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J. P. Lestone, E. F. Shores Los Alamos National Laboratory The neutron experiment (NUEX) was a common diagnostic on nuclear device tests conducted at the Nevada Test Site (NTS). In these experiments neutrons from a device pass up a collimated line of site, and in the case of a Faraday cup (FC) NUEX, the neutrons pass through a thin CH2 foil. Some of these neutrons interact with the nuclei in the foil, generating light charged particles (predominantly protons) which are collected in a Faraday cup. The time dependence of the Faraday cup current is a measure of the energy spectrum of the neutrons that leak from the device. With good device models and accurate neutrontransport codes, the leakage spectrum can be converted into a prompt fast-neutron-induced fission-neutron energy spectrum (PFNS) from ∼1 to 11 MeV. This has been done for one of our last events containing a plutonium primary, where the NUEX data were of a particularly high quality, and for an earlier event containing a uranium primary. The fission-neutrons in these devices were produced by fission events induced by neutrons over a broad range of energies. We have inferred 2 MeV n + 239Pu and n + 235U fission-neutron spectra for outgoing neutron energies from 1.5 to 10.5 MeV, in 1-MeV steps. These spectra are in good agreement with the Los Alamos fission model [1]. [1] D. G. Madland and J. R. Nix, Nucl. Sci. and Eng. 81, 213 (1982), and http://t2.lanl.gov/data/fspect. LA 2 4:00 PM A New Measurement of the Neutron Capture Cross Section of 235 U Below 5 keV David Williams, Yaron Danon, Rian Bahran Gaerttner LINAC Center, Rensselaer Polytechnic Institute, Department of Mechanical, Aerospace and Nuclear Engineering, 110 8th St, Troy, NY 12180 Devin Barry, Greg Leinweber, Robert Block, Michael Rapp Bechtel Marine Propulsion Corporation, Knolls Atomic Power, Laboratory, P.O. Box 1072, Schenectady, New York 12301-1072 The neutron microscopic capture cross section for 235 U is a critical parameter for the design and operation of nuclear reactors. The evaluated nuclear data libraries of ENDF/B-VII.1 and JENDL-4.0 have nearly identical values for the neutron capture cross section for neutron energies below 0.5 keV. In the most recent release of the JENDL library the onset of the unresolved resonance region (URR) was changed from 2.25 keV to 0.5 keV, and in this region the average neutron capture cross section from ENDF/B-VII.1 is about 10% higher than that from JENDL-4.0. In an attempt to address the discrepancies between the libraries, a new measurement of the neutron capture cross section of 235 U was conducted at the Gaerttner LINAC Center located at Rensselaer Polytechnic Institute. This measurement used a 16 segment γ-multiplicity NaI(Tl) detector to detect the prompt gammas emitted from neutron interactions with a highly enriched 235 U sample. Using the time-of-flight method, detected events were recorded and grouped based on the total gamma energy per interaction and observed multiplicity. A method was developed to separate fission from capture based on total energy deposition and gamma multiplicity. Application of this method in the thermal and resonance region below 0.5 keV for both the fission and capture cross section produced cross sections in excellent agreement with both the ENDF/B-VII.1 and JENDL-4.0 evaluations. The measurements support the conclusion to lower the 235 U neutron capture cross section below the ENDF values in the energy range 0.5-2.25 keV. LA 3 4:20 PM 164
Neutron Capture Cross Sections and Gamma Emission Spectra from Neutron Capture on 234,236,238 U measured with DANCE. J.L. Ullmann, T.A. Bredeweg, A.J. Couture, R.C. Haight. M. Jandel, T. Kawano, J.M. O’Donnell, R.S. Rundberg, D.J. Vieira, J.B. Wilhelmy Los Alamos National Laboratory. J.A. Becker, A. Chyzh, C. Y. Wu Lawrence Livermore National Laboratory B. Baramsai, G. E. Mitchell North Carolina State University M. Krtička Charles University, Prague An accurate knowledge of the gamma-ray strength function and level density is needed for the firstprinciples calculation of neutron-capture cross sections. A constraint on these quantities is provided by measurements of gamma-ray emission spectra. We will present neutron-capture cross sections from 10 eV to 10 keV and gamma-emission spectra from several isolated neutron resonances in 234,236,238 U, measured using the DANCE detector at LANSCE. The measurements will be compared to cross-section calculations and gamma-emission calculations made using different models for the radiative strength function. DANCE is a calorimetric 4π array consisting of 160 BaF2 crystals, designed for studying neutron capture on small samples of rare or radioactive nuclides. The measurements were made at the Manuel J. Lujan, Jr. Neutron Scattering Center at the Los Alamos National Laboratory, under the auspices of the U.S. Department of Energy contract DE-AC52-06NA25396. LA 4 4:40 PM Neutron-Induced Fission Cross Section Measurements at LANSCE A.B. Laptev, F. Tovesson Los Alamos National Laboratory T.S. Hill Idaho National Laboratory A well established program of neutron-induced fission cross section measurement at Los Alamos Neutron Science Center (LANSCE) is supporting fast nuclear reactor technology. The incident neutron energy range spans from sub-thermal up to 200 MeV by combining two LANSCE facilities, the Lujan Center and the Weapons Neutron Research center (WNR). The time-of-flight method is implemented to measure the incident neutron energy. A parallel-plate fission ionization chamber is used for fission fragment detection. The event rate ratio between the investigated foil and a standard 235 U foil is translated into a fission cross section ratio. Thin actinide targets with deposits of
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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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direction was recently used at n TO
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were chemically separated and the 2
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Strontium-82 Production at ARRONAX
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Page 116 and 117: expected via an (n,γ) reaction. Pr
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Page 122 and 123: good timing characteristics.Example
Page 124 and 125: Materials and Measurements, Retiese
Page 126 and 127: derive reliable covariances from ta
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Page 130 and 131: Accurate and reliable nuclear data
Page 132 and 133: Facility (HRIBF) at Oak Ridge Natio
Page 134 and 135: CALIFA, a Calorimeter for the R3B/F
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Page 140 and 141: A significant breakthrough in our t
Page 142 and 143: and the neutron and proton emission
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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
Page 178 and 179: solving the quantum three-body prob
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
Page 188 and 189: from non 1/v behavior of nuclei. Mo
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Page 194 and 195: NC 3 11:20 AM Propagation of Nuclea
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Page 200 and 201: calculating their mathematical mome
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Page 206 and 207: available for ENDF/B-VII. The obser
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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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