERDA) developed its 2016 Stretch Code Supplement to the 2016 New York State Energy Conservation Construction Code. Since 2017, NYSERDA has continued to develop the 2018 edition, as part of the efforts to achieve a statewide Net Zero Energy Code by 2028. To support this effort, Pacific Northwest National Laboratory (PNNL) conducted energy simulation analysis to quantify the energy savings of proposed commercial provisions of the NYStretch-Energy Code 2018 compared to ANSI/ASHRAE/IES1 Standard 90.1-2013. Specifically, PNNL collaborated with New Buildings Institute (NBI), and developed energy-efficiency measures (EEMs) from national model codes and standards, high-performance building codes and standards, regional energy codes, and measures being proposed as part of the ongoing NYStretch-Energy code development process. PNNL analyzed these measures using whole building energy simulation for selected prototype commercial and multifamily buildings representing buildings in New York State. This report describes the analysis methodology, explains detailed specifications of the EEMs, and summarizes the results of individual EEMs and EEM bundles by building type and climate zone. As shown in Figure ES.1, significant energy saving could be achieved by adopting the NYStretch-Energy Code 2018.

32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATI↗
DOE OSTI2016

Proposed 10 MWe North-Facing Falling Particle Receiver Design

A 10 MWe north-facing falling particle receiver (FPR) is proposed in this document to support performance comparisons of this design when compared with a direct s-CO 2 solar receiver concept. This document describes the modeling and simulation effort for the proposed FPR to evaluate its thermal performance. A description of the modeling strategy is provided in the following section including details on the receiver and heliostat field. Then, this model is used to evaluate the performance of the receiver at various times of throughout the year. Finally, the results of this analysis are summarized. Direct comparisons with a similarly sized s-CO 2 solar receiver concept are not discussed here.

47 OTHER INSTRUMENTATION↗
DOE OSTI2018

A Proposed Path Forward for Transportation of High-Assay Low-Enriched Uranium

Many of the advanced reactors that are being designed will use high-assay low-enriched uranium (HALEU) as the reactor fuel. HALEU is fuel that is enriched between 5% – 20% uranium-235. With the change to higher enriched material, the industry will have new challenges with the development and regulatory approval of enrichment and fuel fabrication facilities and suitable transportation packages to support the economic use of HALEU materials. One area of concern relates to ensure sub-criticality of the material during transportation as identified by the Nuclear Energy Institute (NEI). To evaluate the relevant work, experts, and industry perspectives on HALEU, a workshop was organized to share relevant experience and insights into HALEU transportation, handling, and management. At the August 30 and 31, 2018 workshop, NEI and industry provided the following recommendations to DOE and the national lab complex. 1. DOE and the lab complex should communicate and educate the Nuclear Regulatory Commission (NRC) on criticality issues related to HALEU. 2. Idaho National Laboratory (INL) should support work needed to certify package design for the transportation of HALEU. a. Suggest amending the Certificate of Compliance of an existing package used for the shipment of commercial quantities. b. Suggest DOE provide funding to package designer(s) for analysis and engineering work for a package to be submitted to NRC for approval. 3. INL should provide specific, or a range, of the expected impurities that will be present in recycled naval fuel. 4. In the longer term, DOE and the lab complex should increase the availability of criticality benchmark data to further reduce conservatism in package design. In addition, a couple key takeaways were identified, including: 1. Although the labs can provide additional criticality experiments, industry has enough data to license facilities, overpacks, and cylinders. Validation from additional critical experiments to establish less uncertainty in the benchmarks will be helpful. 2. A collective effort from industry is needed to express consistency on how much information exists or is needed related to criticality. Based on interactions with industry, DOE, and national laboratories, it appears that large-volume transportation of fresh HALEU appears feasible from a criticality perspective. Specifically, an initial review of applicable criticality benchmark experiments identified numerous applicable experiments. However, a more thorough review of a realistic transportation package design is suggested. Therefore, the following next steps are proposed: 1. Evaluate a large volume package with uranium dioxide enriched to 20%. Specifically, the GNF-A NPC package was proposed as a potentially viable option. 2. Based on the results of (1), determine if additional package designs and fuel material should be evaluated. 3. Based on the results of (1), determine if additional criticality experiments would be beneficial to improve the margins for criticality due to uncertainties. 4. Determine DOE transportation needs (packages sizes, shielding requirements, handling/operational requirements, and timing of availability) related to HALEU. 5. Continue to interface with NEI and interested industry companies to determine the appropriate time to engage the NRC.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2018

PROPOSAL: P-1101 Matter-wave Atomic Gradiometer Interferometric Sensor (MAGIS-100)

We propose to build and install at Fermilab a next generation instrument that uses light pulse atom interferometry to search for physics beyond the Standard Model. In particular, we propose to search for dark matter and new forces, and to test some aspects of quantum mechanics in a new regime. The setup will exploit the existing 100m vertical NuMI access shaft, and will be an upgrade of the existing 10m-scale experiment at Stanford. Note that for many searches, the sensitivity of the experiment is proportional to baseline. To fully exploit the opportunity, we would use the latest advances in atomic clock technologies. The experiment would also provide an R&D platform for, and a critical step towards, the next-but-one generation experiment, which might possibly be located in a shaft at SURF in South Dakota, and which would be sufficiently sensitive to detect, in an unexplored frequency range, gravitational waves from known sources.

