Publications Repository - Helmholtz-Zentrum Dresden-Rossendorf

Die Analyse von Ultraschall-Transmissionssignalen zeigte, daß eine laufende Identifikation des Stromungszustandes in Rohrleitungen durch einen Aufbau von Relationen zwischen den physikalischen Parametern einer Zweiphasenströmung und den charakteristischen Mustern gemessener Signale möglich ist. Auf dieser Grundlage werden Ergebnisse eines Systems, welches aus einer Ultraschall-Meßeinheit, einer Datenbankeinheit und einer Mustererkennungseinheit besteht, vorgestellt. Dieses System liefert am Ausgang vier Parameter: einen Identifikator fur die Strömungsform, die separaten Volumenströme der flüssigen und der gasformigen Phase und den abgeleiteten Gasgehalt. Der Parametersatz dient als einer von mehreren Eingabensätzen fur das übergeordnete Überwachungs- oder Diagnosesystem. Die mit diesem System erzielten Erkennungsraten liegen zwischen 87 % und 94%.

Druckentlastungsexperimente der TU Hamburg/Harburg von überkritischem CO₂ aus einem Druckbehälter werden vorgestellt. Dabei wurden mit einer Gamma-Durchstrahlung axiale Dampfgehaltsprofile im System CO₂-flüssig und CO₂-gasförmig sowie Druck- und Temperaturverläufe gemessen. Die Experimente, insbesondere die lokalen Gasgehalte, können durch das Programm BLDN des FZR mit Erfolg nachgerechnet werden, wobei verschiedene Driftansätze auf ihre Anwendbarkeit auf CO₂ hin überprüft wurden.

Small-angle neutron scattering (SANS) experiments were performed at KWS2 facility of the KFA Jülich for investigating the defect structures, which are produced by neutron irradiation in Russian Cr-Mo-V alloyed reactor pressure vessel steel. Irradiation and post-irradiation annealing considerably change both SANS intensity and its course in the Guinier plot, which was analysed by the Glatter method. As a rule, bimodal size distribution functions were found with a first maximum at a radius of 1-2 nm and a second maximum at 6-8 nm. Irradiation increases the first maximum annealing reduces it.

The first four Greifswald reactor units belong to the WWER 440/230 reactor family and they are the only ones permanently shut-down. The status of the WWER 440 units as concerns the plant specific material data is shortly described in the paper. The lack of material data is a real problem of the 230 model reactors and the high lead factor in the surveillance irradiations of the more modern 213 units is an essential uncertainty in the safety assessment of the units. In addition most aof the 230 units have been and some of the 213 units will be annealed. Greifswald units are fully representative WWER 440 units and they represent irradiated, irradiated-annealed and irradiated-annealed-reirradiated material conditions. In this paper a basic material research programme is proposed, which can greatly support the operating WWER units.

In the present paper the stability of the time-dependent, three-dimensional, incompressible flow around a circular cylinder exposed to an external magnetic field is investigated numerically. We perform a linear 3d stability analysis of the 2d flow being either steady or quasiperiodic as known from previous work. By monitoring the time evolution of the integral energy of the 3d disturbances in the computational domain we decide whether the flow is globally unstable or stable. The results are compared and validated with recent results for the purely hydrodynamic problem. We restrict the analysis to a magnetic field being aligned with the oncoming flow. For this case we numerically confirm the general result of Hunt that in the (Re, N)-plane parameter regions above the 2d-neutral stability curve exist where the flow is 3d-unstable but 2d stable (steady) because the magnetic field acts in a different way on 2d and 3d instabilities.

Die Beschreibung der Strömungsfelder in Blasensäulen ist Grundlage für die Bestimmung der Stoff und Wärmetransportvorgänge. Dabei steht die Untersuchung der instationären Zirkulationsbewegung der flüssigen Phase im Mittelpunkt, die mit Hilfe spektraler Verfahren berechnet wird. Das Modell wird für ein zweidimensionales rechteckiges Gebiet in kartesischen Koordinaten (Strömungsbox) aufgestellt. Hierbei wird die nichtlineare Wirbeltransportgleichung durch den spektralen Ansatz für free-slip Randbedingungen gelöst, der die Wirbeltransportgleichung in ein System von gekoppelten, nichtlinearen gewöhnlichen Differentialgleichungen umwandelt, die die zeitliche Entwicklung der Fourier-Koeffizienten a_n,m(t) und damit die Evolution der einzelnen Wirbelmoden beschreiben. Die nichtlinearen Terme werden durch explizite Berechnung der Konvolutionssummen gemäß dem traditionellen Galerkin-Verfahren ermittelt. Für die diskrete Phase wird angenommen, daß das Gas durch eine bestimmte Anzahl von Düsen im Boden der Säule eingespeist wird. Es werden Blasen mit konstantem Durchmesser angenommen, die diskret modelliert werden, d.h. ihre momentanen Koordinaten werden durch Partikeltracking ermittelt. Die Momentangeschwindigkeit einer Blase ergibt sich aus der Vektorsumme der Geschwindigkeit der Flüssigkeit am Ort der Blase und der Relativgeschwindigkeit der Blase als Folge des lokalen Druckgradienten. Die Blasenkoaleszenz wird nicht berücksichtigt. Die Blasen verlassen das Strömungsgebiet bei Erreichen des oberen Randes. Es wird angenommen, daß jede einzelne Blase eine Kraftwirkung auf die Flüssigkeit verursacht, die in der Wirbeltransportgleichung im Volumenkraftterm berücksichtigt wird. Hierbei wird näherungsweise eine Dirac-Funktion angenommen, deren Stärke der Auftriebskraft entspricht. Die Kraftwirkungen aller Blasen im Strömungsgebiet werden addiert. Rechenergebnisse für eine rechteckige Strömungsbox mit Gaseinspeiusung über eine oder mehrere im Boden angeordnete Kanülen zeigen die Anregung von Wirbeln, die zu einer Deformation der Blasentrajektorie führen. Dabei treten typische typische instationäre Zirkulationszellen auf. Wichtig ist, daß die spektralen Verfahren auch bei Begrenzung auf wenige Moden in der prinzipiell Lage sind, großräumige Zirkulationszellen in der Blasensäule zu beschreiben. Klassische Verfahren erfordern demgegenüber stets eine feine räumliche Nodalisierung. Hieraus folgt, daß mit spektralen Verfahren grundlegende Erkenntnisse bei Anwendung von Wenigmodenmodellen mit geringem Rechenaufwand erzielt werden können.

