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JAEA-Conf 2011-002 - 日本原子力研究開発機構

JAEA-Conf 2011-002 - 日本原子力研究開発機構

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Koichi IEYAMA, Kosuke SHIMOZATO, Takanori KITADA<br />

Osaka University, 2-1Yamada-oka, Suita-shi, Osaka, Japan, 565-0871<br />

k-ieyama@ne.see.eng.osaka-u.ac.jp<br />

Analyses were performed to verify nuclear data of some rare-earth elements(Dy, Ho, Er and Tm) by using<br />

the continuous energy Monte-Carlo code: MVP, and to evaluate the validity of the cross section libraries<br />

(JENDL-4.0, JENDL-3.3, ENDF/B-VII.0 and JEFF-3.1) by comparing infinite dilution cross section in SRAC<br />

library 107 energy groups. The difference of energy-integrated capture rate among these libraries is about 0.1%<br />

for Dy and 0.2% for Er at both E3 and EE1 coresand the influence on energy-integrated capture rate by the<br />

difference of the cross section libraries is small at these cores.Though there is a relatively large difference in<br />

the C/E value of Ho2O3 at EE1 core between ENDF/B-VII.0 and JEFF-3.1, the difference of energy-integrated<br />

capture rate between these libraries is about 0.8% at EE1 core.<br />

<br />

<strong>JAEA</strong>-<strong>Conf</strong> <strong>2011</strong>-<strong>002</strong><br />

The rare-earth elements would be useful as an advanced burnable poison. However, only a few critical<br />

experiments with rare-earth element have been carried out so far to validate the accuracy of their nuclear data.<br />

Critical experiments with four rare-earth<br />

0.05<br />

elements (Dy, Ho, Er and Tm) at Kyoto<br />

University Critical Assembly (KUCA) 0.04<br />

E3 B3/8"P36EU(3)<br />

H/235U 317<br />

were performed in two kinds of cores (E3 0.03<br />

EE1 B1/8"P60EU-EU(5)<br />

and EE1 core) with different neutron<br />

H/235U 52<br />

spectra shown in Fig. 1. The validity of<br />

0.02<br />

cross section of rare-earth elements was 0.01<br />

estimated from the analysis of measured<br />

0<br />

data by the continuous energy 1.E-03 1.E-01 1.E+01 1.E+03 1.E+05 1.E+07<br />

Monte-Carlo code; MVP and infinite<br />

energy[eV]<br />

dilution cross section in SRAC library<br />

107 energy groups.<br />

Fig. 1 Neutron Spectrum for each unit cell<br />

normalized neutron flux[-]

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