Decomposition studies of group 6 hexacarbonyl complexes. Part 1: Production and decomposition of Mo(CO)6 and W(CO)6

Chemical studies of superheavy elements require fast and efficient techniques, due to short half-lives and low production rates of the investigated nuclides. Here, we advocate for using a tubular flow reactor for assessing the thermal stability of the Sg carbonyl complex – Sg(CO)6. The experimental setup was tested with Mo and W carbonyl complexes, as their properties are established and supported by theoretical predictions. The suggested approach proved to be effective in discriminating between the thermal stabilities of Mo(CO)6 and W(CO)6. Therefore, an experimental verification of the predicted Sg–CO bond dissociation energy seems to be feasible by applying this technique. By investigating the effect of 104,105Mo beta-decay on the formation of 104,105Tc carbonyl complex, we estimated the lower reaction time limit for the metal carbonyl synthesis in the gas phase to be more than 100 ms. We examined further the influence of the wall material of the recoil chamber, the carrier gas composition, the gas flow rate, and the pressure on the production yield of 104Mo(CO)6, so that the future stability tests with Sg(CO)6 can be optimized accordingly.

Miḳraʾot ḳeṭanot tarja ''g mitsṿot ha-Torah : 613 Gesetze der Mosaischen Lehre. Im Originaltexte u. dt. Übers. nach d. von Zunz rev. Bibel ...

von Ignatz Großmann

Measurements of neutrino oscillation in appearance and disappearance channels by the T2K experiment with 6.6×10²⁰ protons on target

We report on measurements of neutrino oscillation using data from the T2K long-baseline neutrino experiment collected between 2010 and 2013. In an analysis of muon neutrino disappearance alone, we find the following estimates and 68% confidence intervals for the two possible mass hierarchies: Normal Hierarchy: sin²θ₂₃= 0.514+0.055−0.056 and ∆m²_32 = (2.51 ± 0.10) × 10⁻³ eV²/c⁴ Inverted Hierarchy: sin²θ₂₃= 0.511 ± 0.055 and ∆m²_13 = (2.48 ± 0.10) × 10⁻³ eV²/c⁴ The analysis accounts for multi-nucleon mechanisms in neutrino interactions which were found to introduce negligible bias. We describe our first analyses that combine measurements of muon neutrino disappearance and electron neutrino appearance to estimate four oscillation parameters, |∆m^2|, sin²θ₂₃, sin²θ₁₃, δCP , and the mass hierarchy. Frequentist and Bayesian intervals are presented for combinations of these parameters, with and without including recent reactor measurements. At 90% confidence level and including reactor measurements, we exclude the region δCP = [0.15, 0.83]π for normal hierarchy and δCP = [−0.08, 1.09]π for inverted hierarchy. The T2K and reactor data weakly favor the normal hierarchy with a Bayes Factor of 2.2. The most probable values and 68% 1D credible intervals for the other oscillation parameters, when reactor data are included, are: sin²θ₂₃= 0.528+0.055−0.038 and |∆m²_32| = (2.51 ± 0.11) × 10⁻³ eV²/c⁴.

Isotopic prediction calculation methodologies: application to Vandellos-II Reactor cycles 7-11

Determining as accurate as possible spent nuclear fuel isotopic content is gaining importance due to its safety and economic implications. Since nowadays higher burn ups are achievable through increasing initial enrichments, more efficient burn up strategies within the reactor cores and the extension of the irradiation periods, establishing and improving computation methodologies is mandatory in order to carry out reliable criticality and isotopic prediction calculations. Several codes (WIMSD5, SERPENT 1.1.7, SCALE 6.0, MONTEBURNS 2.0 and MCNP-ACAB) and methodologies are tested here and compared to consolidated benchmarks (OECD/NEA pin cell moderated with light water) with the purpose of validating them and reviewing the state of the isotopic prediction capabilities. These preliminary comparisons will suggest what can be generally expected of these codes when applied to real problems. In the present paper, SCALE 6.0 and MONTEBURNS 2.0 are used to model the same reported geometries, material compositions and burn up history of the Spanish Van de llós II reactor cycles 7-11 and to reproduce measured isotopies after irradiation and decay times. We analyze comparisons between measurements and each code results for several grades of geometrical modelization detail, using different libraries and cross-section treatment methodologies. The power and flux normalization method implemented in MONTEBURNS 2.0 is discussed and a new normalization strategy is developed to deal with the selected and similar problems, further options are included to reproduce temperature distributions of the materials within the fuel assemblies and it is introduced a new code to automate series of simulations and manage material information between them. In order to have a realistic confidence level in the prediction of spent fuel isotopic content, we have estimated uncertainties using our MCNP-ACAB system. This depletion code, which combines the neutron transport code MCNP and the inventory code ACAB, propagates the uncertainties in the nuclide inventory assessing the potential impact of uncertainties in the basic nuclear data: cross-section, decay data and fission yields