72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS↗
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↗
DOE OSTI2020

Sensitive Resources Assessment and Forest Analysis for the Proposed Versatile Test Reactor, Oak Ridge, Tennessee

The US Department of Energy’s (DOE’s) Oak Ridge National Laboratory (ORNL) is a leading institution in advanced materials, supercomputing, neutrons, and nuclear science. As a research laboratory managed by UT-Battelle, LLC for DOE, ORNL has national priorities in energy, security, and scientific discovery that necessitate facility improvements and expansions. DOE is also committed to environmental stewardship. The laboratory is located on the ~32,000-acre (~13,000-ha) Oak Ridge Reservation (ORR), much of which is categorized as a National Environmental Research Park (NERP) and a state Wildlife Management Area. DOE works with the Tennessee Wildlife Resources Agency (TWRA), Tennessee Department of Environment and Conservation (TDEC), US Fish and Wildlife Service (USFWS), US Department of Agriculture, and other agencies to serve as an effective steward of the ORR. Accordingly, project managers must conform to environmental regulations, agreements, and policies at the federal, state, and institutional levels. Per 40 CFR (Code of Federal Regulations) 1508.14, potential effects on research and science education also represent potential effects of federal actions on the NERP, and impacts on, e.g., deer harvest, must be considered on the Oak Ridge Wildlife Management Area when other aspects of the human environment are affected. The United States currently has no fast neutron testing capability to support advanced nuclear research and development. The proposed Versatile Test Reactor (VTR) will take advantage of current investments by the US government and private industry in nuclear reactors to expedite the design and construction process, using proven technology to create a world-class scientific infrastructure. The VTR will take advantage of fast neutrons provided by this proven technology, along with a capability to rapidly insert, conduct, and remove state-of-the-art experiments. An advantage of the VTR is that it can support future innovations in experimental capabilities without modifying the facility. The VTR will support progress in a variety of science and technology areas, including testing and qualification of advanced reactor fuels; testing and qualification of innovative structural materials; testing of innovative components and instruments; validation of advanced modeling and simulation tools; and versatility for future technical missions. Through proven technology, the VTR can take advantage of existing reactor designs and operating experience to reduce the risk, cost, and time for design and construction. The top available resources of DOE laboratories, industry, and universities will be used to expedite reactor design and construction toward developing the scientific infrastructure that affords a strong testing capability that can be sustained over many years. This report summarizes current knowledge of natural and cultural resources primarily within the VTR construction area. At the time of this report, the proposed VTR site design includes a construction area of ~150.4 acres (~69.9 ha), which contains an ~51.3-acre (~20.8-ha) operations area, located within forested natural areas of the ORR. The primary goal of the work presented here was to evaluate potential effects on sensitive resources that might result from development and construction activities associated with VTR. In addition to on-the-ground surveys during spring and summer 2020 by the ORNL Natural Resources Management Program and Aquatic Ecology Group staff, this report makes use of historical (pre-1995) and contemporary (1995 to present) data from additional confirmed sources (e.g., TDEC). Likewise, forest conditions were compiled from a 2011 forest inventory and supplemented with limited ground observations in 2020. The individuals who obtained and compiled the data presented here are familiar with and routinely assess sensitive resources on the ORR. Anyone who references this report must consider that the timing of surveys did not permit a complete delineation of the resources that will be affected. If the VTR project proceeds, additional surveys will be required to account for the seasonal patterns of various threatened and endangered species. Data deficiencies and potential resources that likely went undetected are indicated where possible. Accordingly, this report should facilitate more environmentally sound decisions during planning and 2 development of the VTR site, provide a foundation for further assessment of sensitive and cultural resources, and help project managers better address regulatory guidance and DOE policies on sustainable development in compliance with, for example, the US Endangered Species Act (ESA), Migratory Bird Treaty Act (MBTA), Tennessee Rare Plant Protection and Conservation Act of 1985, Tennessee Nongame and Endangered or Threatened Wildlife Species Conservation Act of 1974, several federal and state regulations regarding aquatic resource protection, and site-specific policies as outlined in various ORR management plans developed by ORNL and TWRA for DOE.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2020

