JAEA-Conf 2011-002 - 日本原子力研究開発機構

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5. Conclusion JAEA-Conf 2011-002 With the help of the depletion perturbation theory, sensitivities of the curium isotope concentrations to nuclear data have been calculated for a light water reactor mixed-oxide burned fuel. Through the sensitivity analysis, phenomenon of the curium isotope generations during a reactor operation has been well understood. In addition, important nuclear data for accurate prediction of the curium isotope concentrations have been successfully specified. These information are helpful to investigate a cause of discrepancy between experimental and calculation values for the curium isotope concentrations. References [1] D. Boulanger, M. Lippens, J. Basselier, "High Burnup PWR and BWR MOX fuel performance: A review of BELGONUCLEAIRE Recent Experimental Programs," Proceeding of the 2004 International Meeting on LWR Fuel Performance, Orland, Florida, September 19-22, paper1109(2004). [2] S. Matsuoka, T. Ito, “Impact of difference of neutron cross section libraries to isotopic concentration of actinides,” Proc. of Int. Conf. on Physics of Reactor, Physor2010, Pittsburgh, (2010). [3] A. Gandini, “Time-dependent generalized perturbation theory for burn-up analysis,” CNEN RT/FI(75)4, Comitato Nazionale per l’Energia Nucleare, Rome (1975). [4] M.L.Williams, “Development of depletion perturbation theory for coupled neutron/nuclide fields,” Nucl. Sci. Eng., 70, p.20-36 (1979). [5] I.C.Gauld, D.E.Mueller, Evaluation of cross-section sensitivities in computing burnup credit fission product concentrations, ORNL/TM-2005/48, Oak Ridge National Laboratory (2005). [6] G.Chiba, et al., “Sensitivity analysis of fission product concentrations for light water reactor burned fuel,” J. Nucl. Sci. Technol., 47[7], p.652-660 (2010). [7] J. Katakura, et al., A set of ORIGEN2 cross section libraries based on JENDL-3.3 library: ORLIBJ33, JAERI-Data/Code 2004-015, Japan Atomic Energy Research Institute (2004).[in Japanese]
JAEA-Conf 2011-002 Sensitivity Analysis for Higher Order Legendre Coefficients of Elastic Scattering Matrices Go CHIBA Research Group for Reactor Physics, Japan Atomic Energy Agency Tokai-mura, Naka-gun, Ibaraki-ken 319-1195 e-mail: chiba.go@jaea.go.jp A sensitivity analysis is carried out focusing on higher order Legendre coefficients of elastic scattering matrices. Non-negligible library effects, which are defined as differences in criticalities caused by differences in nuclear data of different libraries, are observed in higher order Legendre coefficients of elastic scattering matrices of uranium-238 and iron-56 between JENDL-4.0 and the other modern nuclear data files. It is also found that an attention should be paid to the type of multi-group cross sections used for library effect calculations. It is concluded that higher order Legendre coefficients should be accounted for if accurate library effect evaluation is required. 1. Introduction The nuclear data is usually stored in the evaluated nuclear data files with the so-called ENDF format. There are several evaluated nuclear data files such as JENDL, ENDF and JEFF in the world. These libraries have been updated along with the improvement on the nuclear reaction models, the evaluation codes and the experimental data used for nuclear data evaluations. Since the nuclear data is the physical quantity, the evaluated nuclear data may converge to the true values by their improvement. While the latest evaluated nuclear data files such as JENDL-4.0, ENDF/B-VII.0 and JEFF-3.1 have quite high qualities, there are still large differences among them, and these differences significantly affect integral parameters calculated with these nuclear data files. Sensitivity analyses are useful to investigate causes of differences in integral parameters among different nuclear data files, and they have been effectively carried out in order to improve the qualities of the nuclear data files. In the usual sensitivity analyses, various kinds of the nuclear data have been accounted for. Scattering matrices and the first order Legendre coefficients of them have been also treated. Higher order Legendre coefficients of scattering matrices however have been ignored since the contributions of these data are supposed to be negligibly small. In the present paper, a sensitivity analysis is carried out focusing on higher order Legendre coefficients of elastic scattering matrices. Criticalities of various fast neutron systems are calculated with the modern nuclear data files, JENDL-4.0, -3.3, ENDF/B-VII.0 and JEFF-3.1, and differences in the calculated values are investigated from a view point of a difference in higher order Legendre coefficients of elastic scattering matrices.
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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
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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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JAEA-Conf 2011-002 Cowley et al. [1
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4. Conclusions We have compared nuc
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of MeV region with highest cosmic-r
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JAEA-Conf 2011-002 events can be id
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JAEA-Conf 2011-002 models and its p
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JAEA-Conf 2011-002
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JAEA-Conf 2011-002 xx
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JAEA-Conf 2011-002 1. The recent ac
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JAEA-Conf 2011-002 4. Conceptual de
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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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