Iodine-129: Sample preparation, quality control and analyses of pre-nuclear materials and of natural waters from Lower Saxony, Germany

Sample preparation procedures for AMS measurements of 129I and 127I in environmental materials and some methodological aspects of quality assurance are discussed. Measurements from analyses of some pre-nuclear soil and thyroid gland samples and of a systematic investigation of natural waters in Lower Saxony, Germany, are described. Although the up-to-now lowest 129I/127I ratios in soils and thyroid glands were observed, they are still suspect to contamination since they are significantly higher than the pre-nuclear equilibrium ratio in the marine hydrosphere. A survey on all available 129I/127I isotopic ratios in precipitation shows a dramatic increase until the middle of the 1980s and a stabilization since 1987 at high isotopic ratios of about (3.6–8.3)×10−7. In surface waters, ratios of (57–380)×10−10 are measured while shallow ground waters show with ratios of (1.3–200)×10−10 significantly lower values with a much larger spread. The data for 129I in soils and in precipitation are used to estimate pre-nuclear and modern 129I deposition densities.

Nuclear materials : additional information on shipments from DOE's Rocky Flats Plant : fact sheet for the Honorable Timothy E. Wirth, U.S. Senate /

"B-216376"--P. [1].

Recent progress in research on tungsten materials for nuclear fusion applications in Europe

The current magnetic confinement nuclear fusion power reactor concepts going beyond ITER are based on assumptions about the availability of materials with extreme mechanical, heat, and neutron load capacity. In Europe, the development of such structural and armour materials together with the necessary production, machining, and fabrication technologies is pursued within the EFDA long-term fusion materials programme. This paper reviews the progress of work within the programme in the area of tungsten and tungsten alloys. Results, conclusions, and future projections are summarized for each of the programme´s main subtopics, which are: (1) fabrication, (2) structural W materials, (3) W armour materials, and (4) materials science and modelling. It gives a detailed overview of the latest results on materials research, fabrication processes, joining options, high heat flux testing, plasticity studies, modelling, and validation experiments.

Preparedness for rain during sunny weather: Caribbean environmental sustainability in a nuclear age

Includes bibliography

A construção da coordenação política e da cooperação estratégica entre o Brasil e Argentina na área nuclear (1980-1997)

Pós-graduação em História - FCHS

IFMIF suitability for evaluation of fusion functional materials

The International FusionMaterials Irradiation Facility (IFMIF) is a future neutron source based on the D-Li stripping reaction, planned to test candidate fusionmaterials at relevant fusion irradiation conditions. During the design of IFMIF special attention was paid to the structural materials for the blanket and first wall, because they will be exposed to the most severe irradiation conditions in a fusion reactor. Also the irradiation of candidate materials for solid breeder blankets is planned in the IFMIF reference design. This paper focuses on the assessment of the suitability of IFMIF irradiation conditions for testing functionalmaterials to be used in liquid blankets and diagnostics systems, since they are been also considered within IFMIF objectives. The study has been based on the analysis and comparison of the main expected irradiation parameters in IFMIF and DEMO reactor.

Determination of the hoop fracture properties of unirradiated hydrogen-charged nuclear fuel cladding from ring compression tests

In this work, a new methodology is devised to obtain the fracture properties of nuclear fuel cladding in the hoop direction. The proposed method combines ring compression tests and a finite element method that includes a damage model based on cohesive crack theory, applied to unirradiated hydrogen-charged ZIRLOTM nuclear fuel cladding. Samples with hydrogen concentrations from 0 to 2000 ppm were tested at 20 �C. Agreement between the finite element simulations and the experimental results is excellent in all cases. The parameters of the cohesive crack model are obtained from the simulations, with the fracture energy and fracture toughness being calculated in turn. The evolution of fracture toughness in the hoop direction with the hydrogen concentration (up to 2000 ppm) is reported for the first time for ZIRLOTM cladding. Additionally, the fracture micromechanisms are examined as a function of the hydrogen concentration. In the as-received samples, the micromechanism is the nucleation, growth and coalescence of voids, whereas in the samples with 2000 ppm, a combination of cuasicleavage and plastic deformation, along with secondary microcracking is observed.

IBM-7090 programs to compile and modify a nuclear data tape /

"May 31, 1961."

