Studies on the Radioactive Dating of the Lunar Surface Final Report
Remotely controlled rare gas analyzer with chemical reaction as energy source considered for radioactive dating of lunar surface
RADIOACTIVE DATING↗
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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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Simulated radioactivity.
Simulated radioactive decay experiment using random number generator or set of random numbers
SIMULATION↗
2010 Annual NESHAPs Radioactive Air Annual Meeting Hosted in conjunction with the 55th HPS Meeting June 29, 2010
This is a compilation of selected abstracts and presentations/posters from the 2010 Annual Health Physics Society (HPS) meeting held in Salt Lake City, UT and the presentations and information presented at the annual radioactive air NESHAP meeting held in conjunction with the HPS meeting. (CD-ROM)
Environmental Monitoring↗
RECLAMATION OF RADIOACTIVE MATERIAL PACKAGING COMPONENTS
Radioactive material packages are withdrawn from use for various reasons; loss of mission, decertification, damage, replacement, etc. While the packages themselves may be decertified, various components may still be able to perform to their required standards and find useful service. The Packaging Technology and Pressurized Systems group of the Savannah River National Laboratory has been reducing the cost of producing new Type B Packagings by reclaiming, refurbishing, and returning to service the containment vessels from older decertified packagings. The program and its benefits are presented.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Direct reaction measurements with a (132)Sn radioactive ion beam
The (d,p) neutron transfer and (d,d) elastic scattering reactions were measured in inverse kinematics using a radioactive ion beam of {sup 132}Sn at 630 MeV. The elastic scattering data were taken in a region where Rutherford scattering dominated the reaction, and nuclear effects account for less than 8% of the elastic scattering cross section. The magnitude of the nuclear effects, in the angular range studied, was found to be independent of the optical potential used, allowing the transfer data to be normalized in a reliable manner. The neutron-transfer reaction populated a previously unmeasured state at 1363 keV, which is most likely the single-particle 3p{sub 1/2} state expected above the N=82 shell closure. The data were analyzed using finite-range adiabatic-wave calculations and the results compared with the previous analysis using the distorted-wave Born approximation. Angular distributions for the ground and first-excited states are consistent with the previous tentative spin and parity assignments. Spectroscopic factors extracted from the differential cross sections are similar to those found for the one-neutron states beyond the benchmark doubly magic nucleus {sup 208}Pb.
72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS↗
Modeling most likely pathways for smuggling radioactive and special nuclear materials on a worldwide multi-modal transportation network
Nuclear weapons proliferation is an existing and growing worldwide problem. To help with devising strategies and supporting decisions to interdict the transport of nuclear material, we developed the Pathway Analysis, Threat Response and Interdiction Options Tool (PATRIOT) that provides an analytical approach for evaluating the probability that an adversary smuggling radioactive or special nuclear material will be detected during transit. We incorporate a global, multi-modal transportation network, explicit representation of designed and serendipitous detection opportunities, and multiple threat devices, material types, and shielding levels. This paper presents the general structure of PATRIOT, all focuses on the theoretical framework used to model the reliabilities of all network components that are used to predict the most likely pathways to the target.
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗
S&TR Preview: Radioactive Materials Detection and Response
Advanced technology and more realistic training go together to improve searches for and responses to radioactive materials.
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
Multi-phased Approach for Detection Systems and Measures for Nuclear and other Radioactive Material Out of Regulatory Control
The Office of Nuclear Incident Policy and Cooperation and the Office of Nuclear Security Deterrence and Detection at the U.S. Department of Energy, National Nuclear Security Administration provide a multi-phased approach for detection systems and measures for nuclear and other radioactive material out of regulatory control in cargo shipments. The approach is designed using best practices to deter, detect, interdict, characterize, adjudicate, and recover illicit radiation sources. Two case studies will be presented which demonstrate the multi-phased approach to nuclear security.
