Extensive boiling as a precipitation mechanism for precious and base metal ores, Bienaventurada Mine, Huancavelica, Perú

The Bienaventurada mine operates a polymetallic Ag-Pb-Zn (Cu, Au) vein system of the low sulphidation epithermal type. Fluid inclusions, FI, are abundant in quartz, sphalerite and adularia. FI petrography demonstrates typical primary growth zoning which occurs frequently in crystalline quartz, and defines the most common primary FI. These are usually very small, but several types of primary, P, and secondary, S, FI Assemblages (FIAs) comprising FI of measurable size (3 to > 100 μm) can also be identified through careful petrographic work. The fluids are aqueous and undersaturated, and no evidence of CO2 was found; the degree of fill is usually high (~70-80 %) in the L-rich inclusions, but extremely low in V-rich inclusions. The measured microthermometric values are very consistent in the FIAs selected; they are for the most part roughly similar in the P and S assemblages: the median is typically ~258ºC for total homogenization temperatures, Th, and -1.5 ºC for ice melting temperatures, Tm (corresponding to 2.57 wt% NaCl eq). The widespread occurrence of L-rich and V-rich FI in the same FIA and the consistent Th values point to an extensive boiling system along the vein. In these conditions, Th equals T of trapping, and the ores are assumed to have been precipitated from an aqueous low salinity boiling fluid, of likely meteoric origin, at some 250-280º C, under ~500 m hydrostatic head.

Assessment of CTF boiling transition and critical heat flux modeling capabilities using the OECD/NRC BFBT and PSBT benchmark databases

The need to refine models for best-estimate calculations, based on good-quality experimental data, has been expressed in many recent meetings in the field of nuclear applications. The modeling needs arising in this respect should not be limited to the currently available macroscopic methods but should be extended to next-generation analysis techniques that focus on more microscopic processes. One of the most valuable databases identified for the thermalhydraulics modeling was developed by the Nuclear Power Engineering Corporation (NUPEC), Japan. From 1987 to 1995, NUPEC performed steady-state and transient critical power and departure from nucleate boiling (DNB) test series based on the equivalent full-size mock-ups. Considering the reliability not only of the measured data, but also other relevant parameters such as the system pressure, inlet sub-cooling and rod surface temperature, these test series supplied the first substantial database for the development of truly mechanistic and consistent models for boiling transition and critical heat flux. Over the last few years the Pennsylvania State University (PSU) under the sponsorship of the U.S. Nuclear Regulatory Commission (NRC) has prepared, organized, conducted and summarized the OECD/NRC Full-size Fine-mesh Bundle Tests (BFBT) Benchmark. The international benchmark activities have been conducted in cooperation with the Nuclear Energy Agency/Organization for Economic Co-operation and Development (NEA/OECD) and Japan Nuclear Energy Safety (JNES) organization, Japan. Consequently, the JNES has made available the Boiling Water Reactor (BWR) NUPEC database for the purposes of the benchmark. Based on the success of the OECD/NRC BFBT benchmark the JNES has decided to release also the data based on the NUPEC Pressurized Water Reactor (PWR) subchannel and bundle tests for another follow-up international benchmark entitled OECD/NRC PWR Subchannel and Bundle Tests (PSBT) benchmark. This paper presents an application of the joint Penn State University/Technical University of Madrid (UPM) version of the well-known subchannel code COBRA-TF, namely CTF, to the critical power and departure from nucleate boiling (DNB) exercises of the OECD/NRC BFBT and PSBT benchmarks

