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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 1,405 records · Page 78
All sourcesNASA NTRSDOE OSTI
DOE OSTI2016

Poster - 56: Preliminary comparison of FF- and FFF-VMAT for prostate plans with higher rectal dose

Purpose: A recent retrospective study found 53 patients previously treated to 78Gy/39 using flattened filtered (FF) 6X-VMAT at GRRCC had rectal DVH more than one standard deviation higher than the average. This study was to investigate if using 6FFFor10FFF beams could reduce these DVHs without compromising target coverage. Methods: Twenty patients’ plans were re-planed with 2-arc 6X-VMAT, 6FFF-VMAT and 10FFF-VMAT using the Eclipse TPS following departmental protocol. All plans had the same optimization and normalization, and were evaluated against the acceptance criteria from the QUANTEC and Emami. Statistical differences in the mean dose to OARs (D{sub m}) and PTV homogeneity index (HI) between energies were tested using the paired sample Wilcoxon signed rank statistical method (p<0.05). Beam delivery accuracy was checked on five patients using portal dosimetry (PD). Results: The PTV HI for the 10FFF shows no statistical difference from the 6X. All the OARs, except left femoral head with 6FFF, have significantly lower Dm using 6FFF and 10FFF .There is no difference in the maximum doses to rectum and bladder and are limited by the prescribed doses. Measurements show good agreements in the gamma evaluation (3%/3mm) for all energies. Conclusion: This preliminary study shows that doses to the OARs are reduced using 10FFF for the same target coverage. The plans using 6FFF result in lower doses to some OARs, and statistically different PTV HI. All plans showed very good agreement with measurements.

60 APPLIED LIFE SCIENCES↗
DOE OSTI2016

Sci-Sat AM: Radiation Dosimetry and Practical Therapy Solutions - 12: Suitability of plan class specific reference fields for estimating dosimeter correction factors for small clinical CyberKnife fields

Purpose: The purpose of this work is to investigate the utility of plan class specific reference (PCSR) fields for predicting dosimeter response within isocentric and non-isocentric composite clinical fields using the smallest fields employed by the CyberKnife radiosurgery system. Methods: Monte Carlo dosimeter response correction factors (CFs) were calculated for a plastic scintillator and microchamber dosimeter in 21 clinical fields and 9 candidate plan-class PCSR fields which employ the 5, 7.5 and 10 mm diameter collimators. Measurements were performed in 5 PCSR fields to confirm the predicted relative response of detectors in the same field. Results: Ratios of corrected measured dose in the PCSR fields agree to within 1% of unity. Calculated CFs for isocentric fields agree within 1.5% of those for PCSR fields. Large and variable microchamber CFs are required for non-isocentric fields, with differences as high as 5% between different clinical fields in the same plan class and 4% within the same field depending on the point of measurement. Non-isocentric PCSR fields constructed to have relatively homogenous dose over a region larger than the detector have very different ion chamber CFs from clinical fields. The plastic scintillator detector has much more consistent response within each plan class but still require 3–4% corrections in some fields. Conclusions: While the PCSR field concept is useful for small isocentric fields, this approach may not be appropriate for non-isocentric clinical fields which exhibit large and variable ion chamber CFs which differ significantly from CFs for homogenous field PCSRs.

61 RADIATION PROTECTION AND DOSIMETRY↗
DOE OSTI2025

Risk-controlled Expansion Planning with Distributed Resources (REPAIR) v1.0

The Risk-controlled Expansion Planning with Distributed Resources (REPAIR) is an innovative tool to support decisions around utility grid planning to prevent and mitigate the impact of outages caused by routine equipment failures (reliability) or by extreme events (resilience), such as storms, earthquakes or wildfires that long term interruption of service. REPAIR is a risk-based optimization and decision-making model allowing informed and transparent "cost vs risk" decisions regarding infrastructural planning of electric utilities. The model considers long-term resilience and reliability planning strategies that rely on traditional infrastructure upgrade (e.g. circuit hardening, reinforcement, new substations, etc.) or new investment alternatives, such as DERs.

