JAEA-Conf 2011-002 - 日本原子力研究開発機構

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0.010% 0.000% -0.010% -0.020% -0.030% -0.040% 1.0E-5 1.0E-3 1.0E-1 1.0E+1 1.0E+3 1.0E+5 1.0E+7 -1.0E-2 -50% 1.0E-5 1.0E-3 1.0E-1 1.0E+1 1.0E+3 1.0E+5 1.0E+7 “The difference in diff-k” from 239 in Pu for each reaction type is shown in Fig. 5. Sensitivity coefficients for “diff-k” and the difference in the cross sections between JENDL-3.3 and JENDL-4.0 are shown in Fig. 6 and Fig. 7, respectively. 241 Am capture cross section ((σ4.0-σ3.3)/σ3.3) Fission and Capture There are relatively large sensitivity coefficients especially in thermal groups. However the sign of the difference in cross sections depend on energy groups, this fact brings cancellations in “the difference in diff-k” among energy groups. ν-value There are large sensitivity coefficients in thermal groups and about 0.1% difference in the cross sections between two libraries. “The difference in diff-k” does not cancel among energy groups because the difference in the cross sections is always negative in such groups. Therefore ν-value has relatively large impact on “the difference in diff-k” compared to fission and capture cross sections. 0.010% 0.005% 0.000% -0.005% JAEA-Conf 2011-002 0.0E+0 -2.0E-3 -4.0E-3 -6.0E-3 -8.0E-3 Sensitivity Cross Section Fig. 3 “The difference in diff-k” from 241 Am Fig. 4 Sensitivity coefficients and the difference ν value Fission Capture -0.010% 1.0E-5 1.0E-3 1.0E-1 1.0E+1 1.0E+3 1.0E+5 1.0E+7 Fig. 5 “The difference in diff-k” from 239 Pu 50% 40% 30% 20% 10% 0% -10% -20% -30% -40%
4.0E-2 3.0E-2 2.0E-2 1.0E-2 0.0E+0 ν value Fission Capture -1.0E-2 1.0E-5 1.0E-3 1.0E-1 1.0E+1 1.0E+3 1.0E+5 1.0E+7 “The difference in diff-k” from other nuclides such as 241 Am and 239 Pu are shown in Fig. 8 and Fig. 9. Except for 241 Am and 239 Pu, the change of 238 Pu capture cross section has relatively large impact on “the difference in diff-k” about +0.84%Δk/k, and this is caused by the fact that the difference in the cross sections is about -20% in thermal groups and relatively large sensitivity coefficients in such energy groups as shown in Fig. 10. 0.010% 0.005% 0.000% -0.005% 238 Pu Capture -0.010% 1.0E-5 1.0E-3 1.0E-1 1.0E+1 1.0E+3 1.0E+5 1.0E+7 238 UCapture 238 U ν 10% 0% -10% -20% ν value Fission Capture -30% 1.0E-5 1.0E-3 1.0E-1 1.0E+1 1.0E+3 1.0E+5 1.0E+7 Fig. 6 Sensitivity coefficients of 239 Pu Fig. 7 The difference in cross section of 239 Pu Fig. 9 “The difference in diff-k” from 238 U capture, ν and 238 Pu capture JAEA-Conf 2011-002 0.002% 0.001% 0.000% -0.001% -0.002% -0.003% 0.0E+0 -5.0E-5 -1.0E-4 -1.5E-4 -2.0E-4 -2.5E-4 ((σ4.0-σ3.3)/σ3.3) 241 Pu Capture 241 Pu ν -0.004% 1.0E-5 1.0E-3 1.0E-1 1.0E+1 1.0E+3 1.0E+5 1.0E+7 Fig. 8 “The difference in diff-k” from 235 U capture, ν and 241 Pu capture, ν Sensitivity 40% 20% -20% -40% -60% -3.0E-4 -80% 1.0E-5 1.0E-3 1.0E-1 1.0E+1 1.0E+3 1.0E+5 1.0E+7 235 U ν Cross Section Fig. 10 Sensitivity coefficients and the difference in 238 Pu capture cross section ((σ4.0-σ3.3)/σ3.3) 235 U Capture 0%
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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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Page 192 and 193: analysis of integral experiments [6
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