TiN-based coatings on fuel cladding tubes for advanced nuclear reactors

Titanium nitride (TiN) thin films are coated on HT-9 and MA957 fuel cladding tubes and bars to explore their mechanical strength, thermal stability, diffusion barrier properties, and thermal conductivity properties. The ultimate goal is to implement TiN as an effective diffusion barrier to prevent the inter-diffusion between the nuclear fuel and the cladding material, and thus lead to a longer lifetime of the cladding tubes. Mechanical tests including hardness and scratch tests for the samples before and after thermal cycle tests show that the films have a high hardness of 28GPa and excellent adhesion properties despite the thermal treatment. Thermal conductivity measurements demonstrate that the thin TiN films have very minimal impact on the overall thermal conductivity of the MA957 and HT-9 substrates, i.e., the thermal conductivity of the uncoated HT-9 and MA957 substrates was 26.25 and 28.44 W m-1 K-1, and that of the coated ones was 26.21 and 28.38W m-1 K-1, respectively. A preliminary Ce diffusion test on the couple of Ce/TiN/HT-9 suggests that TiN has excellent material compatibility and good diffusion barrier properties.

Efectos de la microestructura sobre la transmisión de neutrones en materiales de interés nuclear.

Cuando un haz policromático de neutrones pasa a través de un material, los neutrones de distintas longitudes de onda son atenuados en formas muy diferentes. Como resultado, el espectro de energía del haz de neutrones cambia cuando una muestra es colocada frente el haz. Un análisis detallado del cociente de intensidad entre los haces de transmitido e incidente puede proporcionar una gran cantidad de información acerca de la estructura cristalina y microestructura de la muestra, definidas a través de la sección eficaz total del material. Para neutrones térmicos y sub-térmicos, el ordenamiento y movimiento de los átomos a escala microscópica define en forma precisa la dependencia de esta magnitud con la energía del neutrón incidente. Así, la variación con la energía de la sección eficaz total de los sólidos debido a la estructura de los átomos para distancias entre 0,1 y 100 Å se encuentra bien establecida, y es explotada en el estudio de estructuras cristalinas y de los movimientos vibracionales y rotacionales. Como contrapartida, el efecto de la estructura mesoscópica de los materiales, esto es para dimensiones entre 0,1 y 100 µm, sobre la sección eficaz total ha sido mucho menos estudiado, a pesar de provocar cambios profundos en esta magnitud. En esta Tesis estudiamos y formalizamos la dependencia de la sección eficaz total con características microestructurales tales como la porosidad, y la distribución de tamaños y orientaciones de los granos que componen los materiales, y desarrollamos modelos teóricos a partir de las características microestructurales de muestras de interés nuclear con diferente microestructura. Estos modelos permiten describir la contribuci ón de la componente elástica coherente de la seción eficaz total sobre los espectros de transmisión de neutrones e introducen parámetros como la cantidad de cristales que conforman el material, su estructura cristalina, parámetros de red, mosaicidad, estructura de poros u orientación preferencial de granos, para describir la sección total de materiales monocristalinos o policristalinos. En todos los casos, los modelos desarrollados fueron implementados en una biblioteca basada en el lenguaje computacional MATLAB y fueron comparados con secciones eficaces totales obtenidas en experimentos de transmisión de neutrones realizados en el Departamento de Física de Neutrones del Centro Atómico Bariloche y en ISIS Facility, Reino Unido. Los novedosos modelos microestructurales propuestos describen fielmente los experimentos desarrollados sobre muestras con distinta microestructura, lo que permite el empleo de los mismos en un código de refinamiento sobre los datos experimentales. Aquí, desarrollamos herramientas computacionales que ajustan por cuadrados mínimos no lineales los modelos paramétricos representativos de cada microestructura, sobre la sección eficaz total o la transmisión experimental, para determinar parámetros microestructurales de la muestra a partir de experimentos de transmisión de neutrones con resolución en longitud de onda. Los resultados son de particular relevancia para la interpretación y el análisis cuantitativo de las imágenes realizadas por la técnica de radiografía neutrónica con resolución en energía, que ha recibido un gran impulso en años recientes.

Efectos de la microestructura sobre la transmisión de neutrones en materiales de interés nuclear.