A simplified Probabilistic Safety Assesment of a Steam-Methane Reforming Hydrogen Production Plant coupled to a High-Temperature Gas Cooled Nuclear Reactor

A Probabilistic Safety Assessment (PSA) is being developed for a steam-methane reforming hydrogen production plant linked to a High-Temperature Gas Cooled Nuclear Reactor (HTGR). This work is based on the Japan Atomic Energy Research Institute’s (JAERI) High Temperature Test Reactor (HTTR) prototype in Japan. This study has two major objectives: calculate the risk to onsite and offsite individuals, and calculate the frequency of different types of damage to the complex. A simplified HAZOP study was performed to identify initiating events, based on existing studies. The initiating events presented here are methane pipe break, helium pipe break, and PPWC heat exchanger pipe break. Generic data was used for the fault tree analysis and the initiating event frequency. Saphire was used for the PSA analysis. The results show that the average frequency of an accident at this complex is 2.5E-06, which is divided into the various end states. The dominant sequences result in graphite oxidation which does not pose a health risk to the population. The dominant sequences that could affect the population are those that result in a methane explosion and occur 6.6E-8/year, while the other sequences are much less frequent. The health risk presents itself if there are people in the vicinity who could be affected by the explosion. This analysis also demonstrates that an accident in one of the plants has little effect on the other. This is true given the design base distance between the plants, the fact that the reactor is underground, as well as other safety characteristics of the HTGR. Sensitivity studies are being performed in order to determine where additional and improved data is needed.

Aplicación de un tratamiento biológico a las aguas residuales provenientes de una destilería de alcohol de caña, utilizando un reactor UASB

