Authors:Honghao He, Mengyang Wu, and Janos Gyergyak
1 Development and current situation of installation art 1.1 The evolution of installation art French artist Marcel Duchamp produced works “Bicycle Wheel” and “Fontain” in 1951 and 1950, respectively, [ 1, 2 ]. These works of art have attracted the
Hélio Oiticica was born in Rio de Janeiro in 1937, and belonged to the radical art avant-garde in Brazil. In 1957 he produced his first work, Metaesquema, after which he was part of the neo-concrete group that broke rank with the concrete group. In 1964 he produced his work Parangolé, a cape used by the members of the Mangeira samba school, and a work that had expressive social and political connotations. Oiticica wanted spectators to become involved in the Parangolé, i.e. to wear it and to see others wearing it. In the same year Oiticica created his work Tropicalia, an installation that includes a poem, sand, a parrot, a labyrinth and a TV. Two other spatial reliefs, Bilaterais and Bólides, involve visual contact, colour and emotions. Oiticica created the work Cosmococa as quasi-cinema, i.e. a mixture of film and installation. He died in Rio de Janeiro in 1980.
The operation and maintenance of a complex analytical instrument such as an inductively coupled plasma mass spectrometer in
a radioactive contaminated environment presents unique problems and challenges that have to be considered in the purchasing
and installation process. Considerations such as vendor experience, typical radiation levels, sample matrices encountered
during sample analysis, instrument accessability for maintenance, and upkeep must be incorporated into the decision process.
The Radioactive Materials Analytical Laboratory (RMAL) at Oak Ridge National Laboratory (ORNL) recently purchased and installed
an inductively coupled plasma mass spectrometer for the analysis of Department of Energy (DOE) radioactive waste streams.
This presentation will outline the purchasing decision, installation of the instrument, and how the modifications needed to
operate in a radioactive contaminated laboratory do not significantly impact the daily operation and maintenance requirements
of the instrument. Also, a contamination survey of the system will be presented which demonstrates the contamination levels
in the instrument from the sample introduction system to the detector.
Authors:Judit Mádl-Szőnyi, Magdolna Virág, and Ferenc Zsemle
Budapest is famous for its thermal springs and spas and outstanding thermal water resources. In the 21st century renewable energy utilization — including the use of geothermal energy — became the focus of interest. Improving the use of the different forms of geothermal energy requires the assessment of their possibilities. The potential for deep geothermal doublet systems for direct heating in Budapest was evaluated based on the temperature conditions, the depth and reconnaissance of the carbonate reservoir. NW Buda is not appropriate for thermal water exploration. SW and SE Budapest have better temperature conditions but the lithology of the reservoir is uncertain. Beneath Pest the thermal water is well exploitable. It is obvious from the map of the region that the area is promising; however, due to the hydraulic continuity of the system, reinjection is desirable. Considering the reliability of the employed data the geothermal potential map is suitable only for general orientation and guidance.
The geothermal potential map for Groundwater-sourced Heat Pump Systems (GHPS; scale = 1:40,000) was assembled by evaluating the thickness and appearance of the gravel strata and water table, complemented by the sulfate content as an aggressive component of groundwater. The original geothermal potential map series can be used for the evaluation of potential sites in Budapest. It can be concluded that the Buda side of the Danube River is almost entirely unsuitable for shallow groundwater-based heat pump installations. The only areas under consideration are Óbuda and the riverbanks. On the Pest side, there is no gravel in the central part; the largest areas close to the river and in the immediate surroundings are uncertain, with patches of suitable and possible categories. The southern and eastern area of Pest is the most prospective for GHPS installation. The potential maps only consider natural parameters; however, installation may be strongly influenced by the urbanization and the city environment.