The AER benchmark problem defined by L. Korpas et al. for the calculation of VVER­440 control rod worth was solved by using the code DYN3D in 1994. The KAB MAGRU library, generated by the NESSEL code was used then as a source of macroscopic group data. Now DYN3D calculations have been repeated with a new group data library created in EGP Prague by the KASSETA code. Burnup calculations have been carried out for the cycles 4 to 7 of Paks­2 NPP. The critical boron concentrations as a function of time, calculated with both data libraries, were compared to the values measured in the progress of the cycles. The results are in good agreement. The comparison of the fuel­element averaged burnup values after calculating 4 full cycles shows a maximum deviation of about 2 percent between the two data libraries. Concerning the control rod efficiencies the relative deviation is higher. This is due to relatively great differences in the macroscopic group data produced for the control rod!
s by NESSEL and KASSETA. The deviations between results calculated by the same code with different group data indicate that using different data libraries by the AER benchmark participants may be a main reason for the high differences between their results.

The preliminary results of the activation measurements and calculations in the different points of the irradiation facility KORPUS are shortly described and analyzed. The tasks of these investigations are the dosimetry characterization of the facility and creation of the international dosimetry benchmark.

A series of three-dimensional hexagonal dynamic benchmark problems have been defined during 1992 - 1994 in the international VVER cooperation forum AER. All three problems are asymetric control rod ejections from low power level in a realistic VVER-440 core with fuel of three different enrichments and given nuclear data. However, the complexity of the models needed in the benchmark solutions is continuosly increased beginning from pure reactor kinetics and extending to real core thermal hydraulics modelling with a hot channel and DNB effects. Solutions calculated by six organizations with five different mostly nodal codes are included. Agreement of neutron kinetics results is very good. More differneces are induced by thermal hydraulics modelling.

The capability of neuronal networks and fuzzy pattern classification is compared using measuring data that originate from experiments on leakage detection. The classification procedures are to localize simulated acoustically active leaks and to determine the leak rate. Different types of neural networks are needed to perform these two tasks. Alternatively fuzzy classifiers can be applied. Concerning the generalization capability, i.e. the recognition of positions and leak rates that could not be trained, neural networks clearly superior over fuzzy classification.

The new version DYN3DR of the code DYN3D/M2, initially designed for hexagonal-z
core analysis, has been developed for reactor cores with rectangular fuel assemblies.
The neutronic part of the two code versions can be used for steady-state and transient
calculations of reactor cores. The neutron kinetics in both versions is based on the
solution of the two group neutron diffusion equation by nodal methods being different
for hexagonal and rectangular geometry. The thermal-hydraulic module FLOCAL
simulating the two phase flow of coolant and the fuel rod hehaviour is used in both
versions. The accuracy of DYN3DR is demonstrated by comparisons with rod ejection
benchmarks for a PWR with rectangular fuel assemblies. The two phase flow model of
FLOCAL also allows the simulation of BWR transients. Results for the transient BWR
benchmark initiated by increase of inlet subcooling are shown.

The neutron kinetic part is parallelized for running on SUN workstations with several
processors. The speedup for steady state neutronic calculations is presented.

The coupling of advanced thermohydraulic codes with 3-dimensional neutron kinetic codes corresponds to the effort to replace conservative estimations by best estimate calculations. ATHLET is an advanced thermohydraulic code, developed by the German "Gesellschaft für Anlagen- und Reaktorsicherheit" (GRS). The DYN3D code, developed at Forschungszentrum Rossendorf (FZR) for the simulation of reactivity initiated accidents in nuclear reactors with hexagonal and Cartesian fuel element cross section geometry comprises 3-dimensional neutron kinetics, models for the thermohydraulics of the core and the thermomechanical fuel rod behaviour.

The reactor core model DYN3D was coupled with ATHLET according to two basically different strategies. The first way of coupling uses only the neutron kinetics part of DYN3D (internal coupling). In the second way, the whole core is cut out from the ATHLET plant model and is completely described by DYN3D (external coupling). In this case the values of pressure, mass flow rate, enthalpy and boron acid concentration at the bottom and at the top of the core have to be transferred between the codes. This way of coupling is efficiently supported by the General Control and Simulation Module (GCSM) of ATHLET. Almost no changes of the single programs are necessary.

For plausibility test of the code coupling, comparative calculations between point kinetics, internal and external coupling were performed for different hypothetical accident scenarios. First results of the analysis of a main steam line break scenario for a VVER-440 type reactor by the help of ATHLET-DYN3D are presented. The effect of different assumptions for the coolant mixing in downcomer and lower plenum of the reactor has been investigated.

