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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 919 records · Page 51
All sourcesNASA NTRSDOE OSTI
DOE OSTI2017

Ladtap XL Version 2017: A Spreadsheet For Estimating Dose Resulting From Aqueous Releases

LADTAP XL© is an EXCEL© spreadsheet used to estimate dose to offsite individuals and populations resulting from routine and accidental releases of radioactive materials to the Savannah River. LADTAP XL© contains two worksheets: LADTAP and IRRIDOSE. The LADTAP worksheet estimates dose for environmental pathways including external exposure resulting from recreational activities on the Savannah River and internal exposure resulting from ingestion of water, fish, and invertebrates originating from the Savannah River. IRRIDOSE estimates offsite dose to individuals and populations from irrigation of foodstuffs with contaminated water from the Savannah River. In 2004, a complete description of the LADTAP XL© code and an associated user’s manual was documented in LADTAP XL©: A Spreadsheet for Estimating Dose Resulting from Aqueous Release (WSRC-TR-2004-00059) and revised input parameters, dose coefficients, and radionuclide decay constants were incorporated into LADTAP XL© Version 2013 (SRNL-STI-2011-00238). LADTAP XL© Version 2017 is a slight modification to Version 2013 with minor changes made for more user-friendly parameter inputs and organization, updates in the time conversion factors used within the dose calculations, and fixed an issue with the expected time build-up parameter referenced within the population shoreline dose calculations. This manual has been produced to update the code description, verification of the models, and provide an updated user’s manual. LADTAP XL© Version 2017 has been verified by Minter (2017) and is ready for use at the Savannah River Site (SRS).

61 RADIATION PROTECTION AND DOSIMETRY↗
DOE OSTI2017

RCT: Module 2.03, Counting Errors and Statistics, Course 8768

Radiological sample analysis involves the observation of a random process that may or may not occur and an estimation of the amount of radioactive material present based on that observation. Across the country, radiological control personnel are using the activity measurements to make decisions that may affect the health and safety of workers at those facilities and their surrounding environments. This course will present an overview of measurement processes, a statistical evaluation of both measurements and equipment performance, and some actions to take to minimize the sources of error in count room operations. This course will prepare the student with the skills necessary for radiological control technician (RCT) qualification by passing quizzes, tests, and the RCT Comprehensive Phase 1, Unit 2 Examination (TEST 27566) and by providing in the field skills.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
DOE OSTI2017

Sampling and Analysis Plan for Verification Sampling of LANL-Derived Residual Radionuclides in Soils within Tract A-18-2 for Land Conveyance

Public Law 105-119 directs the U.S. Department of Energy (DOE) to convey or transfer parcels of land to the Incorporated County of Los Alamos or their designees and to the Department of Interior, Bureau of Indian Affairs, in trust for the Pueblo de San Ildefonso. Los Alamos National Security is tasked to support DOE in conveyance and/or transfer of identified land parcels no later than September 2022. Under DOE Order 458.1, Radiation Protection of the Public and the Environment (O458.1, 2013) and Los Alamos National Laboratory (LANL or the Laboratory) implementing Policy 412 (P412, 2014), real property with the potential to contain residual radioactive material must meet the criteria for clearance and release to the public. This Sampling and Analysis Plan (SAP) is a second investigation of Tract A-18-2 for the purpose of verifying the previous sampling results (LANL 2017). This sample plan requires 18 projectspecific soil samples for use in radiological clearance decisions consistent with LANL Procedure ENV-ES-TP-238 (2015a) and guidance in the Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM, 2000). The sampling work will be conducted by LANL, and samples will be evaluated by a LANL-contracted independent lab. However, there will be federal review (verification) of all steps of the sampling process.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2017

Uranium Holdup Survey Program (UHSP) Lean Improvement Project

This report discusses the UHSP monitoring program, a radioactive material accounting process and its purpose. The systematic approach to implementing Lean principles, determining key requirements, root causes of variation and disruption that interfere with program efficiency and effectiveness. Preexisting issues within the UHSP are modeled to illustrate the impact that they have on the large and extensive systems.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2018

2012 Canadian RDD Field Trials: Quick Summary for DOE Modelers

A series of three explosive RDD experiments was conducted in 2012 by Defense Research and Development Canada (DRDC) and collaborating organizations from Canada, the US and the UK. Trial details and measurement data were provided by Lorne Erhardt of DRDC. In order to characterize the dispersion and deposition of radioactive material from an RDD, a source of La- 140 (which has a half-life of 1.6781 days) was dispersed by detonation of 0.2 kg of high explosive in each of the three tests. Measurements of the subsequent dispersion and deposition were made using multiple experimental techniques.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2017

Evaluation of Preventative Radiological/Nuclear Detector Archetypes to Validate Repurpose to the Consequence Management Mission

