Stopping criteria for neutron spectrum unfolding algorithms.

Neutron spectrum unfolding is a crucial process in radiation protection and dosimetry. Unfolding codes using iterative algorithms require a criterion to stop the iterations. One approach often relies on the Root Mean Square Error (RMSE) criterion to assess the convergence of iterative algorithms. The aim of this work is to present a new criteria: Average Ratio Scaled (AVGS) and Relative Change in AVGS (dAVGS) to address specific challenges associated with RMSE. Extensive validation tests were conducted, covering a range of scenarios with results showing high level of agreement between the unfolded spectra and the reference.

Obesity attenuates the beneficial effect of an intrauterine infusion of autologous platelet-rich plasma during in vitro fertilization.

OBJECTIVE: To assess how obesity, normal weight (NW) versus overweight/obese (OW/OB), impacts platelet-rich plasma's (PRP) effectiveness during in vitro fertilization and how obesity affects platelets during the menstrual cycle. METHODS: Endometrial mean thickness (EMT), embryo implantation, and clinical pregnancy were assessed using a self-controlled retrospective study that enrolled 59 patients with two failed cycles and treated with autologous PRP (three-dose scheme). The NHANES dataset was used to assess platelet changes during the menstrual cycle, using the mean platelet volume to platelet count ratio (MPR) index. The COSINOR packages for R were used to determine rhythmicity. RESULTS: PRP treatments significantly improved the EMT (2.5 ± 1.4 mm, P<0.001), unaffected by obesity. After the PRP treatment, one patient spontaneously became pregnant; therefore, 58 patients underwent embryo transfer (62 cycles), of which in 39 cycles the embryos implanted (63.9%). This was a significant improvement from their previous cycle (vs. 22.6%, P<0.001). Clinical pregnancy also improved with the PRP treatment over the previous cycle (57.4% vs. 16.1%, P<0.001). When stratified by obesity, there was an appreciable decrease in embryo implantation and clinical pregnancy rates for the OW/OB group; nevertheless, the PRP treatment significantly improved embryo implantation and clinical pregnancy (P<0.05). A rhythm was observed with the MPR index (P<0.05) only for the NW group, suggesting that the platelets normally fluctuate during the menstrual cycle. CONCLUSION: PRP improved embryo implantation and clinical pregnancy rates; however, these beneficial effects were attenuated by obesity. PRP presumptively promoted a change in the uterine environment to mimic the normal findings associated with normal-weight women.

Neutron pumping of active medium formed by gadolinium isotopes 155Gd and 156Gd pair: A feasibility study.

The possibility of creating technical means for controlling the processes of accumulation and conversion of the energies of thermal and epithermal neutrons into the energy of monoenergetic photons due to neutron pumping of an active medium consisting of nuclei with long-lived isomeric states was studied in this work. The system under study consisted of an external pulse-periodic source of deuterium-tritium neutrons (PSN) and a subcritical blanket, which included a variable neutron-collimation beam-shaping assembly (vBSA) and an active medium. The vBSA was composed of moderating blocks and selective plates designed to trap and shape a pulsed neutron flux with subsequent conversion of a millisecond signature into monoenergetic photon emission. Gadolinium oxide enriched in 155Gd isotope was used as the active medium, where the heavier one could be at different excited states, the de-excitations of which were accompanied by photon emission. In this research, the possibility of using the conjugate system (i.e., blanket - PSN - vBSA) for converting excess neutron energy accumulated in the inverse state of 156Gd nuclei into photon emission was demonstrated in detail.

Comparison of H*(10) estimations, due to neutrons and γ-rays, around FANT with two 241Am/9Be sources.

