Simplified Assessment of Radioiodine Biokinetics for Thyroid Cancer Patients: A Practical Approach Using Continuous External Radiation Monitoring.

INTRODUCTION: The biokinetics of radioiodine (RAI) in thyroid cancer patients are complex. This study aims to develop a practical approach for assessing RAI biokinetics to predict patient discharge time and estimate radiation exposure to caregivers. METHODS: We retrospectively reviewed data from patients with differentiated thyroid carcinoma undergoing RAI treatment. Serial radiation dose rates were dynamically collected during hospitalization and fitted to a biexponential model to assess the biokinetic features: RAI uptake fraction of thyroid tissue (Ft) and effective half-life of extra-thyroid tissue (Tet). Correlations with 99mTc thyroid uptake ratio (TcUR), radiation retention ratio (RR), renal function, and body mass index (BMI) were analyzed. RESULTS: Thirty-five patients were enrolled. The derived Ft was 0.08 ± 0.06 and Tet was 7.57 ± 1.45 h. Pearson's correlation analysis revealed a significant association between Ft and both TcUR and RR (p < 0.05), while Tet correlated with renal function and BMI (p < 0.05). CONCLUSION: This novel and practical method assessing RAI biokinetics demonstrates consistency with other parameters and related studies, enhancing the model reliability. It shows promise in predicting an appropriate discharge time and estimating radiation exposure to caregivers, allowing for modifications to radiation protection precautions to follow ALARA principle and minimize the potential risks from radiation exposure.

Establishment of a NORM baseline for selected seafood in the Gulf of Mexico.

Naturally occurring radioactive material was characterized in selected seafood samples from three areas in the Gulf of Mexico. Relatively desirable and abundant fish such as Red Snapper, Red Drum, Northern Whiting, and Spotted Trout as well as oysters were collected and analyzed using gamma spectroscopy to determine the concentration of 228Ra, 226Ra, and 40 K. Average total activity concentration from these radionuclides were 0.9 ±â€¯0.6, 1.6 ±â€¯1.2, and 132 ±â€¯57 Bq kg-1 respectively, in the edible portion of wet weight samples. The results were consistent with previous studies for other bodies of water. A small but statistically significant increase in 226Ra was found in comparison to similar research performed 20 years prior. These measurements provide a reasonable baseline for the examined species from the Gulf of Mexico.

Novel Spiroplasma sp. Isolated From CWD Is an Extreme Bacterial Thermoacidophile That Survives Autoclaving, Boiling, Formalin Treatment, and Significant Gamma Irradiation.

Rapid spreading of chronic wasting disease (CWD) in wildlife and captive cervid populations has exposed lack of progress in dealing with the transmissible spongiform encephalopathies (TSE) of man and animals. Since the TSE transmissible agent was resistant to extremes in environmental and chemical treatments, focus was on an unconventional agent including the prion theory. Recent breakthrough research has revealed consistent isolation of a novel Spiroplasma sp. from TSE-affected tissues that propagates in cell-free media and on agar. Here, we developed a live culture assay to test whether the CWD spiroplasma isolate possessed unconventional biologic properties akin to those of the transmissible agent of TSE. The CWD spiroplasma isolate survived boiling for 1 hour, standard liquid autoclaving, 10% formalin treatment overnight, and gamma irradiation of 20 kGy. The CWD spiroplasma isolate is an acidophile, growing best at pH 2. The biologic resistance of the CWD spiroplasma isolate may be due to unusual phage-like viruses found in the bacterial pellet or to DNA-protein binding. Because the CWD spiroplasma isolate has biologic properties consistent with the causal agent of the TSEs, TSE research focus should be redirected to development of diagnostic tests and preventive vaccines for control of CWD based upon the bacterium.

Determination of Uranium Series Activity Before Secular Equilibrium Is Established.

