Nuclear waste Educator's workshop: What and how do we teach about nuclear waste?

A workshop was held at the Massachusetts Institute of Technology (MIT) on July 25th and 26th, 2022. The objective was to develop a blueprint for educating next-generation engineers and scientists about nuclear waste management and disposal, which requires knowledge from diverse disciplines, including nuclear, chemical, civil, environmental, and geological science and engineering. The 49 participants included university professors, researchers, industry experts, and government officials from different areas. First, we have developed a list of key fundamental knowledge on waste management and disposal across the nuclear fuel cycle. In addition, we discussed strategies on how to teach students with diverse backgrounds through innovative teaching strategies as well as how to attract students into this area. Through the workshop, we identified the critical needs to (1) develop community resources for nuclear waste education; (2) synthesize historical perspectives, including past contamination and the management of general hazardous waste; (3) emphasize a complete life-cycle perspective, including proper waste management as the key component for energy sustainability; (4) teach students how to communicate about the key facts and risks to technical and non-technical audiences; and (5) accelerate the use of the state-of-art-technologies to attract and retain a young workforce. Furthermore, we aim to build a diverse, inclusive community that supports students in developing their own narratives about nuclear waste, particularly in recognizing that antagonistic views have been important to improving safety and protecting public health and the environment.

Radiological and non-radiological leaching assessment of alkali-activated materials containing ground granulated blast furnace slag and phosphogypsum.

Alkali-activated materials (AAMs) based on ground granulated blast furnace slag (GGBFS) and phosphogypsum (PG) were investigated in order to quantify leaching of naturally occurring radionuclides (NOR) and inorganic non-radiological elements according to an up-flow percolation column test as described in CEN/TS 16637-3. Gamma spectroscopy and neutron activation analysis (NAA) were applied for radiological characterization, inductively coupled plasma optical emission spectrometry (ICP-OES) and ion-chromatography (IC) for chemical characterization. Upon leaching, 238U, 226Ra, 210Pb, and 228Ra were retained very well. Both for 232Th and 40K, a decrease in activity concentration was observed due to leaching and their release was influenced by the use of different alkali activators, which was also the case for the leaching of non-radiological elements. Only a small amount of Al (0.5-0.8%), Ca (0.1-0.2%) and Si (0.1-0.3%) was mobilized, while highest release was observed for K (56-94%), Na (49-88%) and S (71-87%). At first glance, drinking water is not endangered by leaching of NOR following the requirements of the European Drinking Water Directive. From the results for porosity, obtained with mercury intrusion porosimetry (MIP), it was concluded that both the porosity and formation of multiple leachable and non-leachable complexes are determining factors for the release of elements from AAMs.

Verification of I-125 brachytherapy source strength for use in radioactive seed localization procedures.

A general-purpose nuclear medicine dose calibrator was assessed as a potential replacement for a dedicated air-communicating well-type ionization chamber (brachytherapy source strength verification instrument) for (125)I seed source strength verification for radioactive seed localization, where less stringent accuracy tolerances may be acceptable. The accuracy, precision and reproducibility of the dose calibrator were measured and compared to regulatory requirements. The results of this work indicate that a dose calibrator can be used for (125)I seed source strength verification for radioactive seed localization.

Determination of the internal exposure hazard from plutonium work in an open front hood.

The particle size and quantity of a plutonium dioxide surrogate escaping an open front hood during routine work was measured. Aerosols were collected using a cascade impactor, and the amount of surrogate on each stage of the impactor was measured using neutron activation analysis. The aerodynamic mass median diameter of particles in the breathing zone of a worker was found to be 0.35 ± 5.1 µm. During a 2-h period when normal work activities were mimicked, an average of 3% of the material or 11.13 ± 0.54 µg escaped the hood. This was calculated to be equivalent to 10,000 ± 487 Bq (²³9Pu). The activity in the breathing zone of the worker is estimated, based on other research, to be 36 times less than this, or approximately 280 Bq. Worker occupancy factors were considered and a committed effective dose equivalent of 5 mSv was calculated. The cost-benefit analysis showed the use of the open front hood as a reasonable protective measure. Although worker exposure may approach the International Commission on Radiological Protection limit, the cost of the ergonomic injuries caused by work in a glove box is 5,000 times greater than the dose received by the worker. Protective measures such as respiratory protection should be evaluated on a case by case basis to keep worker exposure as low as reasonably achievable.

Evaluation of flow scintillation analysis for the determination of Sr-90 in bioassay samples.