FANT (Fuente Ampliada de Neutrones Térmicos; in Spanish) is a thermal neutron irradiation facility with an extended and very uniform irradiation area, which has been developed by the Neutron Measurement Laboratory of the Energy Engineering Department at Universidad Politécnica de Madrid (LMN-UPM). In FANT, an isotopic neutron source (241Am/9Be) produces the primary neutrons. The design and facility optimization were carried out by extensive Monte Carlo calculations. In addition, Monte Carlo methods were used to evaluate the facility's performance to produce a constant and uniform thermal neutron field; these results were validated through experimental methods. FANT is designed to have two neutron sources; the objective of this work is to estimate the ambient dose equivalent due to neutrons and gamma-rays by Monte Carlo methods, and to compare these values with measured experimental doses. Thus, the performance of FANT with the two 241Am/9Be sources of LMN-UPM, with regard to the ambient dose equivalent H*(10) produced by both neutrons and photons around the facility, is analyzed in this work. The results are compared with those previously obtained in the framework of the results obtained with the LB6411 device around FANT.

Mechanical and radiation shielding characterization of W-based alloys for advanced nuclear unit.

The paper aims to investigate the mechanical and radiation shielding properties of two tungsten-based alloys manufactured by powder technology; their features when compared with two standard stainless steel grades for advanced nuclear applications. Multiple measurements were performed to characterize the alloys' structural and mechanical properties. XRD analysis and average surface roughness measurements showed the crystalline and morphological structure of the alloys. Surface microhardness added to the abrasive wear analysis showed the final wear resistance of the selected alloys. In addition, the shielding features against gamma and fast neutrons radiation were calculated. The superior characteristics of W-based alloys manufactured by powder technology make them suitable to be used in advanced nuclear power units.

Dosimetric evaluation of 123I (Iodide) and 99mTc (Pertechnetate) in the thyroid of neonates using Cristy-Eckerman and Segars anatomical representations.

Using the MIRD formalism, and the Cristy-Eckeman and Segars anthropomorphic representations, the absorbed dose in the thyroid of newborns, was calculated when 123I (iodide) and 99mTc (pertechnetate) are used during the diagnostic procedures. The dose results will allow exploring the dosimetric impact generated by the use of these radiopharmaceutical compounds and the use of two representations. Regardless the radiopharmaceutical compound and the anthropomorphic representation is the thyroid self-dose is the greatest, due to electrons emitted during the 123I and 99mTc radioisotopes. The relative difference in total dose to the newborn thyroid gland using the Cristy-Eckerman and Segars anthropomorphic representations for the compounds 123I(iodide) and 99mTc(pertechnetate) is 1.82%, and 1.33%, respectively. Regardless of the radiopharmaceutical compound, the replacement of Cristy-Eckerman by Segars phantom does not reflect significant changes in the estimated absorbed dose to the newborn thyroid. Regardless of the anthropomorphic representation, the lowest absorbed dose in newborn's thyroid is obtained when using 99mTc (pertechnetate) is used due to the residence times.

Estimation with Monte Carlo of thermal neutrons in the FANT, using 252Cf and 241Am/9Be neutron source.

The thermal neutron irradiation device (FANT), developed at the Neutron Measurements Laboratory of the Energy Engineering Department at Universidad Politécnica de Madrid, is a high-density polyethylene regular parallelepiped, with a rather uniform neutron fluence inside its irradiation chamber. It uses a Am95241/Be49 neutron source aiming to provide thermal neutron fluence rates. Neutron spectra and neutron fluences were estimated with Monte Carlo methods in the FANT irradiation chamber when a Cf98252 neutron source is used and were compared with the results obtained with the Am95241/Be49 source. Regardless of the neutron source, the largest contribution is due to thermal neutrons, producing also epithermal and fast neutrons. Per neutron emitted by the source, the use of Cf98252 produces a larger amount of neutrons.

Spectra, fluence and absorbed doses in sensitive organs due to scattered X-rays during a chest CT.