Heleno, Miguel [Lawrence Berkeley National Laborat↗
DOE OSTI2014

Modeling and Field Test Planning Activities in Support of Disposal of Heat-Generating Waste in Salt

The modeling efforts in support of the field test planning conducted at LBNL leverage on recent developments of tools for modeling coupled thermal-hydrological-mechanical-chemical (THMC) processes in salt and their effect on brine migration at high temperatures. This work includes development related to, and implementation of, essential capabilities, as well as testing the model against relevant information and published experimental data related to the fate and transport of water. These are modeling capabilities that will be suitable for assisting in the design of field experiment, especially related to multiphase flow processes coupled with mechanical deformations, at high temperature. In this report, we first examine previous generic repository modeling results, focusing on the first 20 years to investigate the expected evolution of the different processes that could be monitored in a full-scale heater experiment, and then present new results from ongoing modeling of the Thermal Simulation for Drift Emplacement (TSDE) experiment, a heater experiment on the in-drift emplacement concept at the Asse Mine, Germany, and provide an update on the ongoing model developments for modeling brine migration. LBNL also supported field test planning activities via contributions to and technical review of framework documents and test plans, as well as participation in workshops associated with field test planning.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2015

Hazards Associated with Legacy Nitrate Salt Waste Drums Managed under the Container Isolation Plan

At present, there are 29 drums of nitrate waste salts (oxidizers with potentially acidic liquid bearing RCRA characteristics D001 and D002) that are awaiting processing, specifically to eliminate these characteristics and to allow for ultimate disposition at WIPP. As a result of the Feb. 14th, 2014 drum breach at WIPP, and the subsequent identification of the breached drum as a product ofLANL TRU waste disposition on May 15th, 2014, these 29 containers were moved into the Perrnacon in Dome 231 at TA-54 Area G, as part of the New Mexico Environment Department (NMED) approved container isolation plan. The plan is designed to mitigate hazards associated with the nitrate salt bearing waste stream. The purpose of this document is to articulate the hazards associated with un-remediated nitrate salts while in storage at LANL. These hazards are distinctly different from the Swheat-remediated nitrate salt bearing drums, and this document is intended to support the request to remove the un-remediated drums from management under the container isolation plan. Plans to remediate and/or treat both of these waste types are being developed separately, and are beyond the scope of this document.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2014

Building Energy Benchmarking in India: an Action Plan for Advancing the State-of-the-Art

This document describes an action plan for advancing the state of the art of commercial building energy benchmarking in the Indian context. The document is primarily intended for two audiences: (a) Research and development (R&D) sponsors and researchers can use the action plan to frame, plan, prioritize and scope new energy benchmarking R&D in order to ensure that their research is market relevant; (b) Policy makers and program implementers engaged in the deployment of benchmarking and building efficiency rating programmes can use the action plan for policy formulation and enforcement .

32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATI↗
DOE OSTI2015

Quinault Indian Nation Comprehensive Biomass Strategic Planning Project

The overall purposes of the Quinault Indian Nation’s Comprehensive Biomass Strategic Planning Project were to: (1) Identify and confirm community and tribal energy needs; (2) Conducting an inventory of sustainable biomass feedstock availability; (3) Development of a biomass energy vision statement with goals and objectives; (4) Identification and assessment of biomass options for both demand-side and supply side that are viable to the Quinault Indian Nation (QIN); and (5) Developing a long-term biomass strategy consistent with the long-term overall energy goals of the QIN. This Comprehensive Biomass Strategic Planning Project is consistent with the QIN’s prior two-year DOE Renewable Energy Study from 2004 through 2006. That study revealed that the most viable options to the QIN’s renewable energy options were biomass and energy efficiency best practices. QIN's Biomass Strategic Planning Project is focused on using forest slash in chipped form as feedstock for fuel pellet manufacturing in support of a tribal biomass heating facility. This biomass heating facility has been engineered and designed to heat existing tribal facilities as well as tribal facilities currently being planned including a new K-12 School.