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
Radiological Impact Associated to Technologically Enhanced Naturally Occurring Radioactive Materials (TENORM) from Coal-Fired Power Plants Emissions - 13436
Certain materials used and produced in a wide range of non-nuclear industries contain enhanced activity concentrations of natural radionuclides. In particular, electricity production from coal is one of the major sources of increased human exposure to naturally occurring radioactive materials. A methodology was developed to assess the radiological impact due to natural radiation background. The developed research was applied to a specific case study, the Sines coal-fired power plant, located in the southwest coastline of Portugal. Gamma radiation measurements were carried out with two different instruments: a sodium iodide scintillation detector counter (SPP2 NF, Saphymo) and a gamma ray spectrometer with energy discrimination (Falcon 5000, Canberra). Two circular survey areas were defined within 20 km of the power plant. Forty relevant measurements points were established within the sampling area: 15 urban and 25 suburban locations. Additionally, ten more measurements points were defined, mostly at the 20-km area. The registered gamma radiation varies from 20 to 98.33 counts per seconds (c.p.s.) corresponding to an external gamma exposure rate variable between 87.70 and 431.19 nGy/h. The highest values were measured at locations near the power plant and those located in an area within the 6 and 20 km from the stacks. In situ gamma radiation measurements with energy discrimination identified natural emitting nuclides as well as their decay products (Pb-212, Pb-2142, Ra-226, Th-232, Ac-228, Th-234, Pa-234, U- 235, etc.). According to the results, an influence from the stacks emissions has been identified both qualitatively and quantitatively. The developed methodology accomplished the lack of data in what concerns to radiation rate in the vicinity of Sines coal-fired power plant and consequently the resulting exposure to the nearby population. (authors)
54 ENVIRONMENTAL SCIENCES↗
Study on release and transport of aerial radioactive materials in reprocessing plants
The release and transport characteristics of radioactive materials at a boiling accident of the high active liquid waste (HALW) in a reprocessing plant have been studied for improving experimental data of source terms of the boiling accident. In the study, a heating test and a thermogravimetry and differential thermal analysis (TG-DTA) test were conducted. In the heating test using a simulated HALW, it was found that ruthenium was mainly released into the air in the form of gas and that non-volatile elements were released into the air in the form of mist. In the TG-DTA test, the rate constants and reaction heat of thermal decomposition of ruthenium nitrosyl nitrate were obtained from TG and DTA curves. (authors)
37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗
A new code for spectrometric analysis for environmental radiological surveillance on monitors focused on gamma radioactivity on aerosols
pGamma is a code developed by the NERG group of the Technical University of Catalonia - Barcelona Tech for the analysis of gamma spectra generated by the Equipment for the Continuous Measurement and Identification of Gamma Radioactivity on Aerosols with Paper Filter developed for our group and Raditel Servies company. Nowadays the code is in the process of adaptation for the monitors of the Environmental Radiological Surveillance Network of the Local Government of Catalonia (Generalitat of Catalonia), Spain. The code is a Spectrum Analysis System, it identifies the gamma emitters on the spectrum, determines its Concentration of Activity, generates alarms depending on the Activity of the emitters and generates a report. The Spectrum Analysis System includes a library with emitters of interest, NORM and artificial. The code is being used on the three stations with the aerosol monitor of the Network (Asco and Vandellos, near both Nuclear Power Plants and Barcelona). (authors)
54 ENVIRONMENTAL SCIENCES↗
Comparing the Predicted Neutron Yields and Radioactivities of Two Accelerators in Taiwan: 235-MeV Proton Cyclotron and 3-GeV Electron Synchrotron - Paper 27