En este trabajo se llevó a cabo el tratamiento de vinazas mediante dos tecnologías anaerobias. Se dividió en cuatro estudios técnicos. El primero fue el arranque y estabilización del reactor UASB (Upflow Anaerobic Sludge Blanket), en dónde se evaluó la estabilización mediante la eficiencia de remoción de DQO y la granulación del lodo. El segundo estudio evaluó el rendimiento del reactor UASB frente a diferentes Cva. El tercer estudio evaluó el efecto del TRH sobre la eficiencia del reactor UASB, y el cuarto de ellos fue evaluar el rendimiento del RABF (Reactor Anaerobio de Biomasa Fija). El reactor UASB de 2,6 L de capacidad, fue arrancado por lotes, con seis ensayos utilizando vinaza como sustrato. Se obtuvieron eficiencias de remoción en DQO en un rango de 79-91%, en los seis lotes. Se obtuvo formación de gránulos con diámetro (Ø) de 0,85-1,15 mm y un coeficiente de esfericidad (Є) de 0,7-0,77. Se logró la granulación de lodos tras 2 meses de operación. Alcanzada la estabilización del reactor UASB, se siguió una operación en flujo continuo. Las Cva probadas de 1, 2, 4 y 6 gDQO/L.d para el reactor UASB dan una respuesta bastante favorable con respecto al rendimiento del reactor, ya que presento eficiencias de remoción de DQOs del 51 hasta el 76%, eficiencias similares a los reportados por la literatura. En el estudio de TRH se operó con Cva de 6 gDQO/L.d y los TRH fueron de 24, 12 ,5 ,3 y 1 día. El % de eliminación de DQO fue de 51, 60, 57, 60 y 63 % remoción en DQOsoluble, respectivamente. Se alcanzó una producción de biogás máximo de 5.283 ml/d, pero al reducir el TRH se observó una reducción proporcional del volumen total de biogás. El %CH4 contenido en el biogás aumento al disminuir el TRH, reflejando valores de 80 al 92 % de CH4. El RABF con un volumen de 8,2 L, utilizo tubos de plástico corrugado como medio de soporte para las bacterias. Se aplicaron las siguientes Cva; 0,5, 1, 3 y 6 gDQO/L.d. El reactor RABF presento una excelente remoción de la materia orgánica (80% DQOs), una producción de biogás estable, y un contenido en CH4 del biogás muy interesante. Sin embargo, para una Cva superior a 3 gDQO/L.d empezó un comportamiento inesperado de reducción de capacidad. Las condiciones hidrodinámicas del reactor UASB son decisivas para la formación de los gránulos, condición previa para iniciar el flujo continuo. Al operar el reactor UASB en modo continuo, se pudo evaluar las mejores condiciones de operación para este tipo de residuo (vinaza). La Cva de 6 gDQO/L.d para el reactor UASB alimentado con vinaza bruta representa el límite de su capacidad. Sin embargo, al aumentar la Cva se genera una mayor producción de biogás y metano. La eficiencia de remoción de la DQO soluble es independiente del TRH, para una Cva de 6 g DQO/L•d y las condiciones de TRH probadas (24, 12, 5, 3 y 1 días). Los valores de remoción de DQO alcanzados son un poco superior a los valores de biodegradabilidad anaerobia de la vinaza observados de 50 %. De manera general, la reducción del TRH o bien la dilución de la vinaza no presenta un efecto significativo sobre la remoción de la materia orgánica soluble, pero si lo presenta en la remoción de sulfatos reduciendo indirectamente su toxicidad. El soporte termoplástico inoculado en el RABF y alimentado con vinaza bruta, actuó como un filtro, además de obtener buenos resultados en eliminación de DQO, pero dada las dimensiones y la altura del relleno se frena la evacuación del metano. This work was carried out by treatment vinasses with two anaerobic technologies. It was divided into four technical studies. The first was the start up and stabilization Upflow Anaerobic Sludge Blanket (UASB) reactor, where the stability was evaluated by the removal efficiency of COD and sludge granulation. The second study evaluated the performance of the UASB reactor against different OLR. The third study evaluated the effect of HRT on the efficiency of the UASB reactor, and the fourth of which was evaluate the performance Fixed Biomass Anaerobic (FBA) reactor. The UASB reactor of 2,6 L capacity, was started in batch, with six assays using vinasse as substrate. Were obtained removal efficiencies of COD in the range of 79- 91% in the six batches. Forming granules were obtained with a diameter (Ø) of 0,85- 1,15 mm and sphericity coefficient (Є) of 0,7 to 0,77. Sludge granulation was achieved after 2 months of operation. Once stabilization is achieved of the UASB reactor, it was followed by a continuous flow operation. The OLR tested 1, 2, 4 and 6 gCOD/L.d for UASB reactor gives a very favorable response regarding the performance of the reactor, as presented COD5 removal efficiencies of 51 to 76%, similar efficiencies those reported in the literature The HRT study was operated with an OLR of 6 gCOD/L.d and HRT were 24, 12, 5, 3 and 1 day. The removal efficiency was 51, 60, 57, 60 and 63% in soluble COD, respectively. It reached a maximum biogas production of 5.283 ml / d, but by reducing the HRT showed a proportional reduction in the total volume of biogas. The %CH4 content in the biogas increased with decreasing TRH, reflecting values of 80 to 92% of CH4. The FBA reactor with a volume of 8,2 L, used corrugated plastic tubes as carrier for bacteria transportation. The following OLR was applied, 0,5, 1, 3 and 6 gCOD/L.d. The FBA reactor showed an excellent removal of organic matter (80% CODS), a stable biogas production, and CH4 content very interesting. However, for more than 3 gCOD/L.d OLR began with unexpected behavior of capacity reduction. The UASB reactor hydrodynamic conditions are decisive for the formation of the granules, precondition to start the continuous flow. By operating the UASB reactor in continuous mode, it was possible to evaluate the best operating conditions for this type of waste (vinasse). The OLR of 6 gCOD/L.d for the UASB reactor fed with raw vinasse represents the limit of its capacity. However, with increasing OLR creates increased biogas production and methane. The removal efficiency of soluble COD is independent of HRT for OLR of 6 gCOD/L.d and HRT conditions tested (24, 12, 5, 3 and 1 day). COD Removal values achieved are slightly higher than the values of the vinasse anaerobic biodegradability of observed at 50%. Generally, reduction of HRT or vinasse dilution does not present a significant effect on the removal of the soluble organic matter; however if it occurs in the removal of sulfate reducing indirectly its toxicity. The thermoplastic support inoculated in FBA reactor and fed with raw vinasse, acted as a filter, in addition to obtaining good results in COD removal, but given the size and height of the filling slows evacuation of methane.

Methodologies for an improved prediction of the isotopic content in high burnup samples. Application to Vandellos-II reactor core

Fuel cycles are designed with the aim of obtaining the highest amount of energy possible. Since higher burnup values are reached, it is necessary to improve our disposal designs, traditionally based on the conservative assumption that they contain fresh fuel. The criticality calculations involved must consider burnup by making the most of the experimental and computational capabilities developed, respectively, to measure and predict the isotopic content of the spent nuclear fuel. These high burnup scenarios encourage a review of the computational tools to find out possible weaknesses in the nuclear data libraries, in the methodologies applied and their applicability range. Experimental measurements of the spent nuclear fuel provide the perfect framework to benchmark the most well-known and established codes, both in the industry and academic research activity. For the present paper, SCALE 6.0/TRITON and MONTEBURNS 2.0 have been chosen to follow the isotopic content of four samples irradiated in the Spanish Vandellós-II pressurized water reactor up to burnup values ranging from 40 GWd/MTU to 75 GWd/MTU. By comparison with the experimental data reported for these samples, we can probe the applicability of these codes to deal with high burnup problems. We have developed new computational tools within MONTENBURNS 2.0. They make possible to handle an irradiation history that includes geometrical and positional changes of the samples within the reactor core. This paper describes the irradiation scenario against which the mentioned codes and our capabilities are to be benchmarked.