Cuando un haz policromático de neutrones pasa a través de un material, los neutrones de distintas longitudes de onda son atenuados en formas muy diferentes. Como resultado, el espectro de energía del haz de neutrones cambia cuando una muestra es colocada frente el haz. Un análisis detallado del cociente de intensidad entre los haces de transmitido e incidente puede proporcionar una gran cantidad de información acerca de la estructura cristalina y microestructura de la muestra, definidas a través de la sección eficaz total del material. Para neutrones térmicos y sub-térmicos, el ordenamiento y movimiento de los átomos a escala microscópica define en forma precisa la dependencia de esta magnitud con la energía del neutrón incidente. Así, la variación con la energía de la sección eficaz total de los sólidos debido a la estructura de los átomos para distancias entre 0,1 y 100 Å se encuentra bien establecida, y es explotada en el estudio de estructuras cristalinas y de los movimientos vibracionales y rotacionales. Como contrapartida, el efecto de la estructura mesoscópica de los materiales, esto es para dimensiones entre 0,1 y 100 µm, sobre la sección eficaz total ha sido mucho menos estudiado, a pesar de provocar cambios profundos en esta magnitud. En esta Tesis estudiamos y formalizamos la dependencia de la sección eficaz total con características microestructurales tales como la porosidad, y la distribución de tamaños y orientaciones de los granos que componen los materiales, y desarrollamos modelos teóricos a partir de las características microestructurales de muestras de interés nuclear con diferente microestructura. Estos modelos permiten describir la contribuci ón de la componente elástica coherente de la seción eficaz total sobre los espectros de transmisión de neutrones e introducen parámetros como la cantidad de cristales que conforman el material, su estructura cristalina, parámetros de red, mosaicidad, estructura de poros u orientación preferencial de granos, para describir la sección total de materiales monocristalinos o policristalinos. En todos los casos, los modelos desarrollados fueron implementados en una biblioteca basada en el lenguaje computacional MATLAB y fueron comparados con secciones eficaces totales obtenidas en experimentos de transmisión de neutrones realizados en el Departamento de Física de Neutrones del Centro Atómico Bariloche y en ISIS Facility, Reino Unido. Los novedosos modelos microestructurales propuestos describen fielmente los experimentos desarrollados sobre muestras con distinta microestructura, lo que permite el empleo de los mismos en un código de refinamiento sobre los datos experimentales. Aquí, desarrollamos herramientas computacionales que ajustan por cuadrados mínimos no lineales los modelos paramétricos representativos de cada microestructura, sobre la sección eficaz total o la transmisión experimental, para determinar parámetros microestructurales de la muestra a partir de experimentos de transmisión de neutrones con resolución en longitud de onda. Los resultados son de particular relevancia para la interpretación y el análisis cuantitativo de las imágenes realizadas por la técnica de radiografía neutrónica con resolución en energía, que ha recibido un gran impulso en años recientes.

Performance-Based Quality Assurance/Quality Control (QA/QC) Acceptance Procedures for In-Place Soil Testing Phase 3

One of the objectives of this study was to evaluate soil testing equipment based on its capability of measuring in-place stiffness or modulus values. As design criteria transition from empirical to mechanistic-empirical, soil test methods and equipment that measure properties such as stiffness and modulus and how they relate to Florida materials are needed. Requirements for the selected equipment are that they be portable, cost effective, reliable, a ccurate, and repeatable. A second objective is that the selected equipment measures soil properties without the use of nuclear materials.The current device used to measure soil compaction is the nuclear density gauge (NDG). Equipment evaluated in this research included lightweight deflectometers (LWD) from different manufacturers, a dynamic cone penetrometer (DCP), a GeoGauge, a Clegg impact soil tester (CIST), a Briaud compaction device (BCD), and a seismic pavement analyzer (SPA). Evaluations were conducted over ranges of measured densities and moistures.Testing (Phases I and II) was conducted in a test box and test pits. Phase III testing was conducted on materials found on five construction projects located in the Jacksonville, Florida, area. Phase I analyses determined that the GeoGauge had the lowest overall coefficient of variance (COV). In ascending order of COV were the accelerometer-type LWD, the geophone-type LWD, the DCP, the BCD, and the SPA which had the highest overall COV. As a result, the BCD and the SPA were excluded from Phase II testing.In Phase II, measurements obtained from the selected equipment were compared to the modulus values obtained by the static plate load test (PLT), the resilient modulus (MR) from laboratory testing, and the NDG measurements. To minimize soil and moisture content variability, the single spot testing sequence was developed. At each location, test results obtained from the portable equipment under evaluation were compared to the values from adjacent NDG, PLT, and laboratory MR measurements. Correlations were developed through statistical analysis. Target values were developed for various soils for verification on similar soils that were field tested in Phase III. The single spot testing sequence also was employed in Phase III, field testing performed on A-3 and A-2-4 embankments, limerock-stabilized subgrade, limerock base, and graded aggregate base found on Florida Department of Transportation construction projects. The Phase II and Phase III results provided potential trend information for future research—specifically, data collection for in-depth statistical analysis for correlations with the laboratory MR for specific soil types under specific moisture conditions. With the collection of enough data, stronger relationships could be expected between measurements from the portable equipment and the MR values. Based on the statistical analyses and the experience gained from extensive use of the equipment, the combination of the DCP and the LWD was selected for in-place soil testing for compaction control acceptance. Test methods and developmental specifications were written for the DCP and the LWD. The developmental specifications include target values for the compaction control of embankment, subgrade, and base materials.