Two major accelerator facilities in Taiwan are about to open. The first proton treatment center equipped with a 235 MeV proton cyclotron and four gantry rooms in Linkou Chang Gung Memorial Hospital is currently under beam commissioning and clinical trials are expected to start soon. In addition, the second light source facility, named Taiwan Photon Source (TPS), in National Synchrotron Radiation Research Center is now approaching its final assembly and will be ready for beam commissioning in this year. These two facilities mark significant milestones in accelerator development and application of Taiwan. Operation of these accelerators could potentially produce intense secondary neutrons and serious material activation. Both issues are crucial and must be carefully evaluated for the purpose of radiation safety, especially in a densely populated hospital or in a crowded user experimental floor. Monte Carlo simulations with evaluated cross sections or benchmarked nuclear models are considered as the most reliable method for accelerator shielding designs or related analyses. This study predicted and compared the magnitudes of potential neutron production and induced radioactivity due to the operation of these two accelerators. For conservative consideration, the primary particle energy and full beam output were assumed to hit a thick target for maximum radiation production. In order to ensure the quality of predictions, much effort has been devoted to associated benchmark calculations, targeting those bombardment experiments involving with the same particle types and similar beam energies and targets. (authors)
43 PARTICLE ACCELERATORS↗
Proton nuclear magnetic resonance (1H NMR) of flammable organic chemicals in radioactive high–level supernatant waste at the Savannah River Site (SRS)
The Savannah River Site stores approximately 36 million gallons of radioactive and hazardous waste that contains approximately 245 million curies. The waste is sent through various chemical processes to reduce its volume and to separate various components. The facility plans to replace formic acid (a chemical used to reduce soluble mercury) with glycolic acid. Recycle solution with glycolate may flow back to the tank farm, where the glycolate can generate hydrogen gas by thermal and radiolytic mechanisms. The current analytical method for detecting glycolate (ion chromatography) in supernatant requires a large dilution to reduce interference from the nitrate anions. Hydrogen nuclear magnetic resonance is an analytical method that requires less sample dilution. It takes advantage of the CH 2 group in glycolate. Liquid samples were spiked with four different levels of glycolate to build a calibration line, as it is recommended in the standard addition method. The detection and quantitation limits determined were 1 and 5 ppm, respectively, for 32 scans, which is well below the process limit of 10 ppm. In one test, 800 scans of a supernatant spiked with 1 ppm glycolate resulted in a -CH 2 peak with a signal-to-noise ratio of 36.
1H↗
Spectral Methods of Remote-Sensing Monitoring of Radioactive Substances and Toxic Chemicals
The physical principles of passive and active methods of remote-sensing monitoring of radioactive substances and toxic chemicals in accidental emissions (leaks) at nuclear fuel cycle objects are examined. The analytical possibilities of the most sensitive methods of remote-sensing monitoring, which are based on the advances made in UV and microwave range radiometry, laser IR-absorption spectroscopy, laser-induced fluorescence, and laser spark emission spectrometry, are discussed. The prospects for the development of spectral methods of remote-sensing monitoring in different ranges are analyzed.
22 GENERAL STUDIES OF NUCLEAR REACTORS↗
Intercalation of Nanopolyaniline with Nanobentonite and Manganese Oxide Nanoparticles as a Novel Nanocomposite to Remediate Cobalt/Zinc and Their Radioactive Nuclides {sup 60}Co/{sup 65}Zn
A novel nanocomposite based on the combination of nanobentonite with nanopolyaniline and nanomanganese oxide (N-Bent–NPANI–NMn{sub 3}O{sub 4}) was synthesized and investigated to extract Co/Zn ions from water using batch technique and {sup 60}Co/{sup 65}Zn radionuclides from radioactive wastewater using column techniques. Characterization was established by High resolution-transmission electron microscopy (HR-TEM), Scanning electron microscope, X-ray diffraction (XRD), thermal gravimetric analysis (TGA) and Fourier transform infrared spectrophotometer. The image of HR-TEM indicated that the produced nanocomposite was ranged from 59.07 to 83.38 nm. Solution pH, time of reaction, amount of solid and metal concentration, all of these parameters were inspected and optimized as fundamental factors during the extraction process. The obtained results implied that the ideal conditions for extraction were pH 6 and 7, reaction time 10 and 20 min, for Co and Zn ions, respectively. The highest removal capacities were found 255.28 and 202.22 mg g{sup −1} for Co and Zn, respectively by using 5 mg nanocomposite. Excellent recoveries were obtained as 94.0–94.5% and 92.0–93.0% for removal of Co–{sup 60}Co and of Zn–{sup 65}Zn ions, respectively from the examined samples. Graphical Abstract: .