Authors:H. Matsuda, B. de Araujo, and J. de Araujo
Celeste-1 is a lab-scale hot cell intended for R&D work in reprocessing of low burn-up spent fuel elements. The studies are concerned with head-end, first separation cycle by Purex Process using mini mixer-settlers and development of analytical techniques. The analytical monitoring for process control purposes is based on several off-line techniques, such as X-ray fluorescence spectrometry, potentiometric titration, -and -spectroscopy, spectrophotometry, fluorimetry, density measurement and gas chromatography. The analytical treatment takes place in a shielded working place analytical hot cell, glove boxes and hoods and some final measurements are made in the associated analytical laboratory. A pneumatic system is used for transporting analytical samples. All analytical procedures are ready and in operation.
Authors:T. Zaremba, W. Mokrosz, J. Hehlmann, A. Szwalikowska, and G. Stapiński
In this paper the examination results of chemical and phase composition as well as wastes graining from the semi-dry flue
gas desulfurization (FGD) have been presented. The wastes contain mainly semi-hydrate calcium sulfite and calcium sulfate.
The phase composition changes of wastes at the temperature of 350 and 600°C have been determined. On the basis of carried
out examinations, possibilities of flue gas desulfurization wastes utilization in building materials production (sulfite and
anhydrite cement) are proposed.
Authors:I. Abugassa, Y. Khrbish, S. Abugassa, N. Ben Faid, A. Bashir, and S. Sarmani
The paper focuses on the validation of the k0-method of instrumental neutron activation analysis (k0-INAA) in the Tajura Nuclear Research Center (TNRC) via the analysis of several certified reference materials. The selected
reference materials were: SRM 1572 Citrus Leaves, SRM 1575 Pine Needles, IAEA-A11 Milk Powder, IAEA-V-10 Hay Powder, RM IAEA-Soil-7
and RM IAEA-SL-1 Lake Sediment. The method is based on the PC version Kayzero/Solcoi software package issued by DSM. All the
samples, reference materials and monitors were irradiated in various positions of the Tajura reactor with different f and α. The parameters f and α (f — thermal/epithermal neutron flux ratio, α — parameter accounting for the non-ideality of the 1/E epithermal neutron fluence rate distribution) were determined using the bare triple monitor method. The results obtained
for all the reference materials are in good agreement with the certified values.
Authors:F. De Corte, A. De Wispelaere, R. van Sluijs, D. Bossus, A. Simonits, J. Kučera, J. Frána, B. Smodis, and R. Jaćimović
At the Special Sessionk0 of the MTAA-8 (Vienna, 1991), and later on at the Intemationalk0 Users Workshop-Gent (1992), progress was reported with respect to the development and use of computer codes in order to mould thek0-standardization of neutron activation analysis into an effective working instrument. Among others, this resulted in the software package KAYZERO for PC DOS, which was designed and distributed by DSM Research (Geleen, NL), and which is based on thek0-methodology, algorithms and nuclear data file developed and created at the INW (Gent, B) and the KFKI (Budapest, H), the traditional k0-centres. One of the most recent initiatives is a project in the framework of the COPERNICUS programme of the Commission of the European Union. It uses the synergism of a Joint Research Project to give an impulse to the exploitation of KAYZERO-assisted NAA as a manageable and competitive analytical tool in industry and environmental sanitation in Hungary, the Czech Republic and Slovenia. An outline is given of the strategy worked out in this JRP, emphasizing the procedures applied in the three institutes for the calibration of their irradiation facilities and Ge-detectors, quality control and assurance procedures following the implementation of the method, and the identification and tackling of the practical analytical problems which are of relevance to the Central European partner countries.
A radiochemical procedure was developed and optimized which allows sensitive241Pu measurement in various sample materials. As a first step, Pu isotopes are separated from matrix elements, purified radiochemically, electroplated, and measured by -spectrometry. The electrodeposited Pu is then redissolved in nitric acid and extracted with trioctylphosphinic oxide/cyclohexane. The organic phase is mixed with scintillator cocktail (PPO/Xylene) and Pu is measured with a liquid scintillation counter. The detection limit of the optimized procedure for a counting time of 100 minutes is 50 mBq241Pu per sample at a 95% confidence level.