Two heats of reactor pressure vessel steel type A533-B-1 differing in their Cu content (0.07 and 0.14 wt.-%) were irradiated to a fluence of 1x1018 neutrons/cm2 at temperatures of 60, 121, and 288 °C, respectively. Their microstructure has been studied by SANS, SAXS, and PAS in the as-irradiated and post-irradiation annealed stages and compared to the behaviour of unirradiated material and the results are discussed.

The knowledge about properties of the anisotropic turbulence in liquid metal flows exposed to an external magnetic field is essential for several technological applications such as the concept of a selfcooled liquid metal blanket for thermonuclear fusion reactors, but also of basic interest for turbulence research. Flow parameters like pressure drop and heat transfer rate are essentially determined by the interaction between the external magnetic field and the liquid metal flow. Several experimental studies revealed that the application of a magnetic field leads not exclusively to a suppression of the turbulent perturbations. Velocity fluctuations remain and demonstrate a distinct anisotropy of the MHD turbulence showing a tendency to become two-dimensional. The properties of the local transport of heat or mass are strongly governed by the anisotropic character of the flow. In this context a number of questions arises regarding the origin, the decay time or the size of the turbulent elements. A typical feature of the two-dimensional turbulence is that the energy becomes concentrated in organised large scale fluctuations. This fact ensures an intensive heat transfer on longer distances. Because of the anisotropy of the electromagnetic dissipation term vortices will be scarcely damped over long distances if their axes are aligned with the magnetic field lines. For practical applications it is important to identify possibilities to promote the formation of such quasi-two-dimensional vortices in order to control the heat or mass transfer rate of the flow. It is well-known that the mentioned perturbations can be generated by rather specific means, for example, mechanical inserts or electrical currents between definitely arranged electrodes, etc.. In this paper we force the turbulence intensity by mechanical means employing a grid of cylindrical bars or flat stripes. Due to the favourable material properties of the used liquid sodium we are able to extend the measurements into the region of high interaction parameters. In this way the obtained results complement the already existing knowledge about the two-dimensional MHD turbulence.

In order to improve the operational surveillance of a VVER-1000 unit of the Ukrainian nuclear power plant Zaporosh'ye a technical monitoring system has been specified and installed during the last three years.
The technical system enables the operator and supervisory body to monitor the core and the unit continuously during normal and off-normal conditions, to assess the safety status of core and unit, and to impose appropriate measures. The system provides an early indication of any operational incident and of emissions of radioactive materials. Based on the system an immediate warning in emergency situations is possible as well as an effective emergency management. For this purpose 49 different safety related operational parameters of the core and unit - e.g.: neutron flux, pressure - primary and secondary circuit, fuel rod outlet water temperature, boron concentration - primary circuit and so on -, 18 radiological parameters of the unit and the plant side and 6 meteorological parameters are automatically monitored and evaluated.
The system was put into operation at the end of 1995. It is now working under test conditions.
The paper presents the technical solution of the system and the evaluation principles. Additionally the paper gives a short overview about the results obtained during the test operation of the system.

A technical system to improve the operational monitoring of the Zaporozh'ye NPP as a tool for the supervisory authority is presented. The system is mainly directed to monitoring the operational data for early detection of, and information about, anomalous events and gives input data for source term estimation. Additionally, radiological data from the site and the environment as well as meteorological data are integrated in the system for pollution transport calculations. Thus the system's information is well suited to becoming a data source for RODOS system.

The present work is aimed at the investigation of two-phase flow in vertical pipes. Even under these very simple boundary conditions, strong 3D effects are observed. The distribution of the gas phase over the cross section varies significantly between the different flow patterns, which are known for the vertical two-phase flow. The paper presents a new device for measuring the void distribution with a high resolution (242 mea-suring points in a cross section area, measuring frequency approx. 1 kHz). This high resolution allows the calculation of local and averaged void fractions, a flow pattern visualization and the determination of bubble size distributions. Bubble flow appears with void center and boundary maximum distribution. The bubble size distribution allows the classification of the transition from homogeneous to inhomogeneous bubble flow and bubble to slug flow. These criteria are compared with selected empirical or theoretical flow pattern maps. The measurements are also used to assess the capability and the accuracy of the code CFX-4.2. The 3D calculations were still only successful for bubble flow, while the experiments were carried out in a wide range of superficial velocities, including other flow patterns like plug or churn turbulent flow.

The Siemens AG is developing the new innovative boiling water reactor concept SWR1000. New features are the passive safety systems (e.g. emergency condensers, building condensers, passive pressure pulse transmitters, gravity-driven core flooding lines).

For the experimental investigation of the emergency condenser effectiveness, the NOKO test facility has been constructed at the Forschungszentrum Jülich in cooperation with Siemens. This test facility has an operating pressure of 10 MPa and a maximum power of 4 MW for steam production. The emergency condenser bundle consists of eight tubes and is fabricated with planned geometry and material of the SWR1000. In more than 200 experiments, the emergency condenser power was determined as a function of pressure, water level and concentration of noncondensables in the pressure vessel as well of pressure, water level and temperature in the condenser.

Post test calculations of NOKO experiments were performed with an improved version of ATHLET. To calculate the heat transfer coefficients during condensation in horizontal tubes it was necessary to develop the module KONWAR and to implement it in ATHLET. KONWAR is based on the flow regime map of Tandon and includes several semiempirical correlations for the determination of the heat transfer coefficients. The comparison bet-ween calculations and experiments shows good agreement.