Spatial distribution of the soil carbon pool in a Holm oak dehesa in Spain

Aims Dehesas are agroforestry systems characterized by scattered trees among pastures, crops and/or fallows. A study at a Spanish dehesa has been carried out to estimate the spatial distribution of the soil organic carbon stock and to assess the influence of the tree cover. Methods The soil organic carbon stock was estimated from the five uppermost cm of themineral soil with high spatial resolution at two plots with different grazing intensities. The Universal Kriging technique was used to assess the spatial distribution of the soil organic carbon stocks, using tree coverage within a buffering area as an auxiliary variable. Results A significant positive correlation between tree presence and soil organic carbon stocks up to distances of around 8 m from the trees was found. The tree crown cover within a buffer up to a distance similar to the crown radius around the point absorbed 30 % of the variance in the model for both grazing intensities, but residual variance showed stronger spatial autocorrelation under regular grazing conditions. Conclusions Tree cover increases soil organic carbon stocks, and can be satisfactorily estimated by means of crown parameters. However, other factors are involved in the spatial pattern of the soil organic carbon distribution. Livestock plays an interactive role together with tree presence in soil organic carbon distribution.

Assessment of CTF boiling transition and critical heat flux modeling capabilities using the OECD/NRC BFBT and PSBT benchmark databases

Over the last few years, the Pennsylvania State University (PSU) under the sponsorship of the US Nuclear Regulatory Commission (NRC) has prepared, organized, conducted, and summarized two international benchmarks based on the NUPEC data—the OECD/NRC Full-Size Fine-Mesh Bundle Test (BFBT) Benchmark and the OECD/NRC PWR Sub-Channel and Bundle Test (PSBT) Benchmark. The benchmarks’ activities have been conducted in cooperation with the Nuclear Energy Agency/Organization for Economic Co-operation and Development (NEA/OECD) and the Japan Nuclear Energy Safety (JNES) Organization. This paper presents an application of the joint Penn State University/Technical University of Madrid (UPM) version of the well-known sub-channel code COBRA-TF (Coolant Boiling in Rod Array-Two Fluid), namely, CTF, to the steady state critical power and departure from nucleate boiling (DNB) exercises of the OECD/NRC BFBT and PSBT benchmarks. The goal is two-fold: firstly, to assess these models and to examine their strengths and weaknesses; and secondly, to identify the areas for improvement.

The contribution of two common shrub species to aboveground and belowgraound carbon pool in Iberian Dehesas

Shrubs play an important role in water-limited agro-silvo-pastoral systems by providing shelter and forage for livestock, for erosion control, to maintain biodiversity, diversifying the landscape, and above all, facilitating the regeneration of trees. Furthermore, the carbon sink capacity of shrubs could also help to mitigate the effects of climate change since they constitute a high proportion of total plant biomass. The contribution of two common extensive native shrub species (Cistus ladanifer L. and Retama sphaerocarpa (L.) Boiss.) to the carbon pool of Iberian dehesas (Mediterranean agro-silvo-pastoral systems) is analyzed through biomass models developed at both individual (biovolume depending) and community level (height and cover depending). The total amount of carbon stored in these shrubs, including above- and belowground biomass, ranges from 1.8 to 11.2 Mg C ha_1 (mean 6.8 Mg C ha_1) for communities of C. ladanifer and from 2.6 to 8.6 Mg C ha_1 (mean 4.5 Mg C ha_1) for R. sphaerocarpa. These quantities account for over 20e30% of the total plant biomass in the system. The potential for carbon sequestration of these shrubs in the studied system ranges 0.10e1.32 Mg C ha_1 year_1 and 0.25e1.25 Mg C ha_1 year_1 for the C. ladanifer and R. sphaerocarpa communities’ respectively

Potential issues related to emergency core cooling system strainers performance at boiling water reactors: application to Cofrentes NPP (Spain)

From the 60s to the 90s, a great number of events related to the Emergency Core Cooling Systems Strainers have been happened in all kind of reactors all over the world. Thus, the Nuclear Regulatory Commission of the USA emitted some Bulletins to address the concerns about the adequacy of Emergency Core Cooling Systems (ECCS) strainer performance at boiling water reactors (BWR). In Spain the regulatory body (Consejo de Seguridad Nuclear, CSN) adopted the USA regulation and Cofrentes NPP installed new strainers with a considerable bigger size than the old strainers. The nuclear industry conducted significant and extensive research, guidance development, testing, reviews, and hardware and procedure changes during the 90s to resolve the issues related to debris blockage of BWR strainers. In 2001 the NRC and CSN closed the Bulletins. Thereafter, the strainers issues were moved to the PWR reactors. In 2004 the NRC issued a Generic Letter (GL). It requested the resolution of several effects which were not noted in the past. The GL regarded to be resolved by the PWR reactors but the NRC in USA and the CSN in Spain have requested that the BWR reactors investigate differences between the methodologies used by the BWRs and PWRs. The developments and improvements done for Cofrentes NPP are detailed. Studies for this plant show that the head loss due to the considered debris is at most half of the limited head loss for the ECCS strainer and the NPSH (Net Positive Suction Head) required for the ECCS pumps is at least three times lower than the NPSH available.