Timely achievement of uranium series' secular equilibrium is not always feasible. Our objective is to mathematically justify methods for early uranium series gamma spectroscopy measurements that can accurately predict naturally occurring radioactive material equilibrium activities long before equilibrium is established. It was believed that, regardless of prior Rn escape, after sealing a sample for a few hours the activities of Rn, Ra, and U could theoretically be determined with a single measurement of both Pb and Bi. However, when accounting for error, this theory did not work as expected (CV = 14.0 in Ra simulation). A similar approach published by Li et al. in 2015 proved to be much more reliable with the error considered, using Pb activities measured at two different times gave significantly improved results when tested the same way (CV = 0.29 in Ra simulation). Because both Pb and Bi activities are typically available when using gamma spectrometry, we combine these approaches and further increased the accuracy of the calculated activities (CV = 0.21 in Ra simulation).

Visualizing High-Order Decay after Disequilibria.

High-order decay equations are often difficult to study without significant care taken with variables and assumptions. As parent and progeny activities evolve over time, the effects of uncertainties and approximations confound the quality and interpretation of results. Of particular concern is the situation when decay equilibrium has been disturbed and progenies have arbitrary initial activities. To address this, code was created using Wolfram Mathematica to visualize the time-activity plots of the high order progenies of naturally occurring radioactive material after secular equilibrium is disturbed. The Bateman equation for an un-replenished parent was expanded to calculate activity vs. time for up to 13 progenies at different initial activities. The code uses the formula of Skrable et al., without parent production, expanded to the 13th progeny with arbitrary initial concentration. The code calculates and plots activity vs. time; it also reports the cumulative disintegrations of each progeny over a user-specified time period for comparison to counting measurements. The code could also be modified to incorporate additional production or branched decay schemes. We believe this code may be useful to health physicists and is intended to be accessible for anyone's use. This paper presents the code with explanations and examples on how to use it.

Using Geographic Information Systems to Determine Site Suitability for a Low-Level Radioactive Waste Storage Facility.

Radioactive waste is an inevitable product of using radioactive material in education and research activities, medical applications, energy generation, and weapons production. Low-level radioactive waste (LLW) makes up a majority of the radioactive waste produced in the United States. In 2010, over two million cubic feet of LLW were shipped to disposal sites. Despite efforts from several states and compacts as well as from private industry, the options for proper disposal of LLW remain limited. New methods for quickly identifying potential storage locations could alleviate current challenges and eventually provide additional sites and allow for adequate regional disposal of LLW. Furthermore, these methods need to be designed so that they are easily communicated to the public. A Geographic Information Systems (GIS) based method was developed to determine suitability of potential LLW disposal (or storage) sites. Criteria and other parameters of suitability were based on the Code of Federal Regulation (CFR) requirements as well as supporting literature and reports. The resultant method was used to assess areas suitable for further evaluation as prospective disposal sites in Louisiana. Criteria were derived from the 10 minimum requirements in 10 CFR Part 61.50, the Nuclear Regulatory Commission's Regulatory Guide 0902, and studies at existing disposal sites. A suitability formula was developed permitting the use of weighting factors and normalization of all criteria. Data were compiled into GIS data sets and analyzed on a cell grid of approximately 14,000 cells (covering 181,300 square kilometers) using the suitability formula. Requirements were analyzed for each cell using multiple criteria/sub-criteria as well as surrogates for unavailable datasets. Additional criteria were also added when appropriate. The method designed in this project proved to be sufficient for initial screening tests in determining the most suitable areas for prospective disposal (or storage) sites. Cells above 90%, 95%, and 99% suitability include respectively 404, 88, and 4 cells suitable for further analysis. With these areas identified, the next step in siting a LLW storage facility would be on-site analysis using additional requirements as specified by relevant regulatory guidelines. The GIS based method provides an easy, economic, efficient and effective means in evaluating potential sites for LLW storage facilities where sufficient GIS data exist.

The use of photographic film to pinpoint accelerator beam losses.

