JAEA-Conf 2011-002 - 日本原子力研究開発機構

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To clarify what nuclides and reaction types are dominant to “the difference in diff-k” about -0.2%Δk/k between JENDL-3.3 and JENDL-4.0, sensitivity analysis was performed. The followings were found in this investigation. The main contribution to “the difference in diff-k” comes from 241 Am capture reaction, and the value is about -0.3%Δk/k. “The difference in diff-k” caused by the change of 239 Pu cross sections cancels among reaction types, although the change of 239 Pu cross sections for each reaction type brings relatively large impact on “the difference in diff-k”. It is also noted that the change of 238 Pu capture cross section has relatively large impact on “the difference in diff-k” about +0.8%Δk/k. JAEA-Conf 2011-002 The author wishes to express his gratitude to T. Nakagawa of Japan Atomic Energy Agency for providing the covariance data of 241 Am. [1] K. Ishii, M. Tatsumi, T. Kan et al., ‘‘Analysis of MOX corephysics experiments MISTRAL,’’ Trans. At. Energy Soc. Jpn.,2, 39–54 (2003), [in Japanese]. [2] K. Shibata,"Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3," J. Nucl. Sci. Technol. , 1125 (2002). [3] K. Shibata,"JENDL-4.0: A New Library for Nuclear Science and Engineering" (to be published to J. Nucl. Sci. Technol.). [4] Keisuke OKUMURA, "SRAC2006: A Comprehensive Neutronics Calculation Code System, " JAEA-Data/Code 2007-004 (2007). [5] A. Hara, T. Takeda and Y. Kikuchi ”SAGEP:Two-Dimensional Sensitivity Analysis Code Based on Generalized Perturbation Theory” JAERI-M 84-027 (Jan. 1984) [in Japanese].
Koichi IEYAMA, Kosuke SHIMOZATO, Takanori KITADA Osaka University, 2-1Yamada-oka, Suita-shi, Osaka, Japan, 565-0871 k-ieyama@ne.see.eng.osaka-u.ac.jp Analyses were performed to verify nuclear data of some rare-earth elements(Dy, Ho, Er and Tm) by using the continuous energy Monte-Carlo code: MVP, and to evaluate the validity of the cross section libraries (JENDL-4.0, JENDL-3.3, ENDF/B-VII.0 and JEFF-3.1) by comparing infinite dilution cross section in SRAC library 107 energy groups. The difference of energy-integrated capture rate among these libraries is about 0.1% for Dy and 0.2% for Er at both E3 and EE1 coresand the influence on energy-integrated capture rate by the difference of the cross section libraries is small at these cores.Though there is a relatively large difference in the C/E value of Ho2O3 at EE1 core between ENDF/B-VII.0 and JEFF-3.1, the difference of energy-integrated capture rate between these libraries is about 0.8% at EE1 core. JAEA-Conf 2011-002 The rare-earth elements would be useful as an advanced burnable poison. However, only a few critical experiments with rare-earth element have been carried out so far to validate the accuracy of their nuclear data. Critical experiments with four rare-earth 0.05 elements (Dy, Ho, Er and Tm) at Kyoto University Critical Assembly (KUCA) 0.04 E3 B3/8"P36EU(3) H/235U 317 were performed in two kinds of cores (E3 0.03 EE1 B1/8"P60EU-EU(5) and EE1 core) with different neutron H/235U 52 spectra shown in Fig. 1. The validity of 0.02 cross section of rare-earth elements was 0.01 estimated from the analysis of measured 0 data by the continuous energy 1.E-03 1.E-01 1.E+01 1.E+03 1.E+05 1.E+07 Monte-Carlo code; MVP and infinite energy[eV] dilution cross section in SRAC library 107 energy groups. Fig. 1 Neutron Spectrum for each unit cell normalized neutron flux[-]
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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
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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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JAEA-Conf 2011-002
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JAEA-Conf 2011-002
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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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JAEA-Conf 2011-002
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JAEA-Conf 2011-002 - 日本原子力研究開発機構

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