JAEA-Conf 2011-002 - 日本原子力研究開発機構

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some minor actinides. For major actinides, the impact by difference of nuclear data is relatively large about 234 U and 238 Pu. For minor actinides, the impact by difference of nuclear data is larger than for major actinides and is large about 237 Np, 241 Am, 243 Cm, 244 Cm and 245 Cm, as shown in Fig. 2. U234 U235 U236 U238 GRM1 0.5 0.6 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 Np237 Am241 Am242m Am243 GRM1 C/E JENDL-3.2 JENDL/AC-2008 ENDF/B-VII.0 JEFF-3.1 0.5 0.6 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 C/E JAEA-Conf 2011-002 JENDL-3.2 JENDL/AC-2008 ENDF/B-VII.0 JEFF-3.1 Pu238 Pu239 Pu240 Pu241 Pu242 Cm242 Cm243 Cm244 Cm245 Cm246 GRM1 0.5 0.6 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 GRM1 C/E JENDL-3.2 JENDL/AC-2008 ENDF/B-VII.0 JEFF-3.1 0.5 0.6 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 Fig. 2 C/E Comparison of 4 major evaluated nuclear data file with MALIBU GRM1. C/E JENDL-3.2 JENDL/AC-2008 ENDF/B-VII.0 JEFF-3.1 To measure the characteristics of JENDL-4.0 from a viewpoint of isotope concentration, C/C comparison was performed. The latest 4 evaluated nuclear data files, including JENDL-4 for isotope concentration at high burn up BWR MOX condition were compared with JENDL-3.2. JENDL-4.0, JENDL/AC-2008, JEFF-3.1 and ENDF/B-VII.0 are subject for comparison. JENDL/AC-2008 was used with combination of JENDL-3.2. C/C comparison of major and minor actinides is shown in Fig. 3. Isotope concentration evaluated by JENDL-4.0 is very close to JENDL/AC-2008 result. Remarkable characteristic of JENDL-4.0 are that isotope concentration of 234 U, 238 Pu and 243 Cm is 10% or more higher than other libraries results.
Fig. 3 C/C Comparison of 4 major evaluated nuclear data file with JENDL-3.2 The characteristics of the latest evaluated nuclear data were measured from a view point of isotope concentration prediction. For major heavy metal isotopes, their performances are excellent. For minor heavy metal isotopes, their performances are good, but some remarkable differences are observed. An analysis of performance of JENDL-4.0 is evaluated by C/C comparison. Its characteristic is similar to JENDL/AC-2008 for major and minor actinides. JAEA-Conf 2011-002 1) O. Iwamoto, T. Nakagawa, N. Otuka et al., "JENDL actinoid file 2008," J. Nucl. Sci. Technol., [5], 510 (2009). 2) M. B. Chadwick, P. Oblozinsky, M. Herman et al., "ENDF/B-VII.0: Next generation evaluated nuclear data library for nuclear science and technology," Nucl. Data Sheets, , 2931 (2006). 3) A. Santamarina, D. Bernard, Y. Rugama (Eds.), The JEFF-3.1.1 Nuclear Data Library, JEFF Report 22, OECD/NEA (2009). 4) K. Shibata, O. Iwamoto, T. Nakagawa et al., "JENDL-4.0: A new library for nuclear science and engineering," J. Nucl. Sci. Technol., [1], 1 (2011). 5) D. Boulanger, M. Lippens, J. Basselier, "High burnup PWR and BWR MOX fuel performance: A review of BELGONUCLEAIRE recent experimental programs," Proc. Int. Mtg. on LWR Fuel Performance, Orland, Florida, Sept. 19-22, paper1109 (2004). 6) S. Matsuoka, T. Ito, "Impact of difference of neutron cross section libraries to isotopic concentration of actinides," Proc. Int. Conf. on Advances in Reactor Physics to Power the Nuclear Renaissance (PHYSOR 2010), Pittsburgh, Pennsylvania, USA, May 9-14 (2010). 7) T. Nakagawa, K. Shibata, S. Chiba, et al., "Japanese evaluated nuclear data library version-3 revision 2: JENDL-3.2," J. Nucl. Sci. Tchnol., , 1259 (1995). 8) K. Okumura, T. Mori, M. Nakagawa, et al., "Validation of a continuous-energy monte carlo burn-up
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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 reactions. Figur
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JAEA-Conf 2011-002 Fig. 3. The angu
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analysis of integral experiments [6
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A modified SRAC library was prepare
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JAEA-Conf 2011-002 approximately 0.
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JAEA-Conf 2011-002 constructing the
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Fig.9 Spectrum of gamma-ray followi
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JAEA-Conf 2011-002 in the same way
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JAEA-Conf 2011-002 [7]. For example
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JAEA-Conf 2011-002 For
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JAEA-Conf 2011-002 (5.0-9.0MeV), a
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components, the 0.56Wt% for hydroge
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Sensitivities of curium isotope con
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decreases of (n,g) reaction rates,
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5. Conclusion JAEA-Conf 2011-002 Wi
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2. Foundation of sensitivity analys
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JAEA-Conf 2011-002 where f g and f
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Fig.1 Sensitivity coefficient of th
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An outline of core configurations o
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0.010% 0.000% -0.010% -0.020% -0.03
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To clarify what nuclides and reacti
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Calculation was performed by the MV
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among these libraries, and the diff
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JAEA-Conf 2011-002 - 日本原子力研究開発機構

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