JAEA-Conf 2011-002 - 日本原子力研究開発機構

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analysis of integral experiments [6]. Under this background, the present study was performed to evaluate the effect of the new data of 157Gd on burnup characteristics of high burnup BWR UO2 and MOX assemblies. 2 Comparison of Capture Cross Section of 157Gd Thermal capture cross sections of 157Gd measured in experiments and adopted in recent nuclear data libraries are shown in Table 1, which were provided by K.Shibata[7] and the cross section adopted in nuclear data libraries were evaluated at 300K. In the evaluation of cross sections of JENDL-4.0, the data of Leinweber et al. were used. However, the background cross sections of 157Gd below 0.1eV were determined through the sensitivity study using ICSBEP critical benchmark data [8]. Table 1 Comparison of thermal capture cross section of 157Gd Author Energy (eV) *** Capture Cross Section (barns) Pattenden ‘58 0.0253 264000±4500 Tattersall ‘60 Groshev ‘62 Maxwell 213000±2000 240000±12000 Leinweber ‘06* 226000 Mughabghab ‘06** 254000±815 JENDL-3.3 253681 JENDL-4.0 0.0253 253251 ENDF/B-6.8 253747 ENDF/B-7.0 253747 JEF-2.2 253272 JEFF-3.1.1 JAEA-Conf 2011-002 *Calculated value based Leinweber et al. [1] **Evaluation ***Energy installed in EXFOR 253272 3 Preparation of modified 157Gd cross section New point-wise cross sections of 157Gd corresponding to the measurement of Leinweber et.al,.were prepared for a MVP library [6]. Comparisons of the new and old cross sections of 157Gd were performed using MVP for a Gd2O3UO2 cell in high burnup BWR UO2 and MOX assemblies shown in Figure 1. A new SRAC cross section library was prepared based on the above comparative results.
Average Total-Pu=4.9wt%U-235 Total-Pu=4.9wt%U-235 in MOX = 0.2wt% Gd 2 O 3 fuel : 2%wt-Gd and 4.9wt%-U235 Figure 1 High Burnup BWR Fuel Assembly Average U-235 =3.8wt% Gd 2 O 3 fuel : 5%wt-Gd and 3.6wt%-U235 Burnup calculations in an assembly-geometrical-model were performed by SRAC code[9] with the 107 neutron energy group cross section library prepared from JENDL-3.3 as the base cases. The ratio of 157Gd capture cross section between the modified and the original JENDL-3.3 libraries calculated by MVP is shown in Figure 2. JAEA-Conf 2011-002 Figure 2 Ratio of 157Gd capture cross section between modified and original libraries
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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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among these libraries, and the diff
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JAEA-Conf 2011-002
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JAEA-Conf 2011-002 - 日本原子力研究開発機構

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