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At least 541 records · Page 30

The Role of Indian Tribes in the Safe, Secure, and Routine Transportation of Spent Nuclear Fuel and High-Level Radioactive Waste - 19463

Far too often federally recognized Indian Tribes are the last stakeholders invited to the table to discuss a particular issue with potentially wide-ranging impacts. Indian tribes were the first governments on this continent. With respect to the future transportation of spent nuclear fuel (SNF) or high-level radioactive waste (HLW), Indian tribes are potentially impacted in a myriad of ways: economics, cultural, environmental, health and safety. Yet few regulators fully understand and appreciate the legal and political standing of Indian tribes. This paper will examine the ways in which Indian tribes must be involved with the planning for safe, secure and routine SNF and HLW shipments and the ways in which the federal government is obligated to involve tribes. Indian tribes are similar to states in that they are responsible for the health and safety of its members (which they themselves define). Tribes, like states, make, implement, interpret, and enforce laws, and provide public services - healthcare, public education, social services, drug treatment, public safety and emergency management, transportation, managing natural resources, public housing, and environmental and cultural preservation. Many tribes also operate economic enterprises - manufacturing, farming, forestry, and gaming. The most basic principle of Indian law is the principle of 'sovereignty,' that is, an Indian tribe possesses all the powers of any sovereign state. Tribal governments are not subject to state or local jurisdiction but are subject to federal jurisdiction. The tribes enjoy a government-to-government relationship (and expectation) with the federal government (i.e., agencies, like the Department of Energy, the Nuclear Regulatory Commission). Of paramount concern to Indian tribes is the doctrine of Trust Responsibility, the general principle that the federal government's conduct 'in dealing with the Indians should therefore be judged by the most exacting fiduciary standards.' With respect to SNF/HLW this means that the federal government has an obligation (or a Trust Responsibility) to ensure that tribal people, lands and resources are protected. Equally important is the expectation that federal agencies will work with the Indian tribes on a government-to-government basis before undertaking any action with potential negative consequences on the tribe's people, land or resources. The concept of government-to-government consultation between Indian tribes and the United States is long standing and well recognized. As expressed in Executive Order 13175, 'Consultation and Coordination with Indian Tribal Governments': 'Consultation - Each federal agency must have an accountable process to ensure meaningful and timely input by tribal officials in the development of regulatory policies that have tribal implications.' The purpose of consultation is to ensure that Indian tribes are consulted before government officials make decisions that may have an impact on their lives and territories. The three agencies involved with SNF and HLW transportation - the US Department of Transportation (DOT), the US Nuclear Regulatory Commission (NRC), and the US Department of Energy (DOE) - have had various degrees of success with respect to direct consultation with Indian tribes. Given that there is plenty of lead-time before the first shipments commence, there should be ample time to develop a strategy for ensuring that tribes are equal partners when planning and preparing for shipments of SNF and HLW to the first interim storage facility. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Panel Session 110B: US DOE High-Level Radioactive Waste (HLW) Interpretation

This panel focused on the US DOE High-Level radioactive Waste (HLW) definition interpretation. Discussion integrated topics such as the issuance of the HLW interpretation Federal Registration Notice, the status of the draft Environmental Assessment that analyzes the treatment and commercial disposal of up to 10,000-gallons of SRS Defense Waste Processing Facility recycle wastewater in South Carolina, and the path forward. Panelists with presentations: Status on the Environmental Assessment for the Commercial Disposal of Defense Waste Processing Facility Recycle Wastewater from SRS (Theresa Kliczewski); Enhancing Stakeholder Engagement on the HLW interpretation (Kara Colton, Rick McLeod); Technical Aspects of Potential Disposal of SRS DWPF Recycle Wastewater (Kent Rosenberger)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Borehole Disposal of Radioactive Waste in Israel - 20388