09 BIOMASS FUELS↗
DOE OSTI2016

De-Inventory Plan for Transuranic Waste Stored at Area G

This report describes the strategy and detailed work plan developed by Los Alamos National Laboratory (LANL) to disposition transuranic (TRU) waste stored at its Area G radioactive waste storage site. The focus at this time is on disposition of 3,706 m 3 of TRU waste stored above grade by June 30, 2014, which is one of the commitments within the Framework Agreement: Realignment of Environmental Priorities between the Department of Energy (DOE) National Nuclear Security Administration (NNSA) and the State of New Mexico Environment Department (NMED), Reference 1. A detailed project management schedule has been developed to manage this work and better ensure that all required activities are aligned and integrated. The schedule was developed in conjunction with personnel from the NNSA Los Alamos Site Office (LASO), the DOE Carlsbad Field Office (CBFO), the Central Characterization Project (CCP), and Los Alamos National Security, LLC (LANS). A detailed project management schedule for the remainder of the above grade inventory and the below grade inventory will be developed and incorporated into the De-Inventory Plan by December 31, 2012. This schedule will also include all newly-generated TRU waste received at Area G in FYs 2012 and 2013, which must be removed by no later than December 31, 2014, under the Framework Agreement. The TRU waste stored above grade at Area G is considered to be one of the highest nuclear safety risks at LANL, and the Defense Nuclear Facility Safety Board has expressed concern for the radioactive material at risk (MAR) contained within the above grade TRU waste inventory and has formally requested that DOE reduce the MAR. A large wildfire called the Las Conchas Fire burned extensive areas west of LANL in late June and July 2011. Although there was minimal to no impact by the fire to LANL, the fire heightened public concern and news media attention on TRU waste storage at Area G. After the fire, New Mexico Governor Susana Martinez also requested that LANL accelerate disposition of TRU waste stored above grade at Area G. The 3,706 m 3 volume of TRU waste stored above grade consists of 4,495 containers that include all above grade non-cemented waste as well as above grade cemented waste that was ready for characterization on October 1, 2011. This volume includes all newly-generated TRU waste currently stored at Area G as of October 1, 2011. This volume does not include the Bolas Grandes spheres, mixed low level waste (MLLW) containers, empty containers, cemented waste that requires remediation, projected newly generated TRU waste from FY 2012 and later, or TRU waste stored below grade. The 3,706 m 3 volume represents about 86 per cent of the total volume of TRU waste stored above grade on October 1, 2011. The De-Inventory Plan supports the DOE Office of Environmental Management (EM) goal to disposition 90% of the Legacy TRU waste within the DOE complex by the end of 2015 as stated in its Roadmap for EM’s Journey to Excellence (Reference 2). The plan also addresses precursor actions for disposition of TRU waste that are necessary for compliance with the Compliance Order on Consent issued by the NMED in 2005 (Reference 3).

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2016

Field Implementation Plan for the In-Situ Bioremediation Treatability Study at the Technical Area-V Groundwater Area of Concern

This Field Implementation Plan (FIP) was prepared by Sandia National Laboratories, New Mexico (SNL/NM) and provides instruction on conducting a series of in-situ bioremediation (ISB) tests as described in the Revised Treatability Study Work Plan for In-Situ Bioremediation at the Technical Area-V Groundwater Area of Concern, referred to as the Revised Work Plan in this FIP. The Treatability Study is designed to gravity inject an electron-donor substrate and bioaugmentation bacteria into groundwater via three injection wells to perform bioremediation of the constituents of concern (COCs), nitrate and trichloroethene (TCE), in the regions with the highest concentrations at the Technical Area-V Groundwater (TAVG) Area of Concern (AOC). The Treatability Study will evaluate the effectiveness of bioremediation solution delivery and COC treatment over time. This FIP is designed for SNL/NM work planning and management. It is not intended to be submitted for regulator’s approval. The technical details presented in this FIP are subject to change based on field conditions, availability of equipment and materials, feasibility, and inputs from Sandia personnel and Aboveground Injection System contractor.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2017

Y-12 Groundwater Protection Program Monitoring Optimization Plan for Groundwater Monitoring Wells at the U.S. Department of Energy Y-12 National Security Complex, Oak Ridge, Tennessee

This document is the monitoring optimization plan for groundwater monitoring wells associated with the U.S. Department of Energy (DOE) Y-12 National Security Complex (Y-12) in Oak Ridge, Tennessee. The plan describes the technical approach that is implemented under the Y-12 Groundwater Protection Program (GWPP) to focus available resources on the monitoring wells at Y-12 that provide the most useful hydrologic and groundwater quality monitoring data. The technical approach is based on the GWPP status designation for each well. Under this approach, wells granted “active” status are used by the GWPP for hydrologic monitoring and/or groundwater quality sampling, whereas wells granted “inactive” status are not used for either purpose. The status designation also defines the frequency at which the GWPP will inspect applicable wells, the scope of these well inspections, and extent of any maintenance actions initiated by the GWPP. Details regarding the ancillary activities associated with implementation of this plan (e.g., well inspection) are deferred to the referenced GWPP plans.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2016

Final Work Plan: Targeted Investigation at York, Nebraska

The targeted investigation at York will be implemented in phases, so that data collected and interpretations developed at each stage of the program can be evaluated to guide subsequent phases most effectively. Section 2 of this Work Plan presents a brief overview of the York site, its geologic and hydrologic setting, and the previous CCC/USDA investigations. Section 3, outlines the proposed technical program for the targeted investigation, and Section 4 describes the investigative methods to be employed. A community relations plan is in Section 5, and Section 6 includes health and safety information. In addition to this site-specific Work Plan, the Master Work Plan (Argonne 2002) developed by Argonne for CCC/USDA investigations in Nebraska should be consulted for complete details of the methods and procedures to be used at York.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2017

