JAEA-Conf 2011-002 - 日本原子力研究開発機構

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An outline of core configurations of EPICURE MH1.2 and MISTRAL core4 is shown in Table 1 and Fig. 2. Program EPICURE MH1.2 MISTRAL core4 Core Configuration Partial MOX Homogeneous Full MOX 17×17 Mockup Vm/Vf 1.3 2.0 H/HM 3.7 5.8 Fuel pitch [cm] 1.26 1.32 Fuel rod type MOX-7.0% UO2-3.7% MOX-7.0% Core size [cm] 69 62 Table 1 Core parameters All calculations were performed in 107 energy groups: SRAC2006 [4] was used to obtain the group-wise cross sections for both JENDL-3.3 and JENDL-4.0. The group-wise cross sections were used in the generalized perturbation theory code SAGEP [5] to obtain the sensitivity coefficients for “diff-k” between EPICURE and MISTRAL. “The difference in diff-k” between JENDL-3.3 and JENDL-4.0 denoted as δ(δk4.0-δk3.3) was evaluated by the following equation to obtain detailed information for the difference. S ( k l, r, g 4. 0 ( k 2 JAEA-Conf 2011-002 k ) 1 l, r, g k 2 S 2 k S 1 1 ( ) 4. 0 3. 3 k ) S , 3. 3 3. 3 (2) 3. 3 UO2 3.7% EPICURE MH1.2 MISTRAL core4 where < > represents integration over nuclide, reaction type and energy group, k1 and k2 are “keff” in EPICURE MH1.2 and MISTRAL core4, S1 and S2 are the sensitivity coefficient for “keff” in EPICURE MH1.2 and MISTRAL core4, δk3.3 and δk4.0 are “diff-k” based on JENDL-3.3 and JENDL-4.0, S3.3 is the sensitivity coefficient for “diff-k” based on JENDL-3.3, σ3.3 and σ4.0 are the cross section based on JENDL-3.3 and JENDL-4.0, respectively. l, r , g MOX7.0% Fig. 2 Core configurations (1)
JAEA-Conf 2011-002 Summary of the breakdown of the contribution to “the difference in diff-k” of nuclide and reaction type is summarized in Table 2. “The difference in diff-k” is mainly caused by the change of 241 Am capture cross section, as shown Table 2. “The difference in diff-k” by the change of 239 Pu cross sections cancels among reaction types, although the change of 239 Pu cross sections brings relatively large impact on “the difference in diff-k” for each reaction type. The change of 238 Pu capture cross section also causes “the difference in diff-k” of about +0.08%Δk/k, and the value of 238 U capture cross section is about -0.05%Δk/k. “The difference in diff-k” of about -0.33%Δk/k does not match the value of about -0.2%Δk/k, because there are many positive and negative portions and those cancel each other. Table 2 Contribution to “the difference in diff-k” of each nuclide and reaction type Fission ν Capture [%Δk/k] Elastic Total 235 U 0.005 -0.006 -0.020 0.000 -0.022 238 U 0.006 -0.008 -0.049 0.004 -0.043 238 Pu 0.000 0.000 0.084 0.000 0.084 239 Pu 0.062 -0.101 0.035 0.000 -0.002 240 Pu 0.000 0.000 -0.001 0.000 -0.001 241 Pu 0.003 0.015 -0.011 0.001 0.008 242 Pu 0.000 0.000 -0.005 0.000 -0.005 241 Am -0.001 0.002 -0.334 0.000 -0.333 1 H - - 0.000 -0.015 -0.015 16 O - - 0.000 0.014 0.014 Zr - - 0.000 -0.004 -0.020 -0.333 The main contribution to “the difference in diff-k” comes from the 241 Am capture reaction in the following energy ranges; 1.13eV~1.45eV, 0.47eV~0.62eV and 0.25eV~0.32eV (Fig. 3). This comes from the fact that there are large positive difference in the cross sections between JENDL-3.3 and JENDL-4.0, and comparatively large negative sensitivity coefficients in such energy ranges as shown in Fig. 4. Sensitivity coefficients for “diff-k” of 241 Am capture cross section is always negative caused by the fact that the number density of 241 Am in MISTRAL core4 is larger than that in EPICURE MH1.2. It should be noted that 241 Am capture cross section based on JENDL-4.0 is out of one standard deviation of JENDL-3.3 in above energy ranges.
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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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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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JAEA-Conf 2011-002 - 日本原子力研究開発機構

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