Israel is assessing borehole disposal of radioactive waste. With limited geological options for disposal, intermediate-depth borehole disposal is being considered in the arid Yamin Plain region of the northeastern Negev desert at depths of several hundred meters below ground surface in the vadose zone. Unlike deep borehole disposal of several kilometers, which relies on emplacement below the depth of recirculating groundwater, the safety case for intermediate-depth borehole disposal relies more on the aridity of the vadose zone, the robustness of the waste package, and the other engineered barriers (e.g., seals, backfill materials) in the disposal borehole. As a tradeoff, the shallower depth may allow the use of a larger diameter borehole than would be possible for a deeper borehole. To study the suitability of the Yamin Plain region for borehole disposal, a small-diameter characterization borehole is being planned to retrieve core samples and to better understand the vadose zone geomechanical and hydrogeochemical properties and percolation flux. The information from the characterization borehole will inform the safety case, and together with performance assessment analyses will help to identify key areas of uncertainty and guide future research and development activities aimed at demonstrating the feasibility of the intermediate-depth borehole disposal concept in Israel. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Experimental and Computational Investigation of the Emission of Radioactive Products from Irradiated Fuel of Fast Sodium-Cooled Reactor

The key experimental and computational studies of the emission of long-lived radioactive fission products and actinides from uranium dioxide irradiated in BN-600 into sodium and the gas phase in the range 150–800°C, performed on the experimental bench at the Leipunskii Institute of Physics and Power Engineering, are presented. The results of measurements of the properties of aerosols of certain radioactive fission products formed upon heating of irradiated nuclear fuel in sodium are presented. The experimental results are of interest for evaluating the radiation impact of reactor facilities on workers and the public during beyond design basis accidents.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Computational Errors in the Calculation of Long Radioactive Decay Chains

For safety security of objects utilizing atomic energy, the effect of numerical errors on the calculation of the activity and integrals of the activity in time when using Bateman’s formula and Siewers’ algorithm to calculate radioactive decay chains is investigated. The smallest errors obtain when using Siewers’ algorithm and Bateman’s formula together with long arithmetic. It is shown that the standard calculations of radioactive decay chains according to Bateman’s formula with double precision lead to significant errors. However, these errors have almost no effect on the dose characteristics of mixtures of radionuclides. The analysis is based on data contained in ICRP Publication No. 107.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Stable and radioactive carbon isotope partitioning in soils and saturated systems: a reactive transport modeling benchmark study

This benchmark provides the first rigorous test of a three-isotope system [ 12 C, 13 C, and 14 C] subject to the combined effects of radioactive decay and both stable equilibrium and kinetic fractionation. We present a series of problems building in complexity based on the cycling of carbon in both organic and inorganic forms. The key components implement (1) equilibrium fractionation between multiple coexisting carbon species as a function of pH, (2) radioactive decay of radiocarbon with associated mass-dependent speciation demonstrating appropriate correction of the Δ 14 C value in agreement with reporting convention, and (3) kinetic stable isotope fractionation due to the oxidation of organic carbon to inorganic forms as a function of time and space in an open, through-flowing system. Participating RTM codes are CrunchTope, ToughReact, Hytec, and The Geochemist’s Workbench. Across all problem levels, simulation results from all RTMs demonstrate good agreement.

58 GEOSCIENCES↗

Thermal and Thermophysical Properties of the Radioactive Graphite–Inert Gas System in Heating. Computer Experiment

Consideration has been given to the capabilities of the TERRA software system for modeling thermodynamically the heating of a radioactive graphite–inert gas system in a nuclear reactor. As a result of such modeling, the authors have determined processes occurring in the reactor with the involvement of Eu, Pu, and U actinoids during the heating of the radioactive graphite–argon system at pressures of 10{sup 5} and 10{sup 6} Pa, and also equilibrium constants of chemical reactions and the influence of pressure on them. The thermophysical properties of the system have been studied, and the influence of pressure on its specific volume, the heat capacity, and the molar mass of a gas phase and the weight fraction of a condensed phase has been established.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Quantification techniques of mass-separation and ion yield for the detection of radioactive isotopes

This research demonstrates two methods of quantifying isotope separation efficiency using an inductively coupled plasma mass spectrometer. One method measured the accumulated charge on a conductive collection substrate in real-time while the second method performed a chemical dissolution of the substrate with subsequent post-processing and analysis. Our previous results demonstrated and compared these methods with a multi-element standard of stable isotopes. This research applies these methods to quantifying radioactive isotopes utilizing measurements of the stable isotope at the same mass-to-charge ratio. The mass-separated radioactive isotope were fission products produced from thermal neutron irradiation of a highly enriched 235U foil. The two methods are explained and the results of this new separation methodology are compared to available cumulative fission yields.

