JAEA-Conf 2011-002 - 日本原子力研究開発機構

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Acknowledgement JAEA-Conf 2011-002 The authors thank K. Okumura of the research group for reactor physics, JAEA, for preparing the neutron cross-section sets for the MVP. The authors also thank Y. Nagaya of the research group for reactor physics, JAEA, for supporting parallel execution of the MVP. References [1] M. Goto, N. Nojiri and S. Shimakawa, "Neutronics Calculations of HTTR with Several Nuclear Data Libraries," J. Nucl. Sci. Technol., 43[10], 1237 (2006). [2] K. Shibata, O. Iwamoto, T. Nakagawa, et al., "JENDL-4.0: A New Library for Innovative Nuclear Energy Systems," Proc. of the Int. Conf. on Nuclear Data for Science and Technology (ND2010), Jeju Island, Korea, April 26-30, 2010. [3] Firestone R.B., M. Krticka, D.P. McNabbet, et al., " New Methods for the Determination of Total Radiative Thermal Neutron Capture Cross Sections," Proc. of 2007 Int. Workshop on Compound-Nucleus Reactions and Related Topics, Yosemite, U.S.A., Oct. 22-26, 2007. [4] K. Shibata, Evaluation of neutron nuclear data for 12C, JAERI-M 83-221, Japan Atomic Energy Research Institute (JAERI) (1983). [5] Los Alamos National Laboratory, T-2 Nuclear Information Service, [6] http://t2.lanl.gov/data/data/ENDFB-VII-neutron/C/nat. R. Kinsey, ENDF/B Summary documentation, BNL-NCS-17541, Brookhaven National Laboratory (BNL) (1979). [7] A. Koning, R. Forrest, M. Kellett, et al., The JEFF-3.1 Nuclear Data Library, JEFF Report 21, OECD/NEA (2006). [8] Y. Nagaya, K. Okumura, T. Mori, et al., MVP/GMVPII: General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculations based on Continuous Energy and Multigroup Methods, JAERI 1348, Japan Atomic Energy Research Institute (JAERI), (2005). [9] I. Murata, T. Mori, M. Nagaya, et al., Continuous Energy Monte Carlo Calculations for Randomly distributed Spherical Fuels Based on Statistical Geometry Model, JAERI-Research 96-015, Japan Atomic Energy Research Institute (JAERI), (1996), [in Japanese]. [10] N. Nojiri, S. Shimakawa, N. Fujimoto, et al., "Characteristics test of initial HTTR core," Nucl. Eng. Des., 233, 283 (2004).
JAEA-Conf 2011-002 Takuya Ito, Shogo Matsuoka, Shota Okui Nuclear Fuel Industries, Ltd. Tokai-works, Tokai-mura, Naka-gun, Ibaraki, 319-1196, Japan Email:t-itoh@nfi.co.jp To understand the characteristics of evaluated nuclear data from a view point of isotope concentration prediction, burnup calculations for high burnup BWR MOX fuels were performed based on several nuclear data libraries, including JENDL-4.0. The calculation results were compared to measurements and each other calculations. JENDL/AC-2008 1) was released in 2008 in Japan. In USA, ENDF/B-VII.0 2) was released in 2006 and preparation of ENDF/B-VII.1 is progressing. In Europe, JEFF-3.1.1 3) was released in 2009. JENDL-4.0 4) was released in May 2010. In this study, isotope concentration prediction calculations for high burnup BWR MOX fuels with the new several evaluated nuclear data files are performed and compared to reference values. The result of C/E comparison to the results of radio-chemical analysis of the MALIBU 5,6) high burn up BWR MOX samples is shown for JENDL-3.2 7) , JENDL/AC-2008, ENDF/B-VII.0, JEFF-3.1 by using MVP-BURN 8) . MALIBU program is an international PIE program for high burnup fuel which was irradiated in commercial reactors. As for JENDL-4.0, C/C comparison of isotope concentration against the latest evaluated nuclear data files at high burn up BWR MOX condition is shown. Continuous energy Monte-Carlo code "MVP-BURN" is employed for burnup calculation to reduce both of geometry approximation and effective cross section approximation. In calculation, fuel assembly geometry is simulated exactly and irradiation data which are provided by MALIBU program are traced. MALIBU program 5,6) is an international PIE program for high burnup MOX and UOX fuels. In this program, various nuclides, 17 heavy metal nuclides and 34 fission products nuclides are subject of analysis. The sample matrix is shown in Table 1.
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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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