Proposal to use the DOE-STD-3009-2014 Methodology to Prepare the Documented Safety Analysis (DSA) for Research Reactor Nuclear Facilities

Sandia National Laboratories (SNL) personnel operate a low power research reactor (the Annular Core Research Reactor, or ACRR), and a zero-power critical experiment assembly referred to as CX. In accordance with 10 CFR 830, Subpart B, Appendix A, the acceptable methodology for developing a Documented Safety Analysis (DSA) for DOE nuclear reactors is the Nuclear Regulatory Commission’s (NRC’s) Regulatory Guide 1.70 (RG 1.70). RG 1.70 does not address certain areas required by 10 CFR 830 and expected by DOE (e.g., full facility hazard analysis).Thus, the current DSAs for SNL’s reactor nuclear facilities are based on RG 1.70, but also of necessity supplemented by DOE-STD-3009-94 methods. SNL personnel, in consultation with the National Nuclear Security Administration (NNSA) Sandia Field Office (SFO), have concluded that an alternate methodology is preferred to RG 1.70. The details of the proposal, and the reasons motivating its development, are discussed in the order described below. The proposed alternate methodology will be applicable to the ACRR and the CX (i.e., it will be applicable to nuclear facilities in which a reactor and/or a critical assembly will be operated).

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2020

A Proposed Common Model of Multi-phase Strength and Equation of State for a Tri-laboratory Collaboration (Working Draft 1.1)

The proposed simple common model for multiphase strength and EoS (CMMP) is meant to be sufficiently simple that each of the collaborating labs can share in a common starting point. Another objective is to start with relatively simple assumptions, which will not necessarily capture details of the physical processes, and incrementally add complexity in order to identify the minimal-needed technical detail. Through this co-evolution of model and experiment, we will better learn the importance of various theoretical approximations and where to invest future resources in experiment and model development. This simple framework is based on pressure and temperature equilibrium of all co-existing phases combined with deviatoric stress averaging through a volume fraction weighted ow stress and a volume fraction weighted shear modulus. Implementations of the framework based on equilibrium phase fractions (i.e. instantaneous kinetic rate) and for finite rate transition kinetics are proposed.

36 MATERIALS SCIENCE↗
DOE OSTI2022

Environmental Effects Assessment for Proposed Offshore Wind Farm off the Coast of Grays Harbor, Washington

Grays Harbor Wind LLC (GHW) is proposing to develop a floating offshore wind farm offshore of west Grays Harbor County, Washington (Grays Harbor). The proposed GHW Offshore Wind Project (Project) would entail construction, installation and operation of a 1,000-megawatt (MW) offshore wind farm consisting of approximately 75 floating units, each containing a floating foundation and wind turbine generator (WTG). The Project location is approximately 25 miles (21.7 nautical miles [nmi]) offshore west of Grays Harbor, at waters depths of 360 to 700 feet. The Pacific Northwest National Laboratory (PNNL) was contracted by Herrera Environmental Consultants, Inc. on behalf of GHW to carry out this preliminary scoping study to evaluate baseline conditions and potential effects on fish and marine mammals from development and operation of a floating offshore wind farm installed within a designated area off the coast of Washington1. Floating offshore wind units installed in an ocean environment as part of the Project would interact with marine wildlife. This Study report provides an initial data aggregation and analysis, using publicly available data, of the Project effects, both negative and positive, on the marine environment. The scope of this assessment is limited by the fact that the Project development is presently at the conceptual level. Data on marine organisms were aggregated and evaluated; however seabirds were evaluated by Herrera Environmental Consulting and, along with bats, were not included in the scope of this study. Significant additional work is necessary to characterize ocean, seafloor, and environmental conditions; select appropriate floating offshore wind technologies; identify construction methods and locations; and assess facility locations, including electrical interconnection. Data aggregation and analysis of seabirds and bats is also needed. Evaluation of the full range of potential environmental effects would be conducted following an award of a lease from the Bureau of Ocean Energy Management (BOEM) as part of the leasing, National Environmental Policy Act (NEPA)/State Environmental Policy Act (SEPA) environmental review and permitting processes. While this initial data aggregation and analysis uses best available public scientific information and current assumptions about the Project configuration, the effects discussed herein are based on the status of review to-date and may change as Project-specific details are developed.

