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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<strong>JAEA</strong>-<strong>Conf</strong> <strong>2011</strong>-<strong>002</strong><br />
Sensitivity Analysis for Curium Isotope Concentrations<br />
of Light Water Reactor Mixed-Oxide Burned Fuel<br />
Go CHIBA and Makoto ISHIKAWA<br />
Research Group for Reactor Physics, Japan Atomic Energy Agency<br />
Tokai-mura, Naka-gun, Ibaraki-ken 319-1195<br />
e-mail: chiba.go@jaea.go.jp<br />
With a help of the depletion perturbation theory, sensitivities of curium isotope concentrations<br />
to nuclear data are calculated for a light water reactor mixed-oxide burned fuel. Through the<br />
sensitivity analysis, phenomenon of the curium isotope generations during a reactor operation is<br />
well understood. In addition, important nuclear data for accurate prediction of the curium<br />
isotope concentrations are successfully specified. These information are helpful to investigate a<br />
cause of discrepancy between experimental and calculation values for the curium isotope<br />
concentrations.<br />
1. Introduction<br />
In order to validate prediction calculation methods for fuel depletion of light water reactors,<br />
some experimental programs focusing on fuel depletion, such as the MALIBU program [1], have<br />
been conducted, and the experimental data obtained through these programs have been analyzed<br />
by calculation methods used for core design of light water reactors. As shown in Ref. [2], there<br />
are still some discrepancies between experimental and calculation values even if modern nuclear<br />
data files are employed, and some differences are observed among results obtained with different<br />
nuclear data files.<br />
A sensitivity analysis, which is performed with sensitivity coefficients of nuclide<br />
concentrations (number densities) to nuclear data, is quite a useful technique to investigate causes<br />
of the discrepancies and the differences between different nuclear data files. Moreover,<br />
sensitivity coefficients can be utilized also to quantify uncertainties associated with nuclear data if<br />
uncertainty data for the nuclear data are available.<br />
Sensitivity coefficients of nuclide concentrations to nuclear data can be easily calculated by the<br />
depletion perturbation theory. The depletion perturbation theory for the zero-dimensional<br />
nuclide field equation has been initially proposed by Gandini [3], and has been extended to the<br />
nuclide/neutron coupled field by Williams [4]. Application of the depletion perturbation theory<br />
can be found in some literatures. For example, we can see some examples of the application of<br />
this theory to sensitivity studies for fission product concentrations [5][6].<br />
In a light water reactor mixed-oxide fuel, curium isotopes are generated and are accumulated<br />
through a reactor operation. The accurate prediction for the curium isotope concentrations after<br />
burn-up is not easy since the many ancestor nuclides contribute to the curium isotope generations.<br />
In the present study, we perform a sensitivity analysis focusing on curium isotope concentrations<br />
of a light water reactor mixed-oxide burned fuel with the depletion perturbation theory.