An automated procedure for the determination of (90)Sr was adapted from existing methods of flow scintillation analysis (FSA) for use on aqueous samples with low levels of activity (<1000 dpm per sample). This technique employs high-performance extraction chromatography (HPEC) and an on-line liquid scintillation counter to provide automated separation and subsequent detection of (90)Sr. The total analysis time is 30 min per sample. Dilute urine samples, spiked with (90)Sr, were also processed by this method to test the application of this technique for bioassay monitoring.

Development of composite materials for non-leaded gloves for use in radiological hand protection.

Lead is a hazardous material, and the U.S. Congress has mandated the rapid reduction of all hazardous waste generation as a matter of national policy. With the large amount of plutonium handling in numerous projects including the development of mixed oxide (MOX) fuel, 238Pu power sources, etc., hand glove protection for the emitted alpha, beta, and low energy photons is an important issue. Leaded gloves are the prime shields used for radiological hand protection. U.S. Department of Energy laboratories require a substitute material for the lead oxide in the gloves as a way to reduce mixed waste. To solve this problem, a new blend of non-hazardous materials that have the same radiological properties and approximately the same cost of production have been investigated. The investigations have produced alternative materials using calculations and experiments. The selection of the constituent compounds for the new composite materials was based on the k-absorption edge energy of the main constituent element(s) in the compounds. The formulations of these composites were fashioned on the principle of blending Neoprene rubber formulation with several constituent compounds. Calculations based on the Lambert-Beer attenuation law together with the mass attenuation coefficient values from the XCOM cross section database program were used to determine the transmission fractions of these proposed composite materials. Selected composite materials that compared favorably with the leaded-Neoprene were fabricated. These fabricated composite materials were tested with attenuation experiments and the results were in excellent agreement with the calculations using the Lambert-Beer attenuation law.

Ambient silver concentration anomaly in the Finnish Arctic lower atmosphere.

Mean silver concentrations in weekly particle samples collected at Kevo, northern Finland, were determined for the period of October 1964-March 1978 by neutron activation analysis. Two distinct periods were observed in the silver concentration levels over this time frame. During 1964-1970, mean weekly silver concentration levels were found in the range of 0.01-190 ng/m3 with an arithmetic mean of 2.19 ng/m3. A few very high silver concentration levels (>10 ng/m3) were observed in this period, some of which simultaneously occurred with some of the highest bromine and iodine concentration levels. During 1971-1978, silver concentration levels were in the range of 0.02-0.89 ng/m3 with a mean value of 0.09 ng/m3. The observed concentration levels in the later period matched well the data from the early 1990s reported at Sevettijärvi, northern Finland, about 60 km east of Kevo. Data analysis, historical records for this region, and residence time analysis (RTA) using wind back-trajectories show that occasional smelting of silver-rich Norilsk ores at the Nikel smelter, Kola Peninsula, was probably a significant contributor to elevated mean silver concentration levels during 1964-1970. RTA alone was not able to unambiguously identify the most probable source region for highest silver impacts at Kevo due to the weekly integrated nature of the samples collected. Critical examination of wind back-trajectories (24 per day) for specific high silver, bromine, and iodine concentration weeks was carried out to supplement the ensemble RTA analysis (2 back-trajectories per day). The supplemental back-trajectory analysis revealed that deposition of the smelter component silver as well as the sea components (bromine and iodine) could occur together at Kevo during these weekly sampling periods. The study implies that data from weekly integrated samples are insufficiently time-resolved for RTA methods alone to unambiguously resolve the sources contributing to ambient atmospheric concentrations at Kevo, Finland.

Source-Receptor Modeling Using Trace Metals in Aerosols Collected at Three Rural Canadian Great Lakes Sampling Stations.

High-volume air samplers were used to collect aerosol samples on Whatman 41 air filters at the Canadian air sampling stations Burnt Island, Egbert, and Point Petre. The samples were analyzed for trace elements by neutron activation analysis. Air concentrations of over 30 trace elements were determined. Factor analysis, elemental ratios, and enrichment factor analysis were used to determine source-receptor relationships at the three different sites. Factor analysis exhibited trends that indicate oil and coal combustion, road salt, mining, incineration, and smelting as anthropogenic sources to aerosols of the rural Great Lakes. Elemental ratios showed that the Na to Cl ratio in the Great Lakes aerosol is similar to that found in sea water. Enrichment factor analysis revealed elements with non-crustal sources including the elements Ag, As, Br, Cl, Cu, I, In, Sb, Se, Sn, W, and Zn.