JAEA-Conf 2011-002 - 日本原子力研究開発機構

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References JAEA-Conf 2011-002 [1] NEA/WPEC-26, Uncertainty and target accuracy assessment for innovative systems using recent covariance data evaluations, ISBN 978-92-64-99053-1, 2008. [2] M. Mizumoto, et al. “Neutron capture cross section measurements on 237Np with a 4π Ge spectrometer”, Proc. Int. Conf. on ND 2007, 591 (2008). [3] M. Oshima et. al., “Performance of a 4 π Ge spectrometer for neutron capture cross section measurements,” Proc. Int. Conf. on ND 2007, 603(2007). [4] A. Kimura, et al. “Measurements of neutron-capture cross sections of 244Cm and 246Cm at J-PARC/MLF/ANNRI”, Proc. Int. Conf. on ND 2010, #1380 (2010). [5] S. Nakamura, et al., “Measurements of neutron-capture cross section of palladium isotopes at the J-PARC/MLF/ANNRI”, Proc. Int. Conf. on ND 2010, #1295 (2010). [6] J. Hori et al., “Measurements of neutron-capture gamma rays from the resonances of 91Zr and 96Zr at the J-PARC/MLF/ANNRI”, Proc. Int. Conf. on ND 2010, #1301 (2010). [7] S. Goko, et al, “Measurement of neutron capture cross section ratios of 244Cm resonances using NNRI”, J. Nucl. Sci. Technol. 47 1097 (2010). [8] S. Mizuno, et al.,” Measurements of keV-Neutron Capture Cross Sections and Capture Gamma-Ray Spectra of 161, 162, 163Dy”, J. Nucl. Sci. Technol., 36 493 (1999). [9] F. Maekawa, et al., “First Neutron Production Utilizing J-PARC Pulsed Spallation Neutron Source JSNS and Neutronic Performance Demonstrated”, Nucl. Instrum. Methods. Phys. Res. A 620, 159 (2010). [10] K. Kino et al., “Measurement of energy spectra and spatial distributions of neutron beams provided by the ANNRI beamline for capture cross-section measurements at the J-PARC/MLF”, Nucl. Instrum. Methods. Phys. Res. A 626, 58 (2011). [11] T. Kin et. al., “Development of a 4π Germanium Spectrometer for Nuclear Data Measurements at J-PARC,” the 2009 NSS-MIC Conf. Rec. , N24-2, (2009). [12] A. Kimura, et. al., “Performance of a high speed and high density data acquisition system for multiple gamma-ray detection”, Conference Record of IEEE NSS/MIC/RTDS 2008, Article Number: N30-68, (2008). [13] M. S. Moore and G. A. Keyworth,”Analysis of the Fission and Capture Cross Secssions of the Curium Isotopes”, Physical Review C, 3, 1656 (1971). [14] T. Fujii, et al. “Study on nuclear data by using a high intensity pulsed neutron source for advanced nuclear system (4) Analysis of components of the samples for nuclear data”, Conference record of 2010 Annual Meeting of AESJ, B42 (2010) [in Japanese]. [15] A. Kimura, et al. “A Dead-Time Correction Method for Multiple Gamma-ray Detection”, Conference Record of IEEE NSS/MIC 2009, Article Number: N07-03, (2009). [16] M. Ohta, et al. “Measurement of Neutron Spectrum at BL04 of J-PARC / MLF”, Conference record of 2009 Fall Meeting of AESJ, J15, (2009) [in Japanese]. [17] K. Shibata, et al., "JENDL-4.0: A New Library for Nuclear Science and Engineering," J. Nucl. Sci. Technol. 48[1], 1-30 (2011).
