JAEA-Conf 2011-002 - 日本原子力研究開発機構

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Fig.1 Sensitivity coefficient of the HEU-MET-FAST-028 criticality to Legendre coefficients of uranium-238 elastic scattering cross sections JAEA-Conf 2011-002 Fig.2 Energy group-wise library effect of Legendre coefficients of iron-56 elastic scattering matrices to the HEU-MET-FAST-021 criticality between JENDL-4.0 and JEFF-3.1 (Base library: JENDL-4.0)
Masahiro KIMURA, Takanori KITADA, and Yosuke INOUE Osaka University, 2-1Yamada-oka, Suita-shi, Osaka, Japan, 565-0871 E-mail: m-kimura@ne.see.eng.osaka-u.ac.jp Detailed evaluation of the criticality change observed in MOX core was performed based on sensitivity analysis to clarify what is main cause of the difference in the criticality change between JENDL-3.3 and JENDL-4.0. It is found that the difference in the criticality change between two libraries is mainly caused by the change of 241 Am capture cross section, and the difference in the criticality change caused by the change of 239 Pu cross sections cancels among reaction types, although the change of 239 Pu cross sections brings a relatively large impact on the difference in the criticality change for each reaction type. JAEA-Conf 2011-002 NUPEC has been performing conceptual design studies of high moderation full MOX LWR cores. In a series of experimental analyses, the overestimation of multiplication factor (keff) slightly increases as shown in Fig. 1. The target cores in this study are EPICURE MH1.2 (1993) and MISTRAL core4 (1999) 1.01 1.008 1.006 1.004 [1] . The difference of overestimation in “keff” (diff-k) between EPICURE MH1.2 (“keff”=k1) and MISTRAL core4 (“keff”=k2) is about 0.6%Δk/k by using the 107-group cross section data based on JENDL-3.3 [2] . But it was reported that “diff-k” between two cores is reduced to about 0.4%Δk/k by using the data based on JENDL-4.0 [3] . To clarify what nuclides and reaction types are dominant to “the difference in diff-k” (about 1 EPICURE MH1.2 MISTRAL -0.2%Δk/k) between JENDL-3.3 and JENDL-4.0, (1993) core2 (1997) core3 (1998) core4 (1999) sensitivity analysis was performed in this study. Fig. 1 Criticality of MOX cores (JENDL-3.3) 1.002
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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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Page 192 and 193: analysis of integral experiments [6
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JAEA-Conf 2011-002 - 日本原子力研究開発機構

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