Dion, Michael P.↗

Using radioactive material to evaluate decontamination of contaminated electronics

Electronic materials are used everywhere and can get easily contaminated by their use in the field/laboratory. The goal of this project was to use radioactive material to track the effectiveness of a cleaning procedure using an off-the-shelf cleaning gel. Radioactive potassium bromide (KBr) was used as a model contaminant in four contamination scenarios to gauge the effectiveness of a cleaning gel in the decontamination of contaminated raspberry pi’s. Finally, the investigated decontamination technique was found to be 75–97% effective in removing contamination from the tested electronic devices. 95% of the contaminated electronic devices retained their functionality post-decontamination.

38 - RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCL↗

Experiments with a prototype titanium hot cavity surface ionization source intended for electromagnetic separation of radioactive samarium and other lanthanide elements

This paper reports experimental results of a prototype titanium surface ionization source. For the first time, a lanthanide ion beam has been produced with a surface ionizer composed completely of titanium metal. Titanium does not readily activate with neutron irradiation. This offers the potential for inserting an ion source made of titanium directly into a reactor with a pre-loaded non-radioactive lanthanide target. This seamlessly integrates target irradiation with isotope separation, eliminating post irradiation sample manipulation. Samarium ion beam currents up to 960 nA have been produced in an off-line test bench equipped with rudimentary beam optics. This is a crucial step toward the development of an ionization source adopted for the electromagnetic isotope separator (EMIS) facility, which has been designed for high throughput separations of radioactive 153 Sm and other lanthanides of interest in the field of nuclear medicine. The ion current and important factors affecting the performance of the ion source, such as the ionizer temperature and thermal gradient, are discussed. Lastly, the experimental results are presented together with a discussion of future modifications to optimize the overall surface ionization source performance.

07 ISOTOPE AND RADIATION SOURCES↗

Detection of Sleeping Beauty transposition in the genome of host cells by non-radioactive Southern blot analysis

The Sleeping Beauty transposon (SB-Tn) system is being used widely as a DNA vector for the delivery of therapeutic transgenes, as well as a tool for the insertional mutagenesis in animal models. In order to accurately assess the insertional potential and properties related to the integration of SB it is essential to determine the copy number of SB-Tn in the host genome. Recently developed SB100X transposase has demonstrated an integration rate that was much higher than the original SB10 and that of other versions of hyperactive SB transposases, such as HSB3 or HSB17. In this study, we have constructed a series of SB vectors carrying either a DsRed or a human β-globin transgene that was encompassed by cHS4 insulator elements, and containing the SB100X transposase gene outside the SB-Tn unit within the same vector in cis configuration. These SB-Tn constructs were introduced into the K-562 erythroid cell line, and their presence in the genomes of host cells was analyzed by Southern blot analysis using non-radioactive probes. Many copies of SB-Tn insertions were detected in host cells regardless of transgene sequences or the presence of cHS4 insulator elements. Interestingly, the size difference of 2.4 kb between insulated SB and non-insulated controls did not reflect the proportional difference in copy numbers of inserted SB-Tns. We then attempted methylation-sensitive Southern blots to assess the potential influence of cHS4 insulator elements on the epigenetic modification of SB-Tn. Our results indicated that SB100X was able to integrate at multiple sites with the number of SB-Tn copies larger than 6 kb in size. In addition, the non-radioactive Southern blot protocols developed here will be useful to detect integrated SB-Tn copies in any mammalian cell type.

