JAEA-Conf 2011-002 - 日本原子力研究開発機構

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Neutron Capture Cross Section of 153 Eu (barns) JAEA-Conf 2011-002 Neutron Energy (eV) JENDL-4.0 (2010) F.Widder (1975) V.A.Konks (1964,1968) M.C.Moxon (1976) M.Mizumoto (1979) Present Fig. 5. Neutron capture cross sections of 153 Eu References [1] Nuclear Fuel Cycle Facility Safety Research Committee, “A Guide Introducing Burnup Credit, Preliminary Version”, JAERI-Tech 2001-055, (2001) [in Japanese]. [2] J. F. Briesmeister, Ed. “MCNP-A general Monte Carlo N-Particle Transport code, version 4c,” LA-13709-M (2000) [3] K. Shibata, et al., “JENDL-4.0: A New Library for Nuclear Science and Engineering,” J. Nucl. Sci. Technol., 48, 1 (2011). [4] H. Hirayama, et al., The EGS5 Code System, Stanford Linear Accelerator Center Report SLAC-R-730 (2005). [5] R. L. Macklin, J. H. Gibbons, “Neutron Capture Cross Sections of 151 Eu and 153 Eu from 3 to 2200 keV,” Phys. Rev., 159, 1007 (1987). [6] F. Widder, “Neutron Capture Cross Section Measurements in Theenergy Region from 0.01 to 10 Electron Volts,” Proc. of Conf. on 2.Symp.on Neutr.Capt.Gamma Ray Spectrosc., Petten, 265, (1974). [7] V.A.Konks, Y.P.Popov, Y.I.Fenin, “Radiative Capture of Neutrons by Nuclei with A = 140- 200,” Soviet J. Nucl.Phys., 7, 310(1968) [8] M.C.Moxon, D.A.J.Endacott, J.E.Jolly, “The Neutron Capture Cross-Section of 151 Eu and 153 Eu in the Energy Range 0.1 to 100 keV,” Nucl. Energy, 3, 399 (1976)
JAEA-Conf 2011-002 19. Measurement of Resonance Parameters of 155,156,157,158,160 Gd by using pulsed neutrons with energy ranges from 10 eV to 1 keV Yeong-Rok Kang*, Tae-Ik Ro Department of Physics, Dong-A University, Busan 604-714, Korea Email: tiro@donga.ac.kr Guinyun Kim, Manwoo Lee Department of Physics, Kyungpook National University, Daegu 702-701, Korea Y. Danon, M.J Rapp, D. Williams Department of Mechanical, Aerospace, and Nuclear Engineering, Rensselaer Polytechnic Institute Troy, New York 12180-3590 G. Leinweber, D.P Barry, R.C. Block Bechtel Marine Propulsion Corporation, Knolls Atomic Power Laboratory P.O. Box 1072, Schenectady, New York 12301-1072 We explored neutron interactions with Gadolinium isotopes in the energy region from 10 eV to 1 keV at the electron linear accelerator facility at the Rensselaer Polytechnic Institute (RPI). The neutron capture measurements were made at a flight path of 25 m with a 16-segment sodium iodide multiplicity detector by using the time-of-flight technique. Five high-purity gadolinium isotopes ( 155 Gd, 156 Gd, 157 Gd, 158 Gd, and 160 Gd) and two natural gadolinium samples were used for the neutron capture measurement. Resonance parameters for 155,156,157,158,160 Gd were obtained by using the multilevel R-matrix Bayesian code SAMMY. The samples are placed in the center of a cylindrical 16-segment thallium activated sodium iodide NaI(Tl) detector. Each NaI(Tl) piece is pie shaped and optically separated from each other. All of the NaI(Tl) pieces are housed within an aluminum can with photomultipliers attached to each pie shaped segment. Many new resonances of the epithermal region are proposed, and other resonances previously identified in the literature have been revised. The poor match of the ENDF/B-VII.0 parameters to the current data is significant, and substantial improvement to the understanding of gadolinium cross sections is presented, particularly above 180.4 eV where the ENDF/B- VII.0 resolved region for 155 Gd ends. As a result, fitting data above 180.4 eV was performed without initial estimates for resonance locations and widths as a challenging task. Also new fitting result of 157 Gd above 306.4eV of the upper limit of ENDF/B-VII.0 was presented. 1. Introduction The neutron capture cross-sections of gadolinium (Gd) isotopes are important in the design of reactors, as well as in nuclear-reaction and astrophysical studies. Since the major portion of the natural Gd capture crosssections is due to 155 Gd and 157 Gd, an accurate knowledge of the cross-sections for those isotopes is also of importance to calculate the reactor characteristics when Gd is used as a burnable poison in light water reactors. The purpose of the present work was to measure the neutron capture cross-sections and to determine resonance parameters for Gd isotopes that are an improvement over the current gadolinium evaluations. In addition, the data are important for examining the availability of Gd as a control material for fast reactors. 1 In the region from 1.0 to 300.0 eV, most of the resonances occur in 155 Gd and 157 Gd. In these two isotopes,
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JAEA-Conf 2011-002 Proceedings of t
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JAEA-Conf 2011-002 31. Preliminary
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6.2 Measurement of neutron-induced
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JAEA-Conf 2011-002 Table 1 Comparis
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JAEA-Conf 2011-002 (T1/2=8,900,000
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JAEA-Conf 2011-002 Though words too
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JENDL-3.3 showed better applicabili
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ENDF. Thus this cross section store
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Acknowledgement JAEA-Conf 2011-002
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In the MALIBU program, isotope conc
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some minor actinides. For major act
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JAEA-Conf 2011-002 code MVP-BURN an
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JAEA-Conf 2011-002 [3] Measurements
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3.1 Experimental Set up JAEA-Conf 2
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References JAEA-Conf 2011-002 [1] N
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JAEA-Conf 2011-002 was large. The a
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JAEA-Conf 2011-002 4. Results and D
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Acknowledgments Present study inclu
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Fig. 1 A conceptural picture of the
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4. Theoretical studies Theoretical
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JAEA-Conf 2011-002 Fig.9 Comparison
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Ion source JAEA-Conf 2011-002 LE
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JAEA-Conf 2011-002 3. Readiness
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JAEA-Conf 2011-002 Figure 1. An exa
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JAEA-Conf 2011-002 Figure 6. Compar
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JAEA-Conf 2011-002 calculation of d
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JAEA-Conf 2011-002 equilibrium emis
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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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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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