The use of ionizing radiation for the treatment and diagnosis of diseases is becoming more frequent. The technologies associated with diagnostic imaging are constantly evolving, allowing faster and cheaper diagnoses to benefit the patient. However, this has caused an increase in the exposure to ionizing radiation of patients and health professionals. One of the diagnostic techniques for obtaining high-resolution anatomical images of patients is computed tomography (CT). Due to the detail and quality of the images obtained with CT, its use is becoming more frequent. The information provided by these images allows the specialist to make better diagnoses; however, exposure to X-rays deposits a dose in the patient. CT represents approximately 20% of all X-ray examinations but it is responsible for 70% of the medical dose accumulated by the patient. During the acquisition of the images, the highest dose is deposited in the area of the body whose image is to be obtained. During the incidence of X-rays, there is dispersion of these that reach sensitive organs whose dose is not evaluated. The objective of this work was to estimate, using Monte Carlo methods, the fluence and X-ray spectra and to obtain a factor that allows knowing the absorbed dose in sensitive organs due to scattered radiation during a chest CT. With the MCNP5 code, the CT equipment and a hybrid anthropomorphic phantom, type BOMAB it was found that the absorbed dose in these organs depends on the size of the organ and the distance between the organ and the surface of the slice on the thorax where the X-rays are incident.

How much should you worry about contaminant neutrons in spatially fractionated grid radiation therapy?

Neutron contamination in radiation therapy is of concern in treatment with high-energy photons (> 10 MV). With the development of new radiotherapy modalities such as spatially fractionated grid radiation therapy (SFGRT) or briefly grid radiotherapy, more studies are required to evaluate the risks associated with neutron contamination. In 15 MV SFGRT, high-Z materials such as lead and cerrobend are used as the block on the tray of linear accelerator (linac) which can probably increase the photoneutron production. On the other hand, the high-dose fractions (10-20 Gy) used in SFGRT can induce high neutron contamination. The current study was devoted to addressing these concerns via compression of neutron fluence (Φn) and ambient dose equivalent ([Formula: see text]) at the patient table and inside the maze between SFGRT and conventional fractionated radiation therapy (CFRT). The main components of the 15 MV Siemens Primus equipped with different grids and located inside a typical radiotherapy bunker were simulated by the MCNPX® Monte Carlo code. Evidence showed that the material used for grid construction does not significantly increase neutron contamination inside the maze. However, at the end of the maze, neutron contamination in SFGRT is significantly higher than in CFRT. In this regard, a delay time of 15 minutes after SFGRT is recommended for all radiotherapy staff before entering the maze. It can be also concluded that [Formula: see text] at the patient table is at least 10 times more pronounced than inside the maze. Therefore, the patient is more at risk of neutrons compared to the staff. The [Formula: see text] at the isocenter in SFGRT with grids made of lead and cerrobend was nearly equal to CFRT. Nevertheless, it was dramatically lower than in CFRT by 30% if the brass grid is used. Accordingly, SFGRT with the brass grid is recommended, from radiation protection aspects.

Benchmarking of stray neutron fields produced by synchrocyclotrons and synchrotrons in compact protontherapy centers (CPTC) using MCNP6 Monte Carlo code.

Proton therapy is an external radiotherapy using proton beams with energies between 70 and 230 MeV to treat some type of tumours with outstanding benefits, due to its energy transfer plot. There is a growing demand of facilities taking up small spaces and Compact Proton Therapy Centers (CPTC), with one or two treatment rooms, supposing the technical response of manufacturers to this request. A large amount of stray radiation is yielded in the interaction of proton beam used in therapy, neutrons mainly, hence, optimal design of shielding and verifications must be carried out in commissioning phases. Currently, almost 50 proton centers are under construction and start up in several countries, including ten in Spain. In the present work the effectiveness of shielding in two CPTC was verified with the Monte Carlo code MCNP6 by calculating the ambient dose equivalent, H*(10) due to secondary neutrons, outside the enclosures and walls of the center. The facilities modelled were the two centers currently operating in Spain, the first, since December 2019, with a superconductor synchrocyclotron, and the second, since March 2020, with a compact synchrotron. The geometry and materials are based on dimensions proposed a priori by the vendors, therefore, the paper is focused on check the suitability of the materials and thickness of the walls of the centers. Several models of the radiation sources were simulated, starting from a conservative assumptions, followed by more realistic scenarios. In all cases, the results reached for the ambient dose equivalent, H*(10), were below 1 mSv/year, which is the legal limit considered for the public in international references. Finally, considering that the recent ICRU Report 95 proposes changes in the operational quantities, the dose outside shieldingt has been evaluated in terms of the new next area surveillance quantity, H*, known as ambient dose, in the process of implementation.

