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
JAEA-Conf 2011-002 - 日本原子力研究開発機構
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“Calculated burnup” which is<br />
Realistic history<br />
of<br />
Power, Void frac.<br />
etc.<br />
Measured burnup<br />
evaluated in ICFM and “Measured<br />
burnup” which is evaluated by<br />
radio-chemical analysis can be<br />
Calculated burnup<br />
different naturally. This sample<br />
burnup difference must<br />
considered appropriately.<br />
be<br />
An<br />
Averaged <br />
history through sample<br />
irradiation life<br />
example of difference between the<br />
"Calculated burnup" and "Measured<br />
sample [GWd/t]<br />
burnup [GWd/t]<br />
burnup" is shown schematically in<br />
Fig. 1. Schematic explanation of irradiation history<br />
Fig.1. Our approach to take the burnup difference into account is followings.<br />
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<strong>JAEA</strong>-<strong>Conf</strong> <strong>2011</strong>-<strong>002</strong><br />
<br />
<br />
The time dependent irradiation conditions from the beginning of sample life, BOL, to the end of<br />
sample life, EOL, which is given in the irradiation report supplied from ICFM, linear power rate, etc.<br />
are considered in burnup calculation directly.<br />
<br />
All irradiation conditions are averaged through BOL to EOL, and then burnup calculation is<br />
performed with the averaged irradiation condition.<br />
11) <br />
The irradiation history effect coefficient is a ratio of each isotope concentration in fuel calculated<br />
with averaged burnup history calculation over the concentration evaluated with realistic burnup<br />
history calculation at the EOL given in the report.<br />
<br />
Once the irradiation history coefficient was obtained, the effect of the change of the irradiation<br />
condition through the sample irradiation can be reflected to the isotope concentration evaluated for<br />
the arbitrary sample burnup with averaged burnup history calculation. Therefore the isotope<br />
concentration at the burnup evaluated by radiochemical analysis, "Measured burnup", can be<br />
obtained with consideration of the change of the irradiation condition correctly. Finally the<br />
calculated isotope concentration can be compared with measured isotope concentration to obtain<br />
the C/E value.<br />
<br />
<br />
For highest burnup BWR MOX sample of MALIBU, C/E values for heavy metals are shown<br />
below. Calculation results with all libraries are agreed to measurements within about 5% for most major<br />
actinides. On the other hand, difference between calculation and measurements are over 10% for