77 NANOSCIENCE AND NANOTECHNOLOGY↗
Investigation of candidates for reactor produced radioactive materials in support of radiological training exercises
Bromine-82, Potassium-42 and Copper-64 have been successfully adopted as radioactive surrogates for outdoor large area contamination training. The goal of this project was to discover new materials that could supplement potassium bromide (KBr) and copper pellets in radiological dispersal device (RDD) training events to reduce the down time of the training fields and to broaden the toolbox of the RDD surrogate training event program at Idaho National Laboratory. Of the ten different materials investigated, sodium nitrite, gallium metal, and gallium oxide presented the greatest promise as potential materials to replace potassium bromide in RDD training events.
38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗
Evaluation of mitigation strategies for radioactive fission gases in fluoride-salt-cooled high-temperature reactors
Here, the Fluoride-salt-cooled High-temperature Reactor (FHR) is a promising Generation IV nuclear reactor due to its improved safety design, near atmospheric working pressure, and high electric power conversion efficiency. However, control of radioactive fission gases, such as tritium, is a critical issue in FHRs due to the significantly larger production rate and potentially larger leakage rate of tritium compared to those in Light Water Reactors (LWRs). Therefore, this study proposes two mitigation strategies for tritium in FHRs: Double-Wall Heat eXchanger with a Tritium Carrier (DWHX-TC) option and Single-Wall Heat eXchanger with a Tritium Barrier (SWHX-TB) option. For the DWHX-TC option, two tube surface configurations, i.e., plain and fluted tubes, and four tritium carriers, i.e., helium, FLiBe, FLiNaK, and KF-ZrF 4 , are initially considered, among which the best tube configuration and promising tritium carrier are then selected and used for design optimization of the DWHX. For the SWHX-TB option, two cases, tritium barriers with and without cracks, are investigated in this study. In addition, the two mitigation strategies are evaluated by an in-house, one-dimensional, coupled HEat and MAss Transfer (HEMAT) code developed to predict the leakage rate of tritium in nuclear systems. Our analysis shows that (1) a double-wall configuration using fluted tubes as both the inner and outer tubes is better than other double-wall configurations investigated; (2) helium, as a tritium carrier, is superior to other candidates, including FLiBe, FLiNaK, and KF-ZrF 4 ; (3) the leakage rate of tritium (into the atmosphere) is reduced from 3400 Ci/day, taking the Advanced High-Temperature Reactor (AHTR) as a reference, to 4.0 Ci/day for an optimum design of the DWHX-TC option using helium as the tritium carrier and 1.7 Ci/day for an optimum design of the SWHX-TB option using 30-µm thick silicon carbide (SiC) as the tritium barrier (no cracks); and (4) potential cracks in tritium barriers may significantly deteriorate mass transfer performance of the SWHX-TB option. For example, a cracking rate of 0.1% leads to an increase of 694.1% in the leakage rate under the conditions investigated.
22 GENERAL STUDIES OF NUCLEAR REACTORS↗
Chromatographic separation of radioactive noble gases from xenon
The Large Underground Xenon (LUX) experiment operates at the Sanford Underground Research Facility to detect nuclear recoils from the hypothetical Weakly Interacting Massive Particles (WIMPs) on a liquid xenon target. Liquid xenon typically contains trace amounts of the noble radioactive isotopes 85 Kr and 39 Ar that are not removed by the in situ gas purification system. The decays of these isotopes at concentrations typical of research-grade xenon would be a dominant background for a WIMP search exmperiment. To remove these impurities from the liquid xenon, a chromatographic separation system based on adsorption on activated charcoal was built. 400 kg of xenon was processed, reducing the average concentration of krypton from 130 ppb to 3.5 ppt as measured by a cold-trap assisted mass spectroscopy system. Finally, a 50 kg batch spiked to 0.001 g/g of krypton was processed twice and reduced to an upper limit of 0.2 ppt.
38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