In the event of a radiological or nuclear emergency involving a large-scale release of radioactive material, local responders would be the primary means to perform radiation measurements to assess impacts and issue protective action recommendations for the responders and the public. Over the first 24-36 hours, Federal responders and resources will deploy to augment the local efforts, and if necessary, provide extensive radiation monitoring and assessment capabilities coordinated by the Department of Energy-led Federal Radiological Monitoring and Assessment Center and Federal Emergency Management Agency-led Multiagency Coordination Group. Unless Federal resources happen to be deployed at the moment an incident occurs, such as a preventative radiological/nuclear detection mission for a scheduled special event, the local response to an incident will commence and persist for many hours with no on-scene Federal support. For a catastrophic incident, such as a nuclear detonation or severe reactor accident, the local jurisdictions may not have a full range of adequate supplies of health physics instruments and personnel dosimetry. Therefore early in a crisis, the local responders will inevitably conduct their operations with the radiation detection and dosimetry capabilities that they have available until additional resources and support are requested and arrive. Most of the radiation detection instruments currently fielded at the local level are carried by law enforcement personnel and are designed for interdiction missions - referred to here as preventative radiological/nuclear detection (PRND) instruments. This study investigated how this PRND equipment can be repurposed in consequence management (CM) missions.

61 RADIATION PROTECTION AND DOSIMETRY↗
DOE OSTI2018

Process for Conducting a Cost Benefit Analysis for New Radiation Portal Monitors

The Domestic Nuclear Detection Office (DNDO) has deployed over 1,400 radiation portal monitors (RPMs) around the United States to enhance border security. DNDO is now considering deployment of a newer generation of RPMs, intended to have equal or better sensitivity but a considerably lower nuisance alarm rate due to Naturally Occurring Radioactive Material (NORM) that is common in the stream of commerce. If the nuisance alarm rate is sufficiently reduced at a site, US Customs and Border Protection (CBP) may be able to reduce the staffing necessary to respond to nuisance alarms generated by the RPMs. This document provides an overview of some possible processes for conducting a cost benefit analysis to place a reliable dollar amount on the value of these new systems. While there is no hard and fast guide for conducting a cost benefit analysis, an austere method is provided for quick estimating. Two robust methods are also provided, one taking guidance from an Office of Management and Budget circular and the other from the Government Accountability Office.

99 GENERAL AND MISCELLANEOUS↗
DOE OSTI2018

Establish Fuel Qualification Expectations

The objective of this white paper is to provide an overview of the state of knowledge regarding issues associated with fuel qualification for a liquid-fueled molten salt reactor. The overview consists of fuel qualification expectations for heterogeneous reactors—conventional light water reactors, plus advanced reactors such as sodium fast reactors and modular high-temperature gas-cooled reactors—which consider the mechanical behavior of the fuel itself, interaction between fuel and its cladding, behavior of the cladding, and structural behavior of fuel assemblies. Fuel qualification expectations for molten salt reactors are viewed in contrast to the fuel qualification for heterogeneous reactors in that the fuel is liquid (molten) and there is no accumulation of mechanical effects such as stress, creep, or swelling. However, the liquid fuel salts do accumulate fission products, corrosion byproducts, and buildup of actinides which impact the chemistry of the fuel salt and thermal-physical properties that may impact the ability to remove heat from the core and retain radioactive materials in the fuel salt. Finally, the role of the US Department of Energy in research on tri-structural-isotropic and metal fuel for advanced reactors for fuel qualification purposes is briefly discussed as a potential model for the Department’s research to gather quality chemical and thermal-physical property data necessary to qualify MSR fuel performance under normal and accident conditions.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2015

RPM Deployment Requirements for State and Local Use

Radiation Portal Monitors (RPMs) are instruments that passively detect gamma and neutron radiation for screening people, objects, cargo and transports. RPMs have been deployed around the U.S. and other international borders, for the interdiction of radioactive materials that are deemed as threats. Instruments such as RPMs need to be deployed and operated in a specified manner in order to correctly execute their purpose. The deployment and operation of RPMs can be based on national and international standards and specifications. This document provides guidance on the appropriate deployment of RPMs for State and Local Government use, specifically for Ludlum Technology (Sweetwater, TX) model 4500 RPMs provided by the Department of Homeland Security.