Metodología de simulación numérica de la transferencia de calor por ebullición en película en torno a superficies esféricas refrigeradas por líquido saturado en convección libre: aplicación a reactores nucleares de lecho de bolas (PBR)

En la presente Tesis se realizó un análisis numérico, usando el código comercial Ansys-Fluent, de la refrigeración de una bola de combustible de un reactor de lecho de bolas (PBR, por sus siglas en inglés), ante un escenario de emergencia en el cual el núcleo sea desensamblado y las bolas se dejen caer en una piscina de agua, donde el mecanismo de transferencia de calor inicialmente sería la ebullición en película, implicando la convección y la radiación al fluido. Previamente se realizaron pruebas de validación, comparando los resultados numéricos con datos experimentales disponibles en la literatura para tres geometrías diferentes, lo cual permitió seleccionar los esquemas y modelos numéricos con mejor precisión y menor costo computacional. Una vez identificada la metodología numérica, todas las pruebas de validación fueron ampliamente satisfactorias, encontrándose muy buena concordancia en el flujo de calor promedio con los datos experimentales. Durante estas pruebas de validación se lograron caracterizar numéricamente algunos parámetros importantes en la ebullición en película con los cuales existen ciertos niveles de incertidumbre, como son el factor de acoplamiento entre convección y radiación, y el factor de corrección del calor latente de vaporización. El análisis térmico de la refrigeración de la bola del reactor por ebullición en película mostró que la misma se enfría, a pesar del calor de decaimiento, con una temperatura superficial de la bola que desciende de forma oscilatoria, debido al comportamiento inestable de la película de vapor. Sin embargo, la temperatura de esta superficie tiene una buena uniformidad, notándose que las áreas mejor y peor refrigeradas están localizadas en la parte superior de la bola. Se observó la formación de múltiples domos de vapor en diferentes posiciones circunferenciales, lo cual causa que el área más caliente de la superficie se localice donde se forman los domos más grandes. La separación entre los domos de vapor fue consistente con la teoría hidrodinámica, con la adición de que la separación entre domos se reduce a medida que evolucionan y crecen, debido a la curvatura de la superficie. ABSTRACT A numerical cooling analysis of a PBR fuel pebble, after an emergency scenario in which the nucleus disassembly is made and the pebbles are dropped into a water pool, transmitting heat by film boiling, involving convection and radiation to the fluid, is carried out in this Thesis. First, were performed validation tests comparing the numerical results with experimental works available for three different geometries, which allowed the selection of numerical models and schemes with better precision and lower computational cost. Once identified the numerical methodology, all validation tests were widely satisfactory, finding very good agreement with experimental works in average heat flux. During these validation tests were achieved numerically characterize some important parameters in film boiling with which there are certain levels of uncertainty, such as the coupling factor between convection and radiation, and the correction factor of the latent heat of vaporization. The thermal analysis of pebble cooling by film boiling shows that despite its decay heat, cooling occurs, with pebble surface temperature descending from an oscillatory manner, due to the instability of the vapor film. However, the temperature of this surface has a good uniformity, noting that the best and worst refrigerated area is located at the top of the pebble. The formation of multiple vapor domes at different circumferential positions is observed, which cause that the hottest area of the surface was located where biggest vapor domes were formed. The separation between vapor domes was consistent with the hydrodynamic theory, with the addition that the separation is reduced as the vapor dome evolves and grows, due to the surface curvature.