Am 29. Oktober 1998 veranstaltete die Ortssektion Sachsen der Kerntechnischen Gesellschaft e.V. an der TU Dresden ein Seminar zum Thema "Experimentelle Untersuchungen zur Wirksamkeit passiver Komponenten für den SWR1000". Diese Thematik erhielt u. a. durch das von Siemens beantragte standortunabhänige Prüfverfahren (vgl. atw 43 (1998), Nr. 10, S. 650) sowie der am 5. November in Königswinter durchgeführten KTG-Tagung "SWR1000 - ein zukunftsweisendes Reaktorkonzept" eine besondere Aktualität. In dem derzeit von der Siemens AG entwickelten innovativen Siedewasserreaktor SWR1000 werden zur Erhöhung der Sicherheit und der Wirtschaftlichkeit aktive Sicherheitssysteme weitestgehend durch passive ersetzt oder mit diesen kombiniert. Hierzu zählen die nachfolgend im Detail beschriebenen Systeme Notkondensator, Gebäudekondensator sowie Passiver Impulsgeber.

The condensation in horizontal tubes plays an important role e.g. for the determination of the operation mode of horizontal steam generators of VVER reactors or passive safety systems for the next generation of nuclear power plants. Two different approaches (HOTKON and KONWAR) for modeling this process have been undertaken by For-schungszentrum Jülich (FZJ) and University for Applied Sciences Zittau/Görlitz (HTWS) and implemented into the 1D-thermohydraulic code ATHLET, which is developed by the Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH for the analysis of anticipated and abnormal transients in light water reactors. Although the improvements of the condensation models are developed for different applications (VVER steam generators - emergency condenser of the SWR1000) with strongly different operation conditions (e.g. the temperature difference over the tube wall in HORUS is up to 30 K and in NOKO up to 250 K, the heat flux density in HORUS is up to 40 kW/m² and in NOKO up to 1 GW/m²) both models are now compared and assessed by Forschungszentrum Rossendorf e.V. Therefore post test calculations of selected HORUS experiments were performed with ATHLET/KONWAR. It can be seen that the calculations with the extension KONWAR as well as HOTKON improve significantly the agreement between computational and experimental data.

Free surfaces of liquid gallium and mercury were studied by light scattering from thermally exited capillary waves. Great precautions were taken to prepare an oxide-free liquid metal surface inside a small evacuated container. Experimental results are shown in the form of q dependencies of the wave peak frequency wo and the damping constant ?. The observed damping constants of capillary waves differ greatly from those predicted by the classical theoretical treatment of Hg and Ga surfaces as those of simple liquids. This effect is explained in terms of the presence of a surface layer of highly correlated atoms accompanying the liquid-vapor transition. Viscoelastic properties of surface layer are extracted from the fit of experimental spectra with a theoretical form utilizing a well known phenomenological model. Results of the fit demonstrate that the surface viscosity appears to be negative. This implies that the widely used phenomenological model should be replaced by another one incorporating the Maxwell viscoelastic model. Special point has been made on studying the temperature dependence of the wave peak frequency at the free and oxidized Hg surface. This dependence emphasizes negative derivative of the surface tension d?/d? linked with the spatial distribution of free electrons being much
stronger temperature dependent than local surface ordering recently revealed at the mercury-vapor interface. In contrast, ?o(?) dependence collected at the Hg-HgO interface displayed two principally different tendencies: it increased steadily on the Hg surface covered with an oxide monolayer but was nearly constant at the surface covered with a polymolecular film of HgO. This behavior is discussed in the framework
of various theoretical models.

The report deals with the results of ATHLET post-test calculations for an experiment at the Hungarian integral test facility PMK-2. The experiment „pressurizer surge line break" was carried out within the PHARE 4.2.6b project. The primary objective of this test was to provid data for the phenomena associated with a pressurizer surge line break transient. The post-test analyses were performed with ATHLET mod1.1 Cycle C by the Forschungszentrum Rossendorf (FZR) and with ATHLET mod1.1 Cycle D by the Atomic Research Institute Budapest (KFKI) and the Gesellschaft für Anlagen- und Reaktorsicherheit (GRS).

Perinatal hypoxic-ischemic cerebral injury is a major determinant of neurologic morbidity and mortality in the neonatal period and later in childhood. There is evidence that the dopaminergic system is sensitive to asphyxia. However, the respective enzyme activities have not yet been measured in the living neonatal brain. In this study, we hav used F18-labeled 6-fluoro-L-3,4-dihydroxyphenylalanine (FDOPA) together with positron-emission tomography l(PET) to estimate the activity of the aromatic amino acid decarboxylase (AADC), the ultimate enzyme in the synthesis of dopamine (DA), in the brain of newborn piglets. Simultaneously, the cerebral blood flow (CBF) was measured with colored microspheres. Asphyxia elicited an up to threefold increase of the CBF. Despite this, the blood-brdain transfer of FDOPA as well as the clearance rate constants from brain were unchanged. However, the synthesis rate of FDA from FDOPA was significantly increased in frontal cortex, striatum, and midbrain. The increase of the AADC activity and the decrease of monoamine oxidase activity may contribute to the increase of extracellular DA during asphyxia which is expected to be involved in severe disturbances of neuronal metabolism, e.g., by generating free radicals.