98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗
DOE OSTI2018

Lab touts plutonium storage best practices for Japanese visitors

Engineers from Japan's Oarai Research and Development Center's Plutonium Fuel Research Facility visited TA-55's Plutonium Facility 4 (PF-4) recently to learn best practices from the Laboratory for safely packaging and storing plutonium and other radioactive materials.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2018

GALE 3.1 Verification Report

This report is documentation of the verification activities that have been performed on GALE-3.1 to ensure that the codes meet the requirements and specifications set forth by NRC and that the code meets its intended purpose. Additional benchmark tests for GALE-3.1 are documented in Appendix A of NUREG-0016, Revision 2 for GALE-BWR 3.1 and Appendix A of NUREG-0017, Revision 2 for GALE-PWR 3.1. These activities are done in accordance with the GALE Software Quality Assurance Plan (PNNL-24249) and the GALE Configuration Management & Maintenance Plan (PNNL-24250). These two plans meet the requirements set for by both PNNL software quality assurance requirements and the NRC’s Software Quality Assurance Program and Guidelines (NUREG/BR-0167). The verification activities are documented to conform to Level 2 requirements of NUREG/BR-0167. Verifications were performed for both GALE-3.1 BWR and GALE-3.1 PWR Codes. The GALE 3.1 BWR and PWR codes are computerized mathematical models for calculating the releases of radioactive material in gaseous and liquid effluents. These computer codes are tools which can be used to determine conformance with the requirements of Appendix I to Title 10, Part 50 of the Code of Federal Regulations (10 CFR 50).

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2018

Dose Rate Evaluation for the ES-3100 Package with HEU Content Using MCNP, ADVANTG, Monaco, and MAVRIC

This paper presents a comparative study of dose rate calculations for the ES-3100 package with highly enriched uranium (HEU) content for different source configurations using computer codes: (1) MCNP; (2) Automated Variance Reduction Generator (ADVANTG)/MCNP; (3) Monaco; and (4) Monaco with Automated Variance Reduction using Importance Calculations (MAVRIC). The Model ES-3100 package was developed at the Y-12 National Security Complex for domestic and international transportation of Type B fissile radioactive material. In this study, six different source configurations (i.e., solid cylinder, cylindrical hemi-shell, cylindrical shell, rectangular plate, cylindrical rod, or cylindrical segment form) having 36 kg of HEU metal inside the package containment vessel (based on configurations in the ES-3100/HEU safety analysis report for packaging) are evaluated. Dose rates at the package surfaces and 1 m from the package surfaces are calculated for these different source configurations. MCNP and Monaco cases are run without any biasing options to accelerate the convergence. Consistent Adjoint Driven Importance Sampling (CADIS) and Forward-Weighted CADIS (FW-CADIS) methods developed at the Oak Ridge National Laboratory are implemented in ADVANTG/MCNP and MAVRIC codes to accelerate the convergence. ADVANTG generates variance reduction parameters using Denovo code, and MCNP is used with the variance reduction parameters to accelerate the convergence. MAVRIC uses Denovo code to construct an importance map and a biased source distribution that are supplied to Monaco to accelerate the Monte Carlo simulation. The FW-CADIS option in ADVANTG and MAVRIC is used to accelerate the convergence in this study. The accelerated convergence cases (ADVANTG/MCNP and MAVRIC) are about 100 times faster with 100 times less particle simulation than those cases run without biasing options (analog MCNP and analog Monaco). The MCNP, ADVANTG/MCNP, Monaco, and MAVRIC calculated dose rates at the package surfaces and at 1 m from the package surfaces for the different source configurations are compared and are found to be in general agreement.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2017

FUEL PERFORMANCE MODELING OF REACTIVITY-INITIATED ACCIDENTS USING THE BISON CODE

The Fukushima Daiichi nuclear accidents in 2011 sparked considerable interest in the U.S. to develop new nuclear fuel with enhanced accident tolerance. Throughout the development of these new fuel concepts they will be extensively modeled using specialized computer codes and experimentally tested for a variety of different postulated accident scenarios. One accident scenario of interest, reactivity-initiated accident, is a nuclear reactor event involving a sudden increase in fission rate that causes a rapid increase in reactor power and temperature of the fuel which can lead to the failure of the fuel rods and a release of radioactive material. The focus of this work will be on the fuel performance modeling of reactivity-initiated accidents using the BISON code being developed at Idaho National Laboratory. The overall goal of this work is to provide the best possible modeling predictions for future experimental tests. Accurate predictive capability modeling using BISON is important for safe operation of these tests and provides a cheaper alternative to the expensive experiments.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2018

LANL Meteorological Program Improvements to Continue Meeting Annual 90 Percent Data Recovery Requirements

Recently, the Los Alamos National Laboratory (LANL) Environmental Protection and Compliance (EPC) and Safety Basis (SB) Divisions have collaborated on the latter’s use of the meteorological data as input into dispersion analysis used to determine receptor dose consequences as a result of an accidental release of radioactive material from a LANL nuclear facility. The dose consequence calculations are part of the Department of Energy (DOE) approved Documented Safety Analysis (DSA), which describes the processes, hazards, and controls of nuclear operations within certain facilities at LANL. The DOE approved DSA is required according to Title 10 of the Code of Federal Regulations Part 830 (10CFR830), “Nuclear Safety Management” and is developed in accordance with the 10CFR830, Subpart B “Safety Basis” safe harbor methodology identified as DOE Standard 3009-94, or successor document (DOE STD 3009-94).