Following removal of a superconducting wiggler that has a maximum magnetic-field of 7 T in a high-energy synchrotron facility, sufficient lead shielding was placed upstream of the removal point in the normal-conducting electron storage ring to account for any radiation sources from the upstream components. As is customary in such cases, when vacuum has been breached, there is a period of time required for vacuum re-conditioning of the ring. During this re-conditioning phase, poor vacuum contributes to gas bremsstrahlung formation that typically is visualized as an increase in overall radiation exposure from standard operating conditions. However, in this case, new radiation patterns emerged and persisted throughout the re-commissioning phase. Subsequently, additional shielding was then placed upstream but still failed to resolve the source of radiation. The radiation source point consisted of two distinct components: a point parallel to the position originally covered by the wiggler and a strong forward-directed peak (i.e., bremsstrahlung). The only feedback mechanism to track the beam position is the beam position monitors (BPM's). BPM's were located forward and aft of the parallel source point. The BPM's suggested that the beam was in the correct position. To investigate the elevated radiation level, commercial photographic film was used as a monitoring ruler and the focal point of the radiation source was clearly identified using this novel approach. The silver halide grain contained within the film emulsion possessed sufficient cross section and was activated from Ag to Ag, which has a half-life of 2.39 min and emits easily detectable radiation. Further, the exposed film is ready for reuse after 25 min due to the short half-life of Ag. The proposed method proved to be an easy, economic, and effective approach to rapidly and qualitatively identify the location of the beam losses.

Interleukin-15 receptor is essential to facilitate GABA transmission and hippocampal-dependent memory.

Interleukin-15 (IL15) is a cytokine produced by normal brain, but the functions of the IL15 system in normal adults are not yet clear. The hypothesis that the hippocampal IL15 system is essential for memory consolidation was tested by use of IL15Ralpha knock-out mice in behavioral, biochemical, immunohistological, and electron microscopic analyses. The knock-out mice showed deficits in memory, determined by the Stone T-maze and fear conditioning. In their hippocampi, the concentration of GABA was significantly lower. There were region-specific changes of the GABA-synthesizing enzyme glutamic acid decarboxylase (GAD), with increased GAD-67-immunopositive interneurons in the stratum oriens of the CA1 region of the hippocampus, accompanied by nonsignificant reduction of GAD-67 synapses in the CA3 region. Western blotting showed an increase of GAD-65, but not GAD-67, in the hippocampal homogenate. The ultrastructure of the hippocampus remained intact in the knock-out mice. To further test the hypothesis that IL15 directly modulates GABA turnover by reuptake mechanisms, the dose-response relationship of IL15 on (3)H-GABA uptake was determined in two neuronal cell lines. The effective and nontoxic dose was further used in the synaptosomal uptake studies. IL15 decreased the uptake of (3)H-GABA in synaptosomes from the forebrain of wild-type mice. Consistent with this, IL15Ralpha knock-out mice had increased synaptosomal uptake of (3)H-GABA. Overall, the results show novel functions of a unique cytokine in normal hippocampal activity by regulating GABA transmission.

Dose rates from a cobalt-60 pool irradiator measured with Fricke dosimeters.

This project used Fricke dosimeters to determine the dose rates at multiple locations in a Co pool irradiator. Fricke dosimetry is widely accepted as a chemical dosimetry method to measure radiation absorbed dose due to its simple recipe, linear response, wide dose range, good reproducibility, ease of measurements, and low operational cost. Calibration measurements were used to determine a molar extinction coefficient of 2,185 +/- 14 L mol cm at 303 nm and 25 degrees C; the molar extinction coefficient is comparable to values from the published literature. The Fricke dosimeters measured the dose rate of a National Institute of Standards and Technology-traceable calibrated gamma radiation field to within 1.2% of the calibrated value. The pool irradiator had the largest dose rates near the middle of the torpedo, with dose rate decreasing as one moved towards the bottom or top of the torpedo. The dose rate across the torpedo is not uniform at each level, because of the non-uniform distribution of source activity around the irradiator. Relative error in the Fricke dosimeter dose rate measurements ranged from 1-2%. The dose rates mapped in this project can be used to plan bulk sample irradiation, although dosimetry measurements should still be obtained to confirm delivered dose.