Abstract. The paramagnetic rhenium (II) thionitrosyl compounds trans-[Re(NS)Cl3(MePh2P)2] and trans-[Re(NS)Br3(Me2PhP)2] are characterized by crystal structure diffraction and EPR spectroscopy. Trans-[Re(NS)Cl3(MePh2P)2] is formed during the reduction of (a) [ReNCl2(MePh2P)3] with disulphur dichloride (S2Cl2) or (b) of mer-[ReCl3(MePh2P)3] with trithiazyl chloride ((NSCl)3). Trans-[Re(NS)Br3(Me2PhP)2-] is the final product of the ligand exchange reaction of mer-[Re(NS)Cl2(Me2PhP)3-] with bromine whereby the metal occurred to be simultaneusly oxidized.
The crystal structure analyses show for trans-[Re(NS)Cl3(MePh2P)2] (monoclinic, C2/c, a = 13.831 (3) C, b = 13.970 (1) C, c = 14.682 (2) C, b = 95.33 (1), Z = 4) and trans-[Re(NS)Br3(Me2PhP)2-] (monoclinic, C2/c, a = 33.292 (5) C, b = 8.697 (1) C, c = 17.495 (3) C, b = 115.65 (1), Z = 8) linear co-ordinated NS ligands (Re - N - S - angles 180° and 174.8°). The metal atom is octahedrally co-ordinated with the phosphine ligands in trans position to each other.
X-band and Q-band EPR spectra of the rhenium (II) thionitrosyl complexes (5d5 "low-spin" configuration, S = 1/2) are detected in the temperature range 295 ³ T ³ 130 K. They are characterized by well resolved 185,187Re hyperfine patterns.
The hyperfine parameters are used to get information about the spin-density distribution of the unpaired electron in the complexes under study.

Keywords: Thionitrosyl compounds, Rhenium complexes, EPR spectroscopy, X-ray structure

Doses from 2 x 10¹⁵cm^-2 to 2 x 10¹⁷cm^-2 of ⁵⁷Fe ions were implanted with 40 keV into n-type Si(111) at 350°C. The iron concentration profiles reach peak maximum concentrations from 0.3 at.% for the lowest dose up to about 34 at.%. For the highest dose a plateau-like profile is formed due to the effect of sputtering. The phase formation of the iron disilicides was studied by ⁵⁷Fe conversion electron Mössbauer spectroscopy. Depending on the implanted dose two different regions of phase formation are found. For doses £ 1 x 10¹⁶cm^-2 only the metastable g-FeSi₂ is present whereas at values ³ 2 x 10¹⁶cm^-2 a mixture of a- and b-FeSi₂ is formed. The phase composition in this second region is dose dependent and with increasing iron content an enlarged fraction of the b-phase is found. At the highest dose of 2 x 10¹⁷cm^-2 mostly b-FeSi₂ and no a-FeSi₂ is present. But additionally to the b-FeSi₂ a second component occurs in the Mössbauer spectrum which is observed for the first time. With respect to the iron concentration this subspectrum could be attributed to a new metastable state of the mono silicide. Different annealings of the as-implanted samples at 900°C and 1150°C lead to the formation of the pure b- and a-FeSi₂, respectively. Additionally to the measurements of the concentration profiles investigations of the lateral element distributions in the layers were performed with scanning Auger electron microscopy. It can be concluded that during the annealing at 1150°C precipitates of the a-FeSi₂ grow in the Si matrix.

Es wird ein Überblick über den Entwicklungsstand und die Anwendung von Computercodes mit Kopplung von thermohydraulischen Anlagenmodellen von Kernkraftwerken und 3D Neutronenkinetik gegeben. Insbesondere wird auf die Ankopplung von Neutronenkinetikmoduln an den Thermohydraulikcode ATHLET eingegangen. Es werden Arbeiten zur Validierung der Codekomplexe durch Nachrechnung von transienten Prozessen in Kernkraftwerken und internationale Programmvergleiche beschrieben. Die Anwendung von ATHLET mit gekoppelter 3D Neutronenkinetik für Störfallanalysen wird an 2 Beispielen demonstriert. Mit den gekoppelten Programmsystemen sind erstmals konsistente Störfallanalysen ohne zusätzliche konservative Annahmen möglich. Entwicklungsbedarf besteht noch bei der Berücksichtigung von 3D Temperatur- und Borkonzentrationsverteilungen innerhalb des Reaktors,
die den hypothetischen Störfallablauf wesentlich beeinflussen können.

A possibility for the determination of velocity fields in conducting fluids is presented. Applying a magnetic field from outside, electric and magnetic fields are induced by the fluid motion. These fields can be measured at the walls and outside the fluid volume respectively. The inverse problem of reconstructing the velocity from the measured electric and magnetic fields is solved using Tikhonov regularization.

The mono oxo rhenium(V) complexes of cysteine and cysteine methyl ester were synthesised via ligand exchange reaction starting from rhenium gluconate. Unexpectedly, the obtained oxo Re(V) complex with cysteine methyl ester was partially saponified. Both complexes were fully characterised by common analytical techniques in their solid state. Thus, an octahedral complex structure with 2(NH2,S) coordination in the equatorial plane and one carboxyl group bound trans to the oxo group is proven for both compounds by X-ray diffraction. Furthermore, the existence of a dioxo species at higher pH was proven for the first time with this type of ligands by determing the nearest coordination sphere of the rhenium centre in solution at a pH of 12 using extended x-ray absorption fine structure spectroscopy (EXAFS).