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2017

Nanodilatometry to measure length changes due to radiation damage in naturally aged Pu specimens

Radioactive materials are self-damaging, which over time, impacts many physical and mechanical properties. One well documented effect is a change in density due to swelling from the accumulated damage to the atomic structure and in the case of α-decay, helium in-growth. In some materials, void growth has been shown to develop, where after a period of incubation, the material swells at a rapid rate, with deleterious effects. A second contrasting effect occurs in Ga stabilized δ-Pu, which is thermodynamically unstable and can partially transform to α’-Pu, a phase 20% denser and thus will cause contraction. Such changes can be observed through several experimental techniques. A change in length, measured by dilatometry is perhaps the simplest to understand, and best characterization of bulk. This report describes the development and testing of a dilatometer capable of measuring length changes resulting from radiation damage in standard weapons grade plutonium over a reasonable time scale (~ 1 month) and the preliminary results of measurements on plutonium samples. The dilatometer has the ability to measure swelling in samples between 0-100°C, a temperature range of programmatic interest.

36 MATERIALS SCIENCE↗
DOE OSTI2018

Gamma-ray raster imaging with robotic data collection. FY18 report

This project has developed an alternative imaging capability for measuring radioactive materials in situ. This approach uses a robotic-mounted gamma-ray detector which can move around an area of interest, sampling the space at a high frequency. By rastering across the area, an image can be created with no collimation and a high efficiency. A regression model was developed to map out material distribution as the robot moves through the environment. An informative path planning algorithm was also developed to maximize the information collected throughout the movement path. The use of a robotic mount allows data collection for long periods of time unattended, and it will also eliminate uncertainties in positioning typically introduced by personnel. This approach will be particularly relevant for gloveboxes, shielded cells, or process piping which may have complex, non-uniform distributions of material.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
DOE OSTI2018

2017 Annual Site Environmental Report

Los Alamos National Laboratory’s (the Laboratory’s) annual site environmental reports are prepared annually by the Laboratory’s environmental organizations, as required by U.S. Department of Energy Order 231.1B, Administrative Change 1, Environment, Safety, and Health Reporting, and Order 458.1, Administrative Change 3, Radiation Protection of the Public and the Environment. The following chapters in this report discuss our success in complying with environmental laws, regulations, and orders (Chapter 2, Compliance Summary); how we manage the Laboratory’s environmental performance (Chapter 3, Environmental Programs); how we monitor for air emissions of radioactive materials and climate conditions (Chapter 4, Air Quality); how we monitor for effects of Laboratory operations on groundwater quality (Chapter 5, Groundwater Monitoring); how we monitor the movement of chemicals and radionuclides by storm water runoff and the levels of chemicals and radionuclides in deposited sediment (Chapter 6, Watershed Quality); how we monitor for the presence, levels, and effects of chemicals and radionuclides in plants, animals, soil, and vegetation (Chapter 7, Ecosystem Health); and finally, what radionuclide dose or risk from chemical exposure members of the public may experience as a result of Laboratory operations (Chapter 8, Public Dose and Risk Assessment).

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2018

A Micro-Thermionic Ionization Source for Chemical Detection

The major goal of this project was to develop an ionization-based detector that could be integrated into the portable gas chromatography systems currently produced by Defiant Technologies. This new detector would allow Defiant to analyze a broader range of analytes and enter new markets. There was also an interest in testing the new ionization source in an ion mobility spectrometer (IMS) that is produced by Sandia National Laboratories. Not only could this eliminate the need for a radioactive material in the IMS, it would offer Defiant the opportunity to add a whole new product line to their chemical analysis systems. Significant progress was made in the development of a thermionic ionization source (TIS) and detector. Using a MEMs heater was an attractive concept, but it proved to be an unfruitful approach because of the fragility of the devices at elevated temperatures. A rugged alternative heater was developed using nichrome wire and alumina tubes. These heaters are simple to make, and, for low quantity production, will be considerably cheaper to construct than MEMs devices. This work has provided a firm basis for follow-on projects. There is now a solid concept for constructing heater elements where, prior to this work, there was only the hope that MEMs heaters would work. In addition, the electrometer that was developed works better than the commercial rack-mounted system that was originally used in this study. Overcoming these two obstacles provides a clear technical approach for product development. There will be follow on efforts at Defiant Technologies to refine the development of the thermal ionization detector. Designs are being made to combine the TIS and electrometer electronics into a single package with a simple-to-replace TIS element. Further work will also focus on integrating this new detector into portable gas chromatography products and testing to optimize the performance.

47 OTHER INSTRUMENTATION↗