60 APPLIED LIFE SCIENCES↗

Development of iron phosphate ceramic waste form to immobilize radioactive waste solution

The objective of this research was to develop an iron phosphate ceramic (IPC) waste form using converter slag obtained as a by-product of the steel industry as a source of iron instead of conventional iron oxide. Both synthetic off-gas scrubber solution containing technetium-99 (or Re as a surrogate) and LiCl-KCl eutectic salt, a final waste solution from pyrochemical processing of spent nuclear fuel, were used as radioactive waste streams. The IPC waste form was characterized for compressive strength, reduction capacity, chemical durability, and contaminant leachability. Compressive strengths of the IPC waste form prepared with different types of waste solutions were 16 MPa and 19 MPa for LiCl-KCl eutectic salt and the off-gas scrubber simulant, respectively, which meet the minimum compressive strength of 3.45 MPa (500 psi) for waste forms to be accepted into the radioactive waste repository. The reduction capacity of converter slag, a main dry ingredient used to prepare the IPC waste form, was 4,136 meq/kg by the Ce(IV) method, which is much higher than those of the conventional Fe oxides used for the IPC waste form and the blast furnace slag materials. Average leachability indexes of Tc, Li, and K for the IPC waste form were higher than 6.0, and the IPC waste form demonstrated stable durability even after 63-day leaching. In addition, the Toxicity Characteristic Leach Procedure measurements of converter slag and the IPC waste form with LiCl-KCl eutectic salt met the universal treatment standard of the leachability limit for metals regulated by the Resource Conservation and Recovery Act. This study confirms the possibility of development of the IPC waste form using converter slag, showing its immobilization capability for radionuclides in both LiCl-KCl eutectic salt and off-gas scrubber solutions with significant cost savings.

converter slag↗

A compact ultra-clean system for deploying radioactive sources inside the KamLAND detector

We describe a compact, ultra-clean device used to deploy radioactive sources along the vertical axis of the KamLAND liquid-scintillator neutrino detector for purposes of calibration. The device worked by paying out and reeling in precise lengths of a hanging, small-gauge wire rope (cable); an assortment of interchangeable radioactive sources could be attached to a weight at the end of the cable. All components exposed to the radiopure liquid scintillator were made of chemically compatible UHV-cleaned materials, primarily stainless steel, in order to avoid contaminating or degrading the scintillator. To prevent radon intrusion, the apparatus was enclosed in a hermetically sealed housing inside a glove box, and both volumes were regularly flushed with purified nitrogen gas. Finally, an infrared camera attached to the side of the housing permitted real-time visual monitoring of the cable’s motion, and the system was controlled via a graphical user interface.

42 ENGINEERING↗

Chalcogenide Aerogels as Sorbents for Radioactive Iodine

Iodine ( 129 I and 131 I) is one of the radionuclides released in nuclear fuel reprocessing and poses a risk to public safety due to its involvement in human metabolic processes. In order to prevent the release of hazardous radioactive iodine into the environment, its effective capture and sequestration is pivotal. In the context of finding a suitable matrix for capturing radioactive iodine, several sulfidic chalcogels were explored as iodine sorbents including NiMoS 4 , CoMoS 4 , Sb 4 Sn 3 S 12 , Zn 2 Sn 2 S 6 , and K 0.16 CoS x (x = 4–5). All of the chalcogels showed high uptake, reaching up to 225 mass % (2.25 g/g) of the final mass owing to strong chemical and physical iodine–sulfide interactions. Analysis of the iodine-loaded specimens revealed that the iodine chemically reacted with Sb 4 Sn 3 S 12 , Zn 2 Sn 2 S 6 , and K 0.16 CoS x to form the metal complexes SbI 3 , SnI 4 , and, KI, respectively. In this study, the NiMoS 4 and CoMoS 4 chalcogels did not appear to undergo a chemical reaction with iodine since iodide complexes were not observed with these samples. Once heated, the iodine-loaded chalcogels released iodine in the temperature range of 75 to 220 °C, depending on the nature of iodine speciation. In the case of Sb 4 Sn 3 S 12 and Zn 2 Sn 2 S 6 , iodine release was observed around 150 °C mainly in the form of SnI 4 and SbI 3 , respectively. The NiMoS 4 , CoMoS 4 , and K 0.16 CoS x released elemental iodine at ~75 °C, which is consistent with physisorption. Preliminary investigations on consolidation of iodine-loaded Zn 2 Sn 2 S 6 chalcogel with Sb 2 S 3 as a glass forming additive produced glassy material whose iodine content was around 25 mass %.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗

A comparison of machine learning methods to classify radioactive elements using prompt-gamma-ray neutron activation data

