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importance in nuclear technology, as they can be used as a diagnostic tool. While the fission process has been extensively studied since its discovery more than 70 years ago, the energy dependence of the yields of specific fragments in neutron-induced fission is poorly understood. A new instrument, SPIDER, is currently being developed to address this issue by measuring the mass, charge, and kinetic energy of fission fragments as a function of incident-neutron energy. The instrument is based on the 2E-2V method, in which the velocity and kinetic energy of fragments are measured in coincidence to determine their masses. Additionally, by using Bragg peak spectroscopy, the charge of a fragment can be identified. A prototype instrument has been developed, and preliminary results indicate that 1 mass unit resolution is feasible using this approach. A larger detector array is currently being designed, and will be used at the Los Alamos Neutron Science Center (LANSCE) to study fission fragment yields from thermal neutron energies up to at least 20 MeV. Session KE Integral Experiments Wednesday March 6, 2013 Room: Central Park West at 1:30 PM KE 1 1:30 PM What If Lady Godiva Was Wrong? John D. Bess, J. Blair Briggs, Margaret A. Marshall Idaho <strong>National</strong> <strong>Laboratory</strong> The experiment from which benchmark specifications of ”Lady Godiva” were derived consisted of a bare sphere of highly enriched uranium (HEU) comprised of nested hemispheres. That experiment was performed in the early 1950s and the critical configuration was evaluated and published in the International Handbook of Evaluated Criticality Safety Benchmark Experiments in 1995 with the identifier HEU-MET- FAST-001. The benchmark eigenvalue is reported as 1.000 ± 0.001, which is representative of a very high quality benchmark experiment. Our current neutronic codes and cross section data are tailored to provide qualitative results that concur with the Godiva benchmark. But what if our understanding of the experiment wasn’t perfect? Since 1995, a multitude of additional high-fidelity HEU metal benchmark data have been evaluated and published, including data for several assemblies that were performed at the Oak Ridge Critical Experiments Facility (ORCEF) and others at the Russian Federal Nuclear Center - Institute of Technical Physics (RFNC-VNIITF). Furthermore, the rigor through which benchmark experiments are examined has increased over the past two decades. Eigenvalue calculations of the HEU metal benchmark experiments from ORCEF and VNIITF consistently calculate slightly low, possibly indicating that our fast neutron cross section data for 235 U may not be as well known as hoped. It is recommended that we not just reevaluate the Godiva benchmark data, but also evaluate a more recent bare critical sphere experiment performed at ORCEF in 1971. International Handbook of Evaluated Criticality Safety Benchmark Experiments, NEA/NSC/DOC(95)03, OECD-NEA, Paris, France (2012). KE 2 2:00 PM Shielding Design Calculations for the ESS Target Station High Activated Components Daniela Ene, Ferenc Mezei ESS-AB, Sweden 158
The European Spallation Source (ESS) is the European common effort in designing and building a next generation large-scale user facility for studies of the structure and dynamics of materials. The ESS target, moderators and reflectors system through interactions with 5 MW proton beam (2.5 GeV, 20 Hz) will produce long pulse (2.8 ms width) neutrons in subthermal and thermal energy range. These neutrons are further transported to a variety of neutron scattering instruments. The aim of this work is to assess the strategy to be used for safely handling and shipping of the high activated components of ESS target station. For safe maintenance, during operation as well as handling, transport and storage of the components of the ESS target station after their lifetime, detailed knowledge about the activation induced by the impinging protons and secondary radiation fields is required. The Monte Carlo transport code MCNPX2.6.0 was coupled with CINDER90 version 07.4 to calculate the residual nuclide production in the main items of the system: target wheel and the shaft, moderator-reflector plug, beam window plug, shutters. Dose equivalent rates due to the residual radiation were further calculated with the MICROSHIELD and MCNPX codes using photon sources resulting from CINDER. Various decay times after ceasing operation of each component were considered. The activation and decay heat density distributions of all these components together with the derived dose rates were analyzed to assess the best strategy to be used for their safely remove and transport to a hotcell, eventual dismantling, storage on-site