Improving the properties of commercial steel alloys in the industrial/nuclear field by RF plasma carbonitriding.

The study investigates the effect of RF plasma on the commercial SS201 and Steel alloys physical, structural and nuclear properties, using an atmosphere of nitrogen (85%) plus acetylene (15%) at 500 W working for 0.5 h. The results were compared with untreated alloys and AISI304L. The study indicated the ability of RF plasma to improve both the mechanical and tribological properties of treated alloys compared to the original commercial alloys and the AISI304L, and achieve good shielding properties for industrial/nuclear applications.

Identifying Strategies for Improving Pre-exposure Prophylaxis Adherence: Perspectives from a Sample of Highly Adherent Young Men Who have Sex with Men.

Most research on pre-exposure prophylaxis (PrEP) adherence and persistence uses a deficit-based approach to identify negative influences on PrEP adherence; however, an alternative set of approaches (such as resilience, asset-based, and positive variation) may identify equally important positive influences on PrEP adherence. Thus, the current study presents qualitative perspectives of PrEP adherence strategies from a sample of adherent YMSM. PrEP-using YMSM living in the Chicago area from a larger cohort study were recruited into a 90-day diary study that measured sexual health behaviors including PrEP use. A subset (n = 28) were then recruited for in-depth interviews between April and September 2020 covering topics of PrEP use and adherence. Thematic analysis was used to interpret patterns within the data. The analytic sample (n = 19) consistently reported high levels of adherence. Adherence strategies were organized into three broader categories: psychological (e.g. mindfulness, pill auditing), technical/instrumental (e.g. automated reminders, pill organizers), and social strategies (e.g. checking in with friends, or getting suggestions from friends). The majority of participants described using multiple strategies and changing strategies to respond to barriers to adherence. Other themes that were related to adherence included having a daily medication history and a generally positive outlook toward the PrEP regimen. Those who had medication histories were able to draw from experience to develop strategies for PrEP adherence. Findings suggest the need for pre-emptive counseling for PrEP-initiators on the use of multiple strategies, how to prepare for PrEP adherence, to adapt to challenges, and to adopt a range of potential strategies for adherence.

RESUMEN: La mayoría de las investigaciones sobre el cumplimiento y la persistencia de la profilaxis pre-exposición (PrEP) utiliza un enfoque basado en el déficit para identificar las influencias negativas en el cumplimiento de la PrEP; sin embargo, un conjunto alternativo de enfoques (como resiliencia, basado en en las capacidades o recursos, y variación positiva) puede identificar influencias positivas igualmente importantes en la adherencia a la PrEP. Por lo tanto, el estudio actual presenta perspectivas cualitativas de las estrategias de adherencia a la PrEP de una muestra de los hombres jóvenes que tienen sexo con hombres (YMSM) adherentes. Los YMSM que usaban PrEP que vivían en la región de Chicago de un estudio de cohorte más grande fueron reclutados en un estudio diario de 90 días que midió los comportamientos de salud sexual, incluido el uso de PrEP. Luego se reclutó un subconjunto (n = 28) para entrevistas en profundidad entre abril y septiembre de 2020 que cubrieron temas de uso y adherencia a la PrEP. El análisis temático se utilizó para interpretar patrones dentro de los datos. La muestra analítica (n = 19) reportó consistentemente altos niveles de adherencia. Las estrategias de adherencia se organizaron en tres categorías más amplias: psicológicas (p. ej., atención plena, auditoría de píldoras), técnicas/instrumentales (p. ej., recordatorios automáticos, organizadores de píldoras) y estrategias sociales (p. ej., ponerse en contacto con amigos o recibir sugerencias de amigos). La mayoría de los participantes describieron el uso de múltiples estrategias y el cambio de estrategias para responder a las barreras a la adherencia. Otros temas relacionados con la adherencia incluyeron tener un historial de medicación diario y una perspectiva generalmente positiva hacia el régimen de PrEP. Aquellos que tenían antecedentes de medicación pudieron aprovechar la experiencia para desarrollar estrategias para la adherencia a la PrEP. Los hallazgos sugieren la necesidad de asesoramiento preventivo para los iniciadores de la PrEP sobre el uso de múltiples estrategias, cómo prepararse para la adherencia a la PrEP, cómo adaptarse a los desafíos y adoptar una variedad de posibles estrategias para la adherencia.