Advanced Reactor Technologies - Regulatory Technology Development Plan (RTDP)

This DOE-NE Advanced Small Modular Reactor (AdvSMR) regulatory technology development plan (RTDP) will link critical DOE nuclear reactor technology development programs to important regulatory and policy-related issues likely to impact a “critical path” for establishing a viable commercial AdvSMR presence in the domestic energy market. Accordingly, the regulatory considerations that are set forth in the AdvSMR RTDP will not be limited to any one particular type or subset of advanced reactor technology(s) but rather broadly consider potential regulatory approaches and the licensing implications that accompany all DOE-sponsored research and technology development activity that deal with commercial non-light water reactors. However, it is also important to remember that certain “minimum” levels of design and safety approach knowledge concerning these technology(s) must be defined and available to an extent that supports appropriate pre-licensing regulatory analysis within the RTDP. Final resolution to advanced reactor licensing issues is most often predicated on the detailed design information and specific safety approach as documented in a facility license application and submitted for licensing review. Because the AdvSMR RTDP is focused on identifying and assessing the potential regulatory implications of DOE-sponsored reactor technology research very early in the pre-license application development phase, the information necessary to support a comprehensive regulatory analysis of a new reactor technology, and the resolution of resulting issues, will generally not be available. As such, the regulatory considerations documented in the RTDP should be considered an initial “first step” in the licensing process which will continue until a license is issued to build and operate the said nuclear facility. Because a facility license application relies heavily on the data and information generated by technology development studies, the anticipated regulatory importance of key DOE reactor research initiatives should be assessed early in the technology development process. Quality assurance requirements supportive of later licensing activities must also be attached to important research activities to ensure resulting data is usable in that context. Early regulatory analysis and licensing approach planning thus provides a significant benefit to the formulation of research plans and also enables the planning and development of a compatible AdvSMR licensing framework, should significant modification be required.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2016

Livermore Site Spill Prevention, Control, and Countermeasures (SPCC) Plan

This Spill Prevention, Control, and Countermeasure (SPCC) Plan describes the measures that are taken at Lawrence Livermore National Laboratory’s (LLNL) Livermore Site in Livermore, California, to prevent, control, and handle potential spills from aboveground containers that can contain 55 gallons or more of oil. This SPCC Plan complies with the Oil Pollution Prevention regulation in Title 40 of the Code of Federal Regulations (40 CFR), Part 112 (40 CFR 112) and with 40 CFR 761.65(b) and (c), which regulates the temporary storage of polychlorinated biphenyls (PCBs). This Plan has also been prepared in accordance with Division 20, Chapter 6.67 of the California Health and Safety Code (HSC 6.67) requirements for oil pollution prevention (referred to as the Aboveground Petroleum Storage Act [APSA]), and the United States Department of Energy (DOE) Order No. 436.1. This SPCC Plan establishes procedures, methods, equipment, and other requirements to prevent the discharge of oil into or upon the navigable waters of the United States or adjoining shorelines for aboveground oil storage and use at the Livermore Site.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2017

Livermore Site SPCC Plan - Dececember 2017

This Spill Prevention, Control, and Countermeasure (SPCC) Plan describes the measures that are taken at Lawrence Livermore National Laboratory’s (LLNL’s) Livermore Site in Livermore, California, to prevent, control, and handle potential spills from aboveground containers that can contain 55 gallons or more of oil. This SPCC Plan complies with the Oil Pollution Prevention regulation in Title 40 of the Code of Federal Regulations (40 CFR), Part 112 (40 CFR 112) and with 40 CFR 761.65(b) and (c), which regulates the temporary storage of polychlorinated biphenyls (PCBs). This Plan has also been prepared in accordance with Division 20, Chapter 6.67 of the California Health and Safety Code (HSC 6.67) requirements for oil pollution prevention (referred to as the Aboveground Petroleum Storage Act [APSA]), and the United States Department of Energy (DOE) Order No. 436.1. This SPCC Plan establishes procedures, methods, equipment, and other requirements to prevent the discharge of oil into or upon the navigable waters of the United States or adjoining shorelines for aboveground oil storage and use at the Livermore Site.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2018

Aluminum Clad Spent Nuclear Fuel Task 1: Oxyhydroxide Layer Behavior and Chemistry Experimental Test Plan