Lessons learned in responding to and recovering from a fire incident.

A review is presented of the response by emergency personnel, including radiation safety staff, to a fire incident in an academic radiation facility. The handling of the incident during the incident itself as well as during post-fire cleanup and recovery efforts are described. The preparation of a variety of written notification reports and the physical and procedural corrective actions taken as a result of the fire are also discussed.

Simulating gaseous 131I distribution in a silver zeolite cartridge using sodium iodide solution.

131I is one of the most significant gaseous fission products in a nuclear power plant. Because of its high volatility at room temperature, iodine can be easily inhaled by radiation workers following release of radioiodine into the atmosphere. The thyroid gland is the critical organ for iodine uptake and is subject to radioiodine carcinogenesis. Hence, monitoring systems are provided in nuclear power plants to sample and evaluate ambient air for gaseous radioiodine content. Due to a highly preferential retention efficiency for iodine gas compared to noble gases, silver zeolite cartridges are typically used in nuclear power plants to adsorb gaseous iodine for sampling purposes. To obtain accurate measurements, preparation of a proper calibration standard to simulate the gaseous radioiodine distribution in the cartridge is essential. This project developed a silver zeolite cartridge calibration standard that uses sodium iodide solution to simulate gaseous iodine distribution. This calibration standard appears to satisfactorily simulate the gaseous radioiodine distribution in the silver zeolite cartridge.

Evaluation of a radiation survey training video developed from a real-time video radiation detection system.

This project incorporates radiation survey training into a real-time video radiation detection system, thus providing a practical perspective for the radiation worker on efficient performance of radiation surveys. Regular surveys to evaluate radiation levels are necessary not only to recognize potential radiological hazards but also to keep the radiation exposure as low as reasonably achievable. By developing and implementing an instructional learning system using a real-time radiation survey training video showing specific categorization of work elements, radiation workers trained with this system demonstrated better radiation survey practice.

Determination of the attenuation properties of laboratory gloves exposed to an ultraviolet transilluminator.

The transmission of ultraviolet radiation (UVR) from an ultraviolet transilluminator through three types of laboratory gloves (latex, nitrile, vinyl) was determined using two independent methods. First, transmittance was measured with a radiometer equipped with UVA and actinic UV detectors. Second, a spectrophotometer was used to determine the UVR transmittance vs. wavelength (250-440 nm); this data was then used to compute the effective attenuation of the glove material. The average UVA percent transmittance using the radiometer method with an unstretched glove was 73.4%, 0.18%, and 1.10% for vinyl, nitrile, and latex, respectively. The average actinic percent transmittance for an unstretched glove was 13.3%, 0.015%, and 0.024% for vinyl, nitrile, and latex, respectively. Slight increases in UVR transmittance resulted from stretching the gloves by 30% or wetting them with saline. Six hours of UVR exposure decreased transmittance of vinyl gloves and increased transmittance by latex gloves. Results from the spectrophotometer method and radiometer methods of determining UVR transmittance agreed that vinyl gloves had the highest transmittance; however, the spectrophotometer method greatly overestimated UV glove attenuation due to the effect of light scattering by the glove material. The study suggests that in some circumstances, vinyl gloves will provide inadequate protection against workplace ultraviolet radiation.

Validation of the integrity of a HEPA filter system.

The objective of this study was to establish a delayed air sampling method to verify the integrity of an existing HEPA filter system in a ventilated fume hood. (238U,232Th)O2 microspheres were generated to fabricate cement nuclear fuel pellets in a HEPA-filtered hood. To comply with the air effluent concentration limits by NRC, the capture efficiency of the HEPA filter was examined. An in-line isokinetic air sampling system was installed downstream of the HEPA filter. Utilizing a gas flow proportional counter, 212Pb was used as a surrogate to indicate any possible penetration of the (238U,232Th)O2 particles through the HEPA filter. Based on the experimental results, this delayed sampling method proved to be an easy and effective way to validate the integrity of the HEPA filter.