Doses and spectra, of leaking-out and scattered photons from X-ray tubes used in dentistry.

Diagnosis by X-ray image are procedures widely used to improve the diagnosis or to follow the evolution of a medical procedure, also are used to support the cancer treatment with linear accelerators. The procedure involves the X-ray unit and the detection system, while the X-ray beam is projected onto the patient; along this procedure X-rays are scattered out from the patient body and X-rays leak-out from the X-ray unit. Both, the scattered and the leaking out radiation, are important during the evaluation or the design of the shielding barriers. X-ray tube features like voltage, electric current, target and filter are related to the dose due to the scattered and leakage radiation. Also, the dose due to the scattered radiation depends upon the scattering angle; while the dose due to the leaking out radiation, depend upon the X-ray tube housing. The objective of this work was to estimate, using Monte Carlo methods, the X-ray spectra and doses (air Kerma and Ambient dose equivalent) produced by scattered and leaking out radiation of 70, 80 and 90 kV X-ray units.

Effect of changing the neutron moderator in a thermal subcritical nuclear reactor.

Subcritical thermal nuclear reactor is the combination of nuclear fuel, moderator and external neutron source. Nevertheless, the amount of neutrons increases through nuclear fissions in the 235U in the fuel, the absorption and leakage of neutrons maintain the subcriticality condition. There are several subcritical reactors with different features and purposes. The open tank subcritical reactor Nuclear Chicago model 9000 is the heterogeneous combination of natural uranium, in hexagonal lattice, and light water, acting as moderator and reflector of neutrons, that uses a239PuBe neutron source. Worldwide there are several of these reactors mainly used in education, where due to the contact with water the Al tubes have corrosion. A possible solution is to use polyethylene as moderator. Aiming to evaluate the effect of changing the moderator, in this work Monte Carlo methods were used to model the reactor with polyethylene and water as moderators increasing the fuel load. For each model were estimated the keff and the µ parameters, and for Case 10a model was calculated the power, the Ambient dose equivalent and the fluence, of neutrons and γ-rays at five sites outside the reactor.

Radiation shielding and dosimetric parameters of mexican artisanal bricks.

In this work, were determined some radiation shielding and dosimetric parameters of three types of bricks for photons energy from 1 keV to 100 GeV photons using the Phy-X/PSD software, and for comparison also has been calculated the same parameters for NBS concrete. The parameters calculated are the linear attenuation coefficients (LAC), effective atomic numbers (Zeff), half value layers (HVL), the energy absorption buildup factors (EABF) and the exposure buildup factors (EBF), as well as the coefficients to use the geometric progression (G-P) fitting method. Obtained results show that the three types of bricks can be used safely for the design of medical facilities housing mammography units (less than 30 keV).

Age-specific calibration for in vivo monitoring of thyroid: is it necessary?

Usually, an age-specific calibration of detectors used for in vivo monitoring of 131I thyroid radioactivity is not performed in practice. This study aimed to investigate the reduction in uncertainty that one can expect if an age-specific calibration is performed. For this, voxel and stylized computational phantoms of the thyroid, corresponding to children at different age groups, were used to simulate the calibration process of 131I detectors used for thyroid monitoring. SCK•CEN physical phantoms were also used for this purpose. Both analytical and Monte Carlo methods (MCNPX version 2.6.0) were used to estimate the counting efficiencies of the considered detectors. The results show that the uncertainties in the assessment of thyroid activity at a distance of 20 cm would be reduced from a range of +8% to +30%, to a range from - 6% to +15% when age-specific calibration was performed. Using a calibration based on thyroids of adults would result in an overestimation of the thyroid activity for children by up to 30% at a detector-neck distance of about 20 cm; a larger overestimation may be expected at closer distances. It is concluded that age-specific calibration of in vivo monitoring systems for the thyroid is important and has to be taken into consideration to improve the reliability of thyroid dose assessment for children.