and shipping off-site as intermediate level waste packages. The derived photon sources were used afterwards to design the shielded exchange flasks that are needed to remove and transport each component after its lifespan to a hotcell. Design of a multi-purpose cask able to accommodate the different highly activated components and shipping them to external conditioning facility was further developed. For this purpose, the photon source term of each of the analyzed item was derived taken into consideration previously estimated decay time on-site prior the cask loading. The main criterion used for optimization of the thickness and material selection of the shielding of the flasks, in agreement with Swedish legislation and ADR provisions, is that the dose rate must not exceed 2 mSv h −1 on the outer surface and 0.1 mSv h −1 at a distance of 1 m. The calculated parameters for the shield of the components with high dose rates will be used for detailed design and manufacturing of the exchange flasks. Obtained results for the off-site shipping cask are discussed in order to derive the requirements to be fulfilled for the type B(U) package design approval. KE 3 2:20 PM Distribution of Radionuclides in MEGAPIE, a Proton Irradiated LBE Target Bernadette Hammer, Dorothea Schumann, Jörg Neuhausen, Viktor Boutellier, Hans-Peter Linder, Natalia Shcherbina, Michael Wohlmuther, Andreas Türler Paul Scherrer Institute Christof Vockenhuber ETH Zurich At the moment, several technologies are developed to reduce the amount and the radiotoxicity of residual waste from nuclear power plants. Promising techniques that could be employed for this purpose are fast reactors or Accelerator Driven Systems (ADS) that use liquid heavy metal as reactor coolants and/or material for generating fast neutrons in spallation targets. In some of these innovative reactor designs, lead or lead-bismuth eutectic (LBE) is used as the liquid metal. In an ADS, additional radioactivity is formed in the spallation unit by interactions of high energy and secondary particles with the target material. Data on this residue nuclide production are essential for benchmark theoretical predictions as well as analyzing safety hazards of future LBE cooled nuclear facilities during and after operation, including the options of intermediate or final disposal [1]. A prototype of a lead-bismuth spallation target, MEGAPIE (MEGAwatt PIlot Experiment) [2], was operated close to the megawatt regime (0.8 MW) in the spallation 159
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ND2013 2013 International Nuclear D
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Session BF Evaluated Nuclear Data L
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Session DD Nuclear Structure and De
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Hale, G. n+ 12 C Cross Sections fro
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Domula, A. New Nuclear Structure an
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Session KC Evaluated Nuclear Data L
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MacCormick, M. Survey and Evaluatio
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ments. Ivanova, T. Uncertainty Asse
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Arnold, C. Precision Velocity Measu
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19 Abridged Agenda Sunday March 4,
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21 Tuesday March 5, 2013 Time Met E
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23 Thursday March 7, 2013 Time Met
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Book of Abstracts Session AA ND2013
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multi-foil Parallel Plate Avalanche
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A Regional Coupled-channel Dispersi
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show the versatility of the code in
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[h] Table 1: Comparison of all the
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step was to determine which detecto
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In an effort to maintain the qualit
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Advances in Reactor Physics Linking
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sponsored the work presented in thi
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A revolutionary nuclear data system
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done in Ref. [1]. We demonstrate th
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CD 4 2:40 PM Development of a Syste
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with a central cavity where small s
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C. Arnold, E. Bond, T. Bredeweg, M.