The diastereoselective synthesis of 6-aroyl-3,5-diarylspiro[cyclohexa-2,4-diene-1,2´-indolines] 4 possessing three stereocenters from 2,4,6-triaryl-pyrylium perchlorates 1 and chiral methyleneindolines 3, generated in situ by deprotonation of the corresponding 3H-indolium perchlorates 2, in the presence of triethylamine/acetic acid in ethanol by a 2,5-[C4+C2] pyrylium ring transformation is reported. Structure elucidation is performed by X-ray structure determinations of the spiro[cyclohexadiene-indolines] 4a, 4p and 4t. The influence of various substituents at C-3 of the methyleneindolines 3 on the stereochemistry of the transformation, mechanistic details as well as spectroscopic data of the products 4 are discussed.

In the course of our investigations into mixed ligand systems containing thiol residues, we have examined, among others, the reactions of bidentate aminethiols with monodentate thiols, as well as tridentate/monodentate mixed ligand systems in the presence of ReOCl3(PPh3)2. Mixed ligand complexes of the general type "2+1+1" and "3+1" have been isolated. Surprisingly, in our synthetic attempts to clarify the mechanism of such reactions, we revceived two unexpected cis-dioxorhenium(V) P,S,N-coordinated complexes, where the aminethiol acts as a bidentate ligand over the Re(V) precursor. The two novel complexes of the general formula ReO2[R2NCH2CH2S][PPh3] where NR2=NEt2 (Complex 1) and NR2=N(CH2CH2)2C(OCH2)2 (Complex 2) are presented below. Both complexes have been characterized by elemental analysis and spectroscopic methods. Crystallographic studies show that the coordination geometry around rhenium is trigonal bipyramidal with the two cis-oxo groups and the sulfur atom of the ligand occupying the basal plane, while the nitrogen of the ligand and the phosphorus occupy the apical positions.

In the REBEKA-test facility of the Karlsruhe Research Centre (FZK) temperature-transient single-rod creep burst tests on Zirconium-Niobium 1 (ZrNb1) cladding tubes of Russian VVER reactors have been performed under conditions simulating a loss-of-coolant accident (LOCA). For the time being the test results obtained allow a comparison of the burst behaviour of ZrNb1- and Zircaloy-4 (Zry4) cladding tubes. The burst temperature and burst strains, respectively as influenced by the burst pressure, burst temperature and heating rate exhibit in the phase transformation temperatures which are up to 100 K lower for ZrNb1 compared to Zry4. For a reliable description of the ZrNb1 cladding behaviour in a LOCA further experimental and theoretical research work is needed.

A joint Russian/German irradiation experiment was performed at the pressurized water reactor VVER 2 of the Rheinsberg NPP (Germany). The experiment comprises about 800 Charpy V-notch, SENB and CT specimens made from 24 different heats of Russian type RPV base and weld metals.
Comprehensive calculations of the neutron fluence were carried out. A multigroup Monte Carlo method allows the calculation of the neutron fluence of each specimen or of different points within a large specimen under consideration of the details of the geometric arrangement. As the calculations shown the neutron fluence considerably varies over the cross section of an irradiation rig. Therefore, influence of the flux gradients on testing of Charpy V-notch and CT-specimens is evaluated.
Methods taking into account a fluence correction of the measured absorbed energies are presented and discussed

The report deals with results of ATHLET calculations for the Hungarian test facility PMK-2. The test facilty is a 1:2070 scaled
down model of a VVER-440 reactor. The calculated experiments includes a „inadvertent opening of the pressurizer safety valve"
and a „pressurizer surge line break". Both experiments were carried out within the PHARE 4.2.6b project. For the calculations
the code ATHLET mod1.1 Cycle C was used. The results of the calculations were compared with the experimental data.

Membranzellen für elektrochemische Reaktionen unter Bildung gasförmiger Produkte (z. B. Chlor, Sauerstoff, Wasserstoff) unterscheiden sich von herkömmlichen Blasensäulenreaktoren durch die Bildung feiner Gasbläschen an der festen Oberfläche der Elektroden und durch eine Begasung der Flüssigkeit über die gesamte Zellenhöhe. Gegenüber reinem Wasser bewirken Zusätze von anorganischen Elektrolyten mit kleinen Anionen eine Behinderung der Koaleszenz der Gasblasen. Zur Untersuchung der Zweiphasenströmung in einer solchen Anordnung wurde eine Nachbildung der Elektrodenreaktion mit Gasentwicklung durch die katalytische Zersetzung von Wasserstoffperoxid an Platin realisiert. Als Blasensäule dient ein Plexiglasrohr mit einem Innendurchmesser von 52 mm. Zentrisch im Rohr ist der Katalysator, ein mit Platin beschichtetes Titanrohr, angeordnet. Der volumetrische Gasgehalt der Dispersion wird mittels über die Säulenhöhe angeordneten Differenzdruckaufnehmer gemessen. Die Volumenstromdichte an Gas steigt linear mit der Säulenhöhe an. Bei kleinen Gasbelastungen (Gasvolumentrom pro aktive Katalysatorfläche) und geringen Eintrittskonzentrationen des Wasserstoffperoxids bildet sich erwartungsgemäß eine homogene Blasenströmung heraus. Ab einem Gasgehalt von ca. 20% gewinnt die Schwarmbehinderung an Einfluß auf die Blasenströmung. Der Gasgehalt der Dispersion wächst überproportional an. Nehmen Gasbelastung und Anfangskonzentration des Wasserstoffperoxids größere Werte an, geht die Blasenströmung in eine Schaumzone über. Im untersuchten Lastbereich erstreckt sich der Schaum bis zu ca. 68% des Reaktionsvolumens. Unabhängig von der örtlichen Volumenstromdichte an Gas werden hier über mehrere hintereinander geschaltete Meßvolumina gleiche Gasgehaltswerte gemessen, d.h. der Zuwachs an eingetragenem Gas wird durch das Anwachsen der mittleren Aufstiegsgeschwindigkeit des Blasenschwarms infolge von Koaleszenz kompensiert. Hinsichtlich seiner Stabilität kann der Schaum als kurzlebig charakterisiert werden. Es wurden Schaumzerfallszeiten im Bereich von 40 Sekunden gemessen.