Characteristics, as a shield against ionizing photons, of concrete blocks used in the construction industry.

INEGI reports that 81% of new constructions are built with durable materials, such as concrete blocks, including rooms where ionizing radiation is used, such as clinics and hospitals. The volume ratios used in the manufacture of concrete blocks have a 1: 5: 2 ratio of: portland cement, sand and crushed gravel. The percentage mass content of each atom in the sample is obtained with the energy-dispersed X-ray fluorescence, these results are used to calculate the characteristics such as shielding of the concrete blocks, which have been partially reported, in this work several characteristics are presented for photons from 1 keV to 100 GeV, such as linear attenuation coefficients, the hemireductive layer, the effective, atomic and electronic sections, the effective atomic number (Zef). The exposure of accumulation and energy absorption factors (EBF, EABF) of 0.5-40 mfp are reported, using the Photon Shielding and Dosimetry (PSD) software. These characteristics are compared to those of NBS concrete. The concrete blocks have an attenuation capacity for energies used in radiological equipment such as mammography, 20-35 keV; dental, 50-90 keV and for conventional radiography equipment, 70-150 keV, so the block and lightened concrete block must be considered in the calculations of primary and secondary shielding walls.

Gamma-ray energy spectrum unfolding of plastic scintillators using artificial neural network.

In this study, the unfolding of the plastic scintillator spectrum was undertaken using the artificial neural networks tools of MATLAB. To this purpose, the response matrix of the plastic scintillator was generated for 145 energy groups and in 512 pulse-height channels using the MCNPX2.6 code. The results confirmed that the relative error in the gamma-ray energy unfolding with artificial neural networks is less than 3.8%.

Mathematical description of the effect of HIF inhibition on the radiobiological response of LNCaP cells.

According to the National Institute of Public Health, prostate cancer (PCa) is the leading cause of cancer death in Mexican men, highly associated with aggressiveness, resistance to treatment, and metastatic spread (Bharti et al., 2019) mediated by activation of the hypoxia-inducible factor 1 (HIF-1α). The objective of the present study was to evaluate the participation of HIF-1α activation in the radiobiological response of the human prostate adenocarcinoma cell line LNCaP, describing the phenomena with a mathematical model. Four groups were formed under different exposure conditions, including hypoxic cells treated with CoCl2 (300 µM for 22 h) with or without hypoxia-inducible factor inhibitor (150 nM chetomin for 4 h added after an incubation period of 18 h with CoCl2, just before completing the incubation period of 22 h). They were exposed to a source of 60Co in a dose range between 2 and 10 Gy to obtain survival curves that are fitted to a mathematical model. CoCl2 or chetomin treatments do not affect the viability of LNCaP cells that remained unchanged after irradiation. CoCl2 induced hypoxia reduces the survivability of LNCaP, and obstruction of HIF-1α signaling with chetomine produces a slight radioprotective effect. As others report, the genetic reprogramming induced by HIF-1α activation acts as an intrinsic agent that selects cells with more aggressive behavior (Pressley et al., 2017), while chetomin protects cells from death due to its scavenger properties. Interestingly, treatment with chetomin of cells induced to hypoxia (HIF-1 activation with CoCl2) produces a significant reduction in the radioresistance of LNCaP cells, demonstrating that the simultaneous use of chetomin and gamma radiation is an effective option for the treatment of hypoxic prostate cancer. At the molecular level, we suggest that the selective force exerted by HIF-1α depends on the production of free radicals by radiation. The proposed mathematical model showed that the rate of change in cell survival as a function of radiation dose is proportional to the product of two functions, one that describes cell death and the other that describes natural or artificial resistance to radiation.