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Science and Technology of Nuclear Installations

Volume 2014, Article ID 509858, 4 pages

http://dx.doi.org/10.1155/2014/509858
Research Article

Impact of Thorium Capture Cross Section Uncertainty on the Thorium Utilized ADS Reactivity Calculation

1Osaka University, 2-1, Yamadaoka, Suita-shi, Osaka 565-0871, Japan

2Hanoi University of Science, 334 Nguyen Trai, Thanh Xuan, Hanoi, Vietnam

Received 15 June 2014; Accepted 3 August 2014; Published 17 August 2014

Academic Editor: Eugenijus Ušpuras

Copyright © 2014 Thanh Mai Vu and Takanori Kitada. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

Abstract

Recently, the researches on fast neutron spectrum system utilized thorium fuel are widely conducted. However, the recent thorium cross section libraries are limited compared to uranium cross section libraries. The impact of thorium cross section uncertainty on thorium fuel utilized accelerator driven system (ADS) reactivity calculation is estimated in this study. The uncertainty of the caused by 232Th capture cross section of JENDL-4.0 is about 1.3%. The uncertainty of JENDL-4.0 is needed to be enhanced to provide more reliable results on reactivity calculation for the fast system. The impact of uncertainty of  232Th capture cross section of ENDF/B-VII is small (0.1%). Therefore, it will cause no significant impact of the thorium cross section library on the thorium utilized ADS design calculation.

1. Introduction

Thorium with its abundance in nature attracts a considerable attention to be a replacing fuel for uranium fuel. Moreover, with the feature that the TRUs production during an operating cycle is drastically reduced compared with the use of uranium, fuel cycle is favorable for the TRUs eliminating system such as the energy amplifier demonstrator facility (EADF) [1], thorium-fueled fast breed reactors (FBRs) [2], or the seed and blanket thorium-reprocessed fuel ADS [3]. However, experimental data and research results of thorium fuel are very limited compared with uranium fuel data and the calculation results of the thorium fuel utilized system could not be evaluated properly. In the previous publication, in order to verify the accuracy of 232Th cross section library in the thermal neutron spectrum system, the experiment on thorium critical cores was conducted. By comparing the experimental and calculated results, the underestimation of 232Th capture cross section of JENDL-4.0 [4] was found to cause the overestimation of effective multiplication factor of the thermal system, about 0.78% [5]. As mentioned above, thorium is widely utilized as the fuel for fast reactor concepts, especially ADS. Thus, it is necessary to investigate the impact of thorium capture cross section uncertainty on the reactivity calculation for the fast system utilized thorium fuel. In order to do so, the sensitivity calculations of effective multiplication factor of the seed and blanket thorium-reprocessed fuel ADS for 232Th capture cross section of JENDL-4.0 and ENDF/B-VII library were done. The uncertainty of the reactivity calculation results for 232Th capture cross section of these two cross section libraries is estimated and presented in this paper.

2. Calculation Model

The calculation model employed in this study is the 2D seed and blanket fuel ADS model [3]. The seed and blanket thorium-reprocessed fuel ADS was designed in order to achieve the efficient transuranic elements (TRUs) transmutation, simplification in the assembly fabrication, and in-core management and Th fuel utilization to produce energy. Lead-bismuth target is placed at center of the core. Sodium is used as coolant of the ADS. The hexagonal assembly is used in the subcritical core. 84 assemblies of individual reprocessed fuel in oxide form are inserted as seed and 96 assemblies of thorium in the oxide form are inserted as blanket of the core to make a heterogeneous configuration. The utilization of thorium fuel in blanket produces much less actinide compared with uranium fuel and the breeding 233U from thorium helps to compensate the burnt TRUs in reprocessed fuel, thus reducing the reactivity swing. Besides, the power contribution from the thorium fuel assemblies increases due to burnup, thus flattening the power peaking factor over the core life time. The core layout is shown in Figure 1. This system is designed to obtain a fast neutron spectrum system since the fast spectra are found to be advantageous for actinide transport from the standpoint that actinide fission-to-capture ratios are high in them [6]. Neutron energy spectra for target and fuel regions in seed and blanket ADS core are shown in Figure 2.

509858.fig.001
Figure 1: Seed and blanket ADS core layout.
509858.fig.002
Figure 2: Neutron energy spectra for target and fuel regions in ADS core [3].

3. Methodology

In order to investigate the influence of the 232Th capture cross section on reactivity calculation of the fast spectrum system, calculations of sensitivity coefficient of of the seed and blanket ADS using thorium-reprocessed fuel for 232Th capture cross section of JENDL-4.0 and ENDF/B-VII [7] are conducted by using SAGEP code [8] with 107-group cross section data obtained by SRAC2006-CITATION [9]. SAGEP is the code which calculates sensitivity coefficients in a multidimensional system on the basis of generalized perturbation theory. The sensitivity calculation scheme is presented in Figure 3. The sensitivity coefficient gives the relative change in the system multiplication factor value as a function of the relative change in the 232Th capture cross section data [10].

509858.fig.003
Figure 3: Sensitivity calculation scheme.

shows the covariance matrix that expresses the correlation in the 232Th cross section for energy groups. In this study, it is generated in a 107-group energy structure to map them into the same group structure as the sensitivity coefficients [10]. The covariance data for 232Th capture cross section is derived from the JENDL-4.0 and ENDF/B-VII evaluated nuclear data file using ERRORR module for NJOY99 code [11].

The uncertainty of the for 232Th capture cross section is derived as in (1) as follows: where is sensitivity coefficient of in a 107-group energy structure obtained by SAGEP code and the superscript means transposition, and is the covariance matrix for reaction of 232Th in a 107-group energy structure obtained by NJOY99 code:

4. Results and Discussion

Figure 4 illustrates the sensitivity coefficients of multiplication factor for capture reaction of 232Th of JENDL-4.0 and ENDF/B-VII cross section library obtained using SAGEP code. As we can see from the figure, sensitivity coefficients of 232Th capture cross section of two libraries mainly concentrate on the fast energy range and are almost the same because the difference between two libraries is very small (Figure 5). The covariance data of two libraries was generated using NJOY99 code and illustrated in Figures 6(a) and 6(b). As we can see from Figures 6(a) and 6(b), the correlation in the cross section for energy groups of JENDL-4.0 library is larger than that of ENDF/B-VII, especially in the energy range from 10 eV to 0.5 MeV, and it is the source to cause the difference in the uncertainty between two libraries. As derived from (1), the uncertainty of the caused by 232Th capture cross section of JENDL-4.0 is about 1.3%. This uncertainty would cause a significant influence in reactivity calculation in the thorium utilized ADS evaluation. Thus, the 232Th capture cross section of JENDL-4.0 is needed to be adjusted to give more reliable results on reactivity calculation for the fast system. On the other hand, the impact of uncertainty of 232Th capture cross section of ENDF/B-VII is small (0.1%). Therefore, its influence on reactivity calculation of Th fuel utilized ADS is not significant. It can be used for the fast spectrum ADS design purpose.

509858.fig.004
Figure 4: Sensitivity coefficient of for 232Th capture cross section of JENDL-4.0 and ENDF/B-VII library.
509858.fig.005
Figure 5: 232Th capture cross sections of JENDL-4.0 and relative difference among