JAEA-Conf 2011-002 - 日本原子力研究開発機構

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JAEA-Conf 2011-002 approximately 0.89 in thermal region below 1.8554eV. The effects on the infinite multiplication factors of fuel assemblies are 0.35%k and 0.30%k respectively in the UO2 and MOX fuel assembly at the beginning of burnup, decrease with burnup and extinguish at 15GWd/t. Effects on fission rate distributions due to the change of 157Gd cross sections reveals mainly at the beginning of life. The maximum effects on fission rates in Gd rods are 1.1% and 1.5% in MOX and UO2 fuel assembly, respectively. The effects extinguish at 15GWd/t. Accurate cross section evaluation of Gd isotopes, especially 157Gd and 155Gd (although not discussed in this paper) are very important in BWR nuclear fuel assembly design. More improvement needs to be done in the future study. References [1] G. Leinweber, D. O. Barry, M. J. Trbovich et al.,”Neutron Capture and Total Cross-Section Measurements and Resonance Parameters of Gadolinium,” Nucl. Sci. Eng., 154, 261 (2006). [2] P. F. Rose and C. L. Dunford, ENDF-102 Date Formats and Procedures of the Evaluated Nuclear Data File ENDF-6, BNL-NCS-44945, Rev.2, BNL (1997). [3] F. Jatuffa et al., “Impact of newly-measured gadolinium cross sections on BWR fuel rod reaction rate distributions, Proc. Int. Conf. PHYSOR2008, Interlaken, Switzerland, September 14-19, 2008, No. 219 (2008). [4] K. Shibata, O. Iwamoto, T. Nakagawa et al., "JENDL-4.0: A New Library for Nuclear Science and Engineering," (to be published to J. Nucl. Sci. Technol.). [5] Y. Nagaya, K. Okumura, T. Mori et al., MVP/GMVP II: General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculations Based on Continuous Energy and Multigroup Methods, JAERI-1348 (2005). [6] K. Okumura, private communication (2009) [7] K. Shibata, private communication (2009) [8] G. Chiba, K. Okumura, K. Sugino, et al. "JENDL-4.0 Benchmarking for Fission Reactor Applications,",J.Nucl. Sci. Technol. Vol. 48, No. 2, p. 1-16 (2011) (To be published) [9] K. Okumura, T. Kugo, K. Kaneko et al., SRAC2006: A Comprehensive Neutronic Calculation Code system, JAERI-Data/Code 2007-004 (JAERI), (2007).
JAEA-Conf 2011-002 33. Improvement of FP Decay Heat Calculation by Introducing TAGS Data . Gamma-Ray Energy Spectra. Hideo TAJIMA , Tadashi YOSHIDA Tokyo City University Tamazutumi 1-28-1, Setagaya-ku, Tokyo 158-8557, Japan e-mail: g1081008@tcu.ac.jp Sample-irradiation measurements and summation calculations of FP decay-heat still disagree each other without a theoretical correction which was introduced in the JNDC FP Decay Data Library long before. This disagreement is caused by the pandemonium problem in the FP decay-data, on which the calculations are based. The pandemonium problem comes from the limitation of the current method of constructing the decay schemes of short-lived nuclides. Recently a series of new TAGS measurements was initiated by a European group. In the mean time, we plan to include these new TAGS data into JENDL to exclude the pandemonium problem without the theoretical correction. This procedure needs not only the average energies but also the energy spectra of the -rays and the-particles. The TAGS data, however, provides us only with the -feedings into energy-bins. So we have to estimate the energy spectra with the aid of theoretical consideration along with the TAGS results. For this purpose, we calculate the energy spectrum of the -ray on the basis of the -feedings obtained by TAGS. 1. Introduction Currently summation calculations are used widely for predicting the fission product (FP) decay heat from a reactor core or a spent fuel. This method is based on summing up all the recoverable energy contributions from all the individual FPs undergoing -decay and the subsequent -transitions. This method, then, requires the average -ray and the -ray energies (E and E) per -decay. Neutrino plays no role in this context because of its absolute insensibility to the surrounding materials. The total absorption gamma-ray spectrometer (TAGS) method is one of the best ways to know these average energies. This method enables us to obtain the average energies of the-ray and the -particles per decay without any bias and to solve the pandemonium problem. The pandemonium problem is essentially the absence of our knowledge about the -feedings to the highly excited states of the daughter nuclides. This problem is caused by the limitation of the current method for
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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 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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