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DA 3 4:20 PM Characterization and P
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detectors at the newly constructed
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Lead and lead-based alloys are - am
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of the setup. One option explored i
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DC 2 4:00 PM Improved Capture Gamma
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DC 5 5:00 PM Thermal Neutron Cross
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M.R. Gilbert, L.W. Packer, S. Lille
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Correlations Between Nuclear Charge
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Community’s 7th Framework Program
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we achieve very good separation of
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analysis of neutron leakage spectru
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a lower nuclear temperature than th
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Tungsten occurs naturally in five i
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for the combined use of integral ex
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in XUNDL and bibliographic informat
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former case, more realistic covaria
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WInfried Zwermann, Kiril Velkov, An
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LA-UR-12-23712 The ENDF/B-VII.1 [1,
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comparison of results C/E of fissio
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Session GA Evaluated Nuclear Data L
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Session GC accelerator applications
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Session GD Antineutrinos Tuesday Ma
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M. Fallot, S. Cormon, M.Estienne, V
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for extraction of very rare isotope
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and neutron multiplicity, informati
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as Monte Carlo simulations, and inc
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on its surface. The amplification t
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Page 112 and 113: Strontium-82 Production at ARRONAX
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Page 128 and 129: Concerns about the limits of worldw
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Page 140 and 141: A significant breakthrough in our t
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Page 154 and 155: KC 2 2:00 PM R-matrix Analysis for
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Page 160 and 161: source SINQ (Swiss Spallation Neutr
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Page 166 and 167: LA 5 5:00 PM Measurements relevant
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Page 176 and 177: LC 5 5:00 PM Uncertainty Study of N
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Page 180 and 181: Session LE Evaluated Nuclear Data L
Page 182 and 183: LE 5 5:00 PM Method of Best Represe
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Page 186 and 187: Impact of the Energy Dependent DDXS
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Page 194 and 195: NC 3 11:20 AM Propagation of Nuclea
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egions: the resolved resonances ran
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y the screening potential predicted
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[1] Y. Kojima et al., Nucl. Instr.
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y the emitted neutron. The Versatil
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enchmarking, the excitation functio
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PA 1 3:30 PM Investigation of Neutr
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as well as for a variety of Minor A
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Society, Vol. 59, No. 2, August 201
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A. Hermanne, R. Adam-Rebeles Cyclot
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We measured the isomeric yield rati
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the trends in the experimental data
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However, experiments often measure
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Statistical description of the gamm
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fragments formed are highly neutron
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F. Farget, J. Pancin GANIL, Caen, F
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ZPR-6/10 cores were applied as comp
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each nucleus in agreement with unce
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atios) is performed. In relation to
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school in science or engineering. I
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programs demanding only one compuls
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gamma-ray spectra will be theoretic
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RA 3 11:20 AM A Microscopic Theory
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Laboratory, Oak Ridge, Tenn., Novem
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Session RD Safeguards and Security
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Seeking Reproducibility in Fast Cri
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RE 4 11:40 AM Verification of Curre
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that a lot of them generally descri
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R. Hirschi, A. Hungerford, G. Magko
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- a density of levels too low for w
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the MONTEBURNS(1.0)-MCNP5-ORIGEN(2.
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The Nuclear Science References (NSR
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and applications using statistical
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Shielding objects are assembled fro
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The knowledge of neutron-induced re
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thus for the second time after the
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the global children health and cons
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Lawrence Livermore National Laborat
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The Russian Nuclear Data Library fo
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OECD Nuclear Energy Agency consider
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For experimental determination of t
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The European Activation SYstem has
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Neutron capture measurements of dys
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[1] H. Penttilä, P. Karvonen, T. E
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Measurement of Activation Cross Sec
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PR 66 Processing and Validation of
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law of the temperature ratio (RT =
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PR 74 Resonance Analysis of the 233
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Study of Various Potentials in Heav
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experimental data and for the produ
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fuel cycle impose tight requirement
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they do not satisfy (for example, b
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Differential Cross Sections for the
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extends the previous evaluation and
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various benchmark tests. The mainly
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PR 104 Evaluations for n+ 54,56,57,
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PR 109 Recent LAQGSM Developments a
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PR 113 Modelling of Spallation Sour
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Jagiellonian University, Reymonta 4
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PR 120 Coupled-Channel Models of Di
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PR 124 Nuclear Data Evaluation and
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physicist. - There is no perfect se
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Manturov, M.N. Nikolaev, A.M. Tsibo
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Vasiliev, W. Wieselquist and H. Fer
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Author Index 1, Vojtěch Rypar, PR
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HF 5, KD 4, LA 3, LA 6, LA 7, LA 8,
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Dunn, M. E., BF 4, RC 3 Dupont, Emm
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Gulliford, Jim, CE 1 Gunsing, Frank
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Kahl, David, HD 7 Kahler, A. C., CA
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Lehaut, G., PD 6 Leinweber, Greg, L
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Munkhsaikhan, J., HC 7 Mura, Luis F
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Prael, Richard E., PE 5 Praena, Jav
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Sheets, S., CF 2 Shen, Qingbiao, PC
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Typel, S., JA 3 Tyutyunnikov, S., L
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