LOCA experiments are characterized by a more or less rapid primary pressure decrease in the early phase of the transient. After
pump coast down natural circulation becomes the dominant decay heat removal mechanism. After leak initiation boiling in the
reactor core leads to formation of two-phase flow conditions in the primary circuit. At these conditions different types of
two-phase flow instabilities can appear. The instabilities play an important role in the behaviour of the primary circuit, because the
instabilities can disturb the decay heat removal from the reactor core.

At the PMK-2 test facility natural circulation instabilities could be detected in 3 different experiments: a 1% cold leg break, a 1%
cold leg break with primary bleed and a surge line break.

With the help of the presented calculations it could be shown, that ATHLET is able to calculate the accident behaviour in a good
agreement with the experimental data. All significant phenomena, such as hot and cold leg loop seal clearing, stagnation of the
natural circulation, phase and mass separation along the facility and especially the natural circulation instabilities are calculated
very well. In some cases the ATHLET calculation provide the more detailed information required to clarify the complex
processes connected with the different kinds of instabilities.

Verschiedene Methoden zur Ermittlung der STC-Leistung von Photovoltaik-Generatoren aus gemessenen Kennlinien werden vorgestellt und diskutiert. Dabei handelt es sich um Varianten einer ursprünglich auf Blässer zurückgehenden Methode. In nahezu allen untersuchten Fällen wurden Generatorminderleistungen bis zu 25%, in Einzelfällen sogar mehr, festgestellt. Die erzielten Ergebnisse haben Konsequenzen auf die Bewertung von Erträgen von PV-Anlagen.

Collecting measurement data of NPP transients will be of key importance for the validation of coupled thermohydraulics / neutron kinetics codes. The transient data should cover relevant effects caused by the interaction between 3D neutron kinetics and thermohydraulics. Data will be collected for both VVER types (VVER­440 and VVER­1000).

Um sich ein besseres Bild über die Strömungsvorgänge im Downcomer und im unteren Plenum eines Druckwasserreaktors machen zu können, wurde mit einem CFD-Code (CFX 4.1) die Strömung unter möglichst realen Randbedingungen nachgerechnet. Hierfür wurden uns freundlicherweise Meßdaten des Anfahrvorganges der Hauptkühlmittelpumpe des DWR Konvoi zur Verfügung gestellt. Die Nachrechnung realer Anfahrvorgänge des DWR Konvoi mit Hilfe von IBS-Meßdaten zeigten eine relativ gute Durchmischung des Kühlmittels im unteren Plenum. Interessant war es festzustellen, daß das Geschwindigkeitsmaximum im unteren Downcomerbereich wie ein Halbkreis um den angefahrenen Stutzen liegt. Unterhalb dieses Stutzens ist die Geschwindigkeit vermindert.

The radiation embrittlement of the reactor pressure vessel is highly safety-relevant for VVER-type pressure vessels. The sensitivity against radiation embrittlement depends on the chemical composition of the pressure vessel steel. Using an irradiation experiment at surveillance positions in two Russian VVER 440-type reactors the effects of copper, phosphorus and nickel on the radiation embrittlement should be investigated. For that, eight mock-up alloys were selected. Their chemical composition varied between 0.015 and 0.42 % Cu, 0.002 and 0.039 % P, 0.01 and 1.98 % Ni, 0.09 and 0.37 % Si, and 0.35 and 0.49 % Mn. Charpy-V impact tests and tensile tests were performed with specimens machined from these alloys. The specimens were tested in the as-received state, in the irradiated state (fluence: 1x10¹⁹ and 8x10¹⁹ /cm² [E>0.5 MeV]) an in the post-irradiation annealed state. In the as-received state, the alloys have a ferritic microstructure. Apart from Cu, the alloyed elements are solved in the matrix.
Irradiation produces strong hardening and embrittlement. The effect increases with the Cu and P content. Ni causes an additional embrittlement. It is independent on the Ni concentration within the range of 1.1 to 2 % Ni and results in a shift of the ductile-brittle transition temperature of about 120 °C after a fluence of 1x10¹⁹ /cm² by a flux of 4x10¹¹ /cm²s. The shift does not depend on the Cu or P content. Furthermore the upper shelf energy is especially reduced by the Ni-rich alloys. For very low content of Cu and P these relations are not valid. The irradiation effect can be eliminated by annealing at 475 °C /100 h. For high content of Cu or P the recovery is incomplete, it remains a residue of 20 to 25 % of the irradiation effect. Ni has no influence on the recovery.
Comparing the results of this study with the ones of the surveillance programmes of the VVER 440-type reactors, the alloys with low Ni content show the same irradiation behaviour as the weld metal. For the Ni rich alloys such well-walidated references are missing.
The experiment is part of an extended research programme. It supposed to continue in order to gain information about the synergistic effects of these elements.