This document presents the test plan for Task 1 of the Aluminum Clad Spent Nuclear Fuel Long Term Dry Storage Technical Issues Action Plan, which covers aluminum clad spent nuclear fuel (ASNF) fuel that is currently or may in the future be held in dry storage for an extended period. The objectives of the Task 1 test plan are to: 1. Understand how ASNF performs over extended dry storage periods. 2. Understand mechanisms that could alter aluminum hydroxide/oxyhydroxide layers during extended storage. 3. Characterize thickness and growth rates of oxyhydroxide layers based on fuel history and provide anticipated H2 gas generation rates based on chemical corrosion. 4. Characterize materials properties for oxides present on ASNF. 5. Interface with canister modeling activity to deliver degradation rates for package performance for both sealed and vented configurations. 6. Understand implications of higher temperature drying (250°C) on stability in dry storage. This test plan lays out the technical activities that will be performed to achieve the test objectives described above. Experiments will be performed at Idaho National Laboratory in-town facilities. Specimens for testing will include those supplied by Savannah River National Laboratory. Activities will include both experiments and modeling and will coordinate with other tasks within the project.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2018

Aluminum Clad Spent Nuclear Fuel Task 3: Sealed and Vented Systems Episodic Breathing and Gas Generation Modeling Plan

This document presents the test plan for Task 3 of the Aluminum Clad Spent Nuclear Fuel Long Term Dry Storage Technical Issues Action Plan, which covers modeling and predictions of the generations of corrosive gases within both sealed and vented, subject to episodic breathing, storage systems. This includes aluminum clad spent nuclear fuel (ASNF) that is currently or may in the future be held in dry storage for an extended period. The overall objectives of the Task 3 modeling plan are to: 1. Comprehensively model the combined effects of episodic breathing in vented storage systems/canisters using INL INTEC CPP-603 facility as an example. Both bulk gas phase radiolysis reactions and aluminum cladding surface gas generation reactions will be included into a 3-dimensional computational fluid dynamics (CFD) model to model and predict long-term evolutions of the temperature and concentrations of corrosive gases within unsealed canisters subjected to episodic breathing. 2. Comprehensively model sealed and inert canister storage system using DOE standard canister as an example. 3. Closely integrate with Task 1 and Task 2 for identification of main gas-generation reactions and kinetics and provide simulation results back to Task 1 and 2 to further refine experimental designs. This test plan lays out the technical activities that will be performed to achieve the test objectives described above. Simulations will be performed using the Idaho National Laboratory super computer Falcon.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2018

LLNL Livermore Site Spill Prevention, Control, and Countermeasure (SPCC) Plan June 2018

This Spill Prevention, Control, and Countermeasure (SPCC) Plan describes the measures that are taken at Lawrence Livermore National Laboratory’s (LLNL ’s) Livermore Site in Livermore, California, to prevent, control, and handle potential spills from aboveground containers that can contain 55 gallons or more of oil. This SPCC Plan complies with the Oil Pollution Prevention regulation in Title 40 of the Code of Federal Regulations (40 CFR) , Part 112 (40 CFR 112) and with 40 CFR 761.65(b) and (c), which regulates the temporary storage of polychlorinated biphenyls (PCBs). This Plan has also been prepared in accordance with Division 20, Chapt er 6.67 of the California Health and Safety Code (HSC 6.67) requirements for oil pollution prevention (referred to as the Aboveground Petroleum Storage Act [APSA]), and the United States Department of Energy (DOE) Order No. 436.1. This SPCC Plan establishes procedures, methods, equipment, and other requirements to prevent the discharge of oil into or upon the navigable waters of the United States or adjoining shorelines for above ground oil storage and use at the Livermore Site.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2018

Resource Conservation and Recovery Act General Contingency Plan for Hazardous Waste Treatment, Storage, and Disposal Units at the Y-12 National Security Complex. Revision 12

This document, Y/TS-1015/R12, Resource Conservation and Recovery Act General Contingency Plan for Hazardous Waste Treatment, Storage, and Disposal Units at the Y-12 National Security Complex, is for reference purposes. It is a consolidation of the August 10, 2018, versions of Attachment 6, “Contingency Plan,” from Tennessee Hazardous Waste Management Permits TNHW-122 and TNHW-127. It is not intended to supersede any requirements in these permits and any differences are unintentional. The decision to implement this contingency plan, as part of the Emergency Plan, depends upon whether an imminent or actual incident involving a RCRA treatment, storage, or disposal unit could threaten human health or the environment.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