JAEA-Conf 2011-002 6. Measurements of Neutron Capture Cross Sections at J-PARC/MLF/ANNRI (2) Measurements of Neutron Capture Cross Sections of Long-Lived Fission Products using a high intensity pulsed neutron source J. HORI1, T. FUJII1, S. FUKUTANI1, M. FURUSAKA4, K. FURUTAKA2, S. GOKO2,a, H. HARADA2, F. HIRAGA4, M. IGASHIRA3, T. KAMIYAMA4, T. KATABUCHI3, A. KIMURA2, T. KIN 2, K. KINO4,b, F. KITATANI2, Y. KIYANAGI4, M. KOIZUMI2, M. MIZUMOTO3, S. NAKAMURA2, M. OHTA2,c, M. OSHIMA2, K. TAKAMIYA1, and Y. TOH2 1Research Reactor Institute, Kyoto University 2Nuclear Science and Engineering Directorate, Japan Atomic Energy Agency 3Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology 4Graduate School of Engineering, Hokkaido University Present address : a Hokkaido University, b High Energy Accelerator Research Organization, c Osaka University e-mail: hori@rri.kyoto-u.ac.jp The neutron capture cross sections of 93Zr, 99Tc and 107Pd have been measured relative to the 10B(n,) standard cross section by the neutron time-of-flight (TOF) method. Neutron capture rays were measured with a 4 Ge spectrometer as a part of the Accurate Neutron-Nucleus Reaction measurement Instrument (ANNRI) installed at the neutron Beam Line No.4 (BL04) of the Material and Life science experimental Facility (MLF) in the Japan Proton Accelerator Research Complex (J-PARC). This paper presents the preliminary results. 1. Introduction The neutron capture cross sections of long-lived fission products (LLFPs) are of great importance for the research of the nuclear transmutation of radioactive waste. Seven nuclei of 79Se, 93Zr, 99Tc, 107Pd, 126Sn, 129I and 135Cs were selected as the most important LLFPs [1]. At first, the current status of experimental data on neutron capture cross sections of those nuclei is summarized briefly. There are no experimental data for 79Se. As for the status of 126Sn and 135Cs, there are only available experimental data with the activation method. It is noted that the only experimental result of 126Sn was recently reported at the thermal energy [2]. For 93Zr and 107Pd, the experimental data obtained by the neutron time-of-flight (TOF) method at the Oak Ridge Electron Linear Accelerator (ORELA) are only available in the resonance region [3,4]. Since a pair of C6D6 detectors was used as a capture -ray detector in the works, the effects due to the isotope impurities contained in a sample were subtracted by using the other experimental data on those isotopes. Therefore, the uncertainty associated with subtraction
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The Institute's staff of about 280
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3. Nuclear Theory Laboratory JAEA-C
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JAEA-Conf 2011-002 References [1] P
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JAEA-Conf 2011-002 reaction 6 Li +
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Using the approximated distribution
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momentum of the constituents of P.
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dσ/dΩ (mb/sr) c.m. scattering ang
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JAEA-Conf 2011-002 [2] N. Austern,
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moderating fast neutrons emitted fr
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JAEA-Conf 2011-002 3. Results and d
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JAEA-Conf 2011-002 the detection de
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Fig.1. Experimental arrangement for
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in this work was confirmed. (2) 153
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Neutron Capture Cross Section of 15
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ENDF resonance parameters are based
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sample changer. The measured flux s
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REFERENCES JAEA-Conf 2011-002 [1] W
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JAEA-Conf 2011-002 Fig. 4: The rela
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Fig. 10: The PHITS2 calculation geo
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for such a low energy region should
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MCNPX calculation was performed bas
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JAEA-Conf 2011-002 We measured dou
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1mm-thick carbon target 22mm in dia
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JAEA-Conf 2011-002 Figure 2 shows e
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The double-differential (n,xp) and
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JAEA-Conf 2011-002 forward angles.
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Fig.3. Two-dimensional plot of PI v
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JAEA-Conf 2011-002 Fig. 7. Deuteron
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JAEA-Conf 2011-002 The new detector
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4. Off line data analysis Double di
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eports of data of carbon-ion incide
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Count [-] 4 10 3 10 2 10 10 1 Charg
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Acknowledgement We are grateful to
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Beam Line BM1 Copper Target BM2 5×
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φ = φbm · ρtof · ρmulti (2) E
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References [1] K. Ishibashi, H. Tak
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JAEA-Conf 2011-002 hint at the orig
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Neutron Dose Rate [Sv/hr/src neutro
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JAEA-Conf 2011-002 radiation protec
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Ztarget, Atarget are the numbers fo
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We described our formalism for calc
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2. Model
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JAEA-Conf 2011-002 reactions. Figur
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JAEA-Conf 2011-002 Fig. 3. The angu
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analysis of integral experiments [6
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A modified SRAC library was prepare
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JAEA-Conf 2011-002 approximately 0.
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JAEA-Conf 2011-002 constructing the
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Fig.9 Spectrum of gamma-ray followi
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JAEA-Conf 2011-002 in the same way
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JAEA-Conf 2011-002 [7]. For example
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JAEA-Conf 2011-002 For
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JAEA-Conf 2011-002 (5.0-9.0MeV), a
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components, the 0.56Wt% for hydroge
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Sensitivities of curium isotope con
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decreases of (n,g) reaction rates,
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5. Conclusion JAEA-Conf 2011-002 Wi
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2. Foundation of sensitivity analys
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JAEA-Conf 2011-002 where f g and f
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Fig.1 Sensitivity coefficient of th
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An outline of core configurations o
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0.010% 0.000% -0.010% -0.020% -0.03
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To clarify what nuclides and reacti
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Calculation was performed by the MV
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among these libraries, and the diff
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JAEA-Conf 2011-002 - 日本原子力研究開発機構

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