Two mechanisms are proposed for the theoretical description of the dilational viscoelasticity on a liquid surface. Possible relaxations of the temperature and electric charges induced due to the passage of the transverse-longitudinal surface waves are discussed. The dilational viscosity of the liquid metal surface can be realistically estimated from the charge oscillations model.

Usually the action of steady magnetic fields on electrically conducting flows is a damping one. But several examples exist where additional instabilities are due to the magnetic field influence. Such examples will be listed up based on a classification of the various MHD actions. The physical reason for these phenomena and possible applications will be discussed.

The application of an external magnetic field to the flow of any electrically conducting fluid can drastically change the flow characteristics, particularly for highly conducting fluids like liquid metals or semiconductor melts. If the magnetic field is steady there is the general expection that the magnetic field influence is a damping one: suppression of instabilities, turbulence damping up to relaminarization, suppression of vortex shedding, etc. Indeed, several metallurgical applications of magnetic fields are based on the assumption that this action always consists of a strong damping. The primary action of a steady magnetic field is an anisotropic redistribution of vorticity. If this results in flow damping depends strongly on the question how the induced electric currents can close in the liquid volume. In the present lecture we give some examples from our research projects in the field where a destabi-lizing action of a steady magnetic field was found, even resulting in a serious increase of turbulence intensity for increasing magnetic field. First example is a simple liquid metal duct flow. Experimental results will be presented showing that by a suitable promotion of vorticity parallel to the magnetic field lines the turbulence intensity (and correspondingly the heat & mass transfer) is increased by factors 4 to 10 compared to both the non-magnetic case and the case without turbulence promoters. The turbulence intensity can even increase with growing distance from the turbulence promoter. A physical interpretation will be given. Second example is the standard hydrodynamic problem of a flow around a circular cylinder. 2-D and 3-D numerical simulations will be presented showing clearly the suppression of the Karman vortex street due to the magnetic field influence, but also the destabilizing magnetic field action: 3-D instability is found for Re=180, a Reynolds-number where the pure hydrodynamic flow is known to be 3-D stable. Due to the magnetic field action the Squire Theorem is no more valid and, indeed, 3-D instability is found at parameters where the flow is 2-D stable. Physical interpretation and comparison with experimental results will be given. Further examples for a destabilizing magnetic field action will be briefly mentioned: flows driven by thermoelectricity, steady magnetic field influence on an inductively stirred melt. These experimental results will mainly be shown by video sequences.

In order to predict type and amount of defects created by keV ions under realistic implantation conditions a combination of computer simulations based on the binary collision approximation (BCA) with classical molecular dynamics (MD) calculations is proposed. Time-ordered BCA simulations are applied to ballistic processes with characteristic energies above several 10 eV. Athermal, rapid thermal, and thermally activated processes with lower characteristic energies are treated by MD simulations. They yield the as-implanted defect state formed several 10 ps after ion impact. The MD calculations are performed in cells which are much smaller than the entire volume of the collision cascade of an incident ion but much larger than the distance between nearest neighbour atoms in the lattice. The as-implanted damage produced by a single ion in a certain cell is found to be completely determined by the nuclear energy deposition of the ion into the cell. Therefore, the MD calculations need to be performed
only in one cell for different values of nuclear energy deposition, and statistical considerations based on BCA simulations can be employed to obtain the depth profile and the total number of different defect species (vacancies, interstitials, disordered atoms, etc.) created on average per incident ion.
The novel simulation method is applied to investigate the damage morphology produced by 15 keV B, 30 keV P, and 15 keV As implants.

Maintaining the integrity of the reactor pressure vessel (RPV) is of highest safety priority. The task is not trivial because the material is exposed to operation conditions that change the material properties and consequently reduce the safety margins. In the common view, this concerns above all the effects of neutron irradiation, which causes a reduction of the toughness. It is state-of-the-art to monitor the effect by an in-service surveillance programme. Recently, there are results that further environmental degradation effects could be of significance. Primarily the influence of gamma radiation and the irradiation-induced hydrogen embrittlement could also affect the material behaviour. Gamma rays produce a high rate of surviving point defects, which can accelerate ageing embrittlement. Hydrogen reduces the fracture toughness of RPV steels. Enhanced uptake of hydrogen can locally occur due to the radiolysis of water in water-starved condition existing in gaps or cracks. Irradiation defects can trap hydrogen and, thus, the hydrogen concentration can increase additionally. Several results are shown and the consequences for the RPV safety assessment and the embrittlement monitoring are discussed.

Es wurde die Eignung von [1-11-C]-Acetat zur quantitativen Perfusionsbestimmung in der myokardialen PET untersucht. Bestimmt wurde zum einen die Flußabhängigkeit der Acetatextraktion anhand eines Vergleichs mit dem derzeitigen Standardtracer 13-NH3, zum anderen wurde die statische Güte der mit beiden Tracern abgeleiteten Perfusionswerte untersucht.

Investigations concerning the "n+1" concept for the preparation of mixed-ligand technetium and rhenium complexes are briefly summarized. Chemical extensions were made with the aim to get less lipophilic and more stable chelates and involve the search of new precursor molecules, alternative types of tridentate ligands and new synthetic routes. N.c.a. preparation of "3+1" complexes can be done either by ligand exchange at Tc gluconate or in one step starting from pertechnetate. Aspects of reactivity are briefly discussed, particularly the reaction with glutathione in vivo. "n+1" complexes were preferably used for the design of receptor-binding tracers showing that the "3+1" unit seems to be well-suited to be adapted to receptor-affine anchor groups.