17 WIND ENERGY↗
DOE OSTI2021

Corrosion Testing Proposal -1: Assessment of the Corrosion of Stainless Steel Subjected to an Aqueous Solution of Hydrochloric Acid

This corrosion-test proposal outlines the methods to promote rapid pitting corrosion on various pitting resistant stainless steels under controlled conditions. This study can be performed in-whole or in- part as the Corrosion Working Group (CWG) leadership of the Los Alamos National Laboratory (LANL) deems pertinent. This proposal is in response to CWG’s need to understand the mechanisms and the possible detrimental failure of the 316L SAVY (an acronym that represents the first initial of the four co-developers, Stone, Anderson, Veirs, Yarbro) 4000 container design currently in service. This detrimental failure evolved from a question that the CWG arrived to by consensus as “What is the critical pit depth that would comprise the design wall-strength of the SAVY-4000?”

36 MATERIALS SCIENCE↗
DOE OSTI2022

Proposed Test of the Two Beam BPM at RHIC

The essence of the ERL operation implies that at least two beams (accelerated and decelerated) are co-propagating in the same vacuum vessel and each beam has its own trajectory. The existing beam position monitors measure only “average” trajectory but not that of an individual beam, unless the time separation between bunches is so large that one can resolve individual bunches. It was proposed to use phase information of the pick-up signal to extract information on the orbit “difference”. We are planning to conduct experiments at RHIC to test the proposed idea. The approach and experiment set-up are described in the paper.

43 PARTICLE ACCELERATORS↗
DOE OSTI2022

Proposed Methodology for Evaluating and Validating TSLs [Slides]

This presentation begins by providing an overview of the research and discusses recent efforts in validating thermal neutron scattering cross sections, including differential cross section measurements at ORNL for evaluation and validation, total cross section measurements at RPI, pulsed-neutron die-away experiments at LLNL, and integral criticality experiments by LLNL. The presentation also proposes a methodology not only for validating thermal scattering files that utilizes all available experimental data, but also for evaluating new libraries as demonstrated on polystyrene. In conclusion, polystyrene evaluation was conducted using multiple experiments, including differential and integral. The proposed methodology has been shown to improve neutron transport and files have been submitted to NNDC for inclusion in ENDF/B-VIII.1 release. MCT-012 & PCM-002 has been relatively insensitive to changes in $\mathcal{S}(α,β)$. The research found that differences in differential results don’t always propagate to differences in integral results, hence why evaluation of differential data important. Future work on the project is also discussed.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
DOE OSTI2019

Proposed Occupational Exposure Limits for Furans

This report documents the re-evaluation of Hanford Tank Farm occupational exposure limits ( HTF OEL) for furan and 13 associated substituted furans identified as Chemicals of Potential Concern. Furan causes liver toxicity and cancer in laboratory animals. Recent toxicity studies in animal models have established a non-genotoxic mechanism of action and new data to support re-evaluation of the furan HTF OEL. As such, PNNL proposes to adjust the HTF OEL for furan from 1 ppb to 1.9 ppb based on a no-observed-adverse-effect level in Fischer-344 rats (the most sensitive species tested) exposed to subchronic oral administration of furan as a point of departure modified by species extrapolation of dose and route, inter- and intra-species uncertainty factors, and adjustments for life-time versus occupational exposure periods. Because of limited data and similar hypothesized mechanisms of toxicity, PNNL recommends continuing to use the furan HTF OEL as a surrogate for substituted furans until further data for substituted furans become available. Further toxicity investigations or new OELs proposed by authoritative organizations (e.g., National Institute of Occupational Safety and Health, Occupational Safety and Health Administration, and the American Conference of Government Industrial Hygienists) would warrant re-evaluation of HTF OEL for furan and substituted furans.

63 RADIATION, THERMAL, AND OTHER ENVIRON. POLLUTAN↗
DOE OSTI2018

Proposed Risk-Based Approach for Nitrosamine Chemicals of Potential Concern

This report documents the re-evaluation of Hanford Tank Farm (HTF) occupational exposure limits (OEL) for five N-nitrosamines identified as Chemicals of Potential Concern (COPC), and two other N-nitrosamines being considered as COPCs. N-nitrosamines are genotoxic, and exposure has been historically regulated based on cancer as the endpoint of concern. Currently, HTF OELs are based on German Maximum Arbeitsplatz Konzentration values that are no longer used. The National Institute of Occupational Safety and Health (NIOSH) recently released new policy applying a risk-based approach to develop OELs for occupational carcinogens and plans to release guidance on specific chemicals in the future. Consistent with this new NIOSH policy, Pacific Northwest National Laboratory proposes a risk-based approach to establish risk-specific doses for occupational exposures to N-nitrosamine COPCs. This approach establishes a range of N-nitrosamine inhalation exposures associated with risk levels that can be used as a tool for protecting HTF workers. Updated guidance from NIOSH or other authoritative bodies on N-nitrosamine OELs should trigger a re-evaluation of this proposed approach.

63 RADIATION, THERMAL, AND OTHER ENVIRON. POLLUTAN↗