The detection of illicit radiological materials is critical to establishing a robust second line of defence in nuclear security. Neutron-capture prompt-gamma activation analysis (PGAA) can be used to detect multiple radioactive materials across the entire Periodic Table. However, long detection times and a high rate of false positives pose a significant hindrance in the deployment of PGAA-based systems to identify the presence of illicit substances in nuclear forensics. In the present work, six different machine-learning algorithms were developed to classify radioactive elements based on the PGAA energy spectra. The model performance was evaluated using standard classification metrics and trend curves with an emphasis on comparing the effectiveness of algorithms that are best suited for classifying imbalanced datasets. We analyse the classification performance based on Precision, Recall, F1-score, Specificity, Confusion matrix, ROC-AUC curves, and Geometric Mean Score (GMS) measures. The tree-based algorithms (Decision Trees, Random Forest and AdaBoost) have consistently outperformed Support Vector Machine and K-Nearest Neighbours. Based on the results presented, AdaBoost is the preferred classifier to analyse data containing PGAA spectral information due to the high recall and minimal false negatives reported in the minority class.

97 MATHEMATICS AND COMPUTING↗

Cosmic radioactivity and INTEGRAL results

Gamma-ray lines from radioactive decay of unstable isotopes co-produced by nucleosynthesis in massive stars and supernova have been measured since more than thirty years. Over the past ten years, INTEGRAL complemented the first sky survey made by COMPTEL. The {sup 26}A1 isotope with 1 My decay time had been first direct proof of currently-ongoing nucleosynthesis in our Galaxy. This has now become a tool to study the ∼My history of specific source regions, such as massive-star groups and associations in nearby regions which can be discriminated from the galactic-plane background, and the inner Galaxy, where Doppler shifted lines add to the astronomical information about bar and spiral structure. Recent findings suggest that superbubbles show a remarkable asymmetry, on average, in the spiral arms of our galaxy. {sup 60}Fe is co-produced by the sources of {sup 26}A1, and the isotopic ratio from their nucleosynthesis encodes stellar-structure information. Annihilation gamma-rays from positrons in interstellar space show a puzzling bright and extended source region central to our Galaxy, but also may be partly related to nucleosynthesis. {sup 56}Ni and {sup 44}Ti isotope gamma-rays have been used to constrain supernova explosion mechanisms. Here we report latest results using the accumulated multi-year database of INTEGRAL observations, and discuss their astrophysical interpretations, connecting to other traces of cosmic radioactivity and to other cosmic messengers.

79 ASTRONOMY AND ASTROPHYSICS↗

Automated management of radioactive sources in Saudi Arabia

For usage of radioactive substances, any facility has to register and take license from relevant authority of the country in which such facility is operating. In the Kingdom of Saudi Arabia (KSA), the authority for managing radioactive sources and providing licenses to organizations for its usage is the National Center of Radiation Protection (NCRP). This paper describes the system that automates registration and licensing process of the National Center of Radiation Protection. To provide 24×7 accesses to all the customers of NCRP, system is developed as web-based application that provide facility to online register, request license, renew license, check request status, view historical data and reports etc. and other features are provided as Electronic Services that would be accessible to users via internet. The system also was designed to streamline and optimize internal operations of NCRP besides providing ease of access to its customers by implementing a defined workflow through which every registration and license request will be routed. In addition to manual payment option, the system would also be integrated with SADAD (online payment system) that will avoid lengthy and cumbersome procedures associated with manual payment mechanism. Using SADAD payment option license fee could be paid through internet/ATM machine or branch of any designated bank, Payment will be instantly notified to NCRP hence delay in funds transfer and verification of invoice could be avoided, SADAD integration is discussed later in the document.

07 ISOTOPE AND RADIATION SOURCES↗

Effect of geometrical configuration of radioactive sources on radiation intensity in beta-voltaic nuclear battery system: A preliminary result

It is known that one main problem in the application of beta-voltaic nuclear battery system is its low efficiency. The efficiency of the beta-voltaic nuclear battery system mainly depends on three aspects: source of radioactive radiation, interface between materials in the system and process of converting electron-hole pair to electric current in the semiconductor material. In this work, we show the effect of geometrical configuration of radioactive sources on radiation intensity of beta-voltaic nuclear battery system.

07 ISOTOPE AND RADIATION SOURCES↗