5-10 Safe and Efficient Criticality Control of Spent Fuels

- Development of Calculation Code and Database for Burnup Credit -

Fig.5-21 The spent fuel isotopic composition database SFCOMPO

Fig.5-21 The spent fuel isotopic composition database SFCOMPO

SFCOMPO is now operated by OECD/NEA to obtain and evaluate new isotopic composition data of spent nuclear fuel under an international collaborative framework.
http://www.nea.fr/html/science/wpncs/sfcompo/

Fig.5-22 Effect of Neutron Capture Reactions of 147,148 Nd on 148 Nd (From the reference)

Fig.5-22 Effect of Neutron Capture Reactions of 147,148Nd on 148Nd (From the reference)

Burnup of spent fuel is evaluated by measurement of 148Nd quantities. This figure shows that the abundance of 148Nd is affected by neutron capture reactions of 147Nd and 148Nd. It enables us to conduct quantitative evaluation of the 147Nd and 148Nd effect in burnup calculations.

One of the most important issues in safety evaluation of fuel cycle facilities is to prevent a criticality accident. The neutron multiplication factor of the nuclear fuel in fuel cycle facilities decreases as the fuel burnup proceeds. In Japan, instead of burnt fuel, un-irradiated fuels are assumed in the criticality safety evaluation of fuel cycle facilities except a commercial spent fuel reprocessing plant. This is because assuming fresh fuel composition is conservative and simple. However, the economical disadvantage is large because of the excessive safety margin. For example, the number of fuel assemblies that can be transported in one time as well as stored in a facility will be decreased.

JAEA has conducted studies on burnup credit, a concept taking into account the decrease in the neutron multiplication factor with the burnup of fuel into the criticality safety evaluation.

We developed the integrated burnup calculation code system SWAT in order to evaluate isotopic composition accurately. This is because the isotopic composition of SF is a key issue in the burnup credit. SWAT will be a kernel of an integrated criticality safety evaluation code system under development for a comprehensive criticality safety evaluation including burnup calculation.

We also developed the spent fuel isotopic composition database "SFCOMPO" which arranges and archives isotopic composition data to be used for benchmarking of burnup calculation codes including SWAT. We widely distributed such data to researchers through the framework of OECD/NEA (Fig.5-21). For precise evaluation of burnup calculation codes, we evaluated error of burnup estimation by measuring changes in Neodymium-148 which are induced by neutron capture reactions. (Fig.5-22)

In summary, we are developing calculation codes and collecting experimental data which are required for expanding use of the burnup credit concept in Japan. These results are used in JAEA as well as in industries and Japan Nuclear Energy Safety Organization (JNES).

Reference
Suyama, K. et al., Effect of Neutron Induced Reactions of Neodymium-147 and 148 on Burnup Evaluation, Journal of Nuclear Science and Technology. vol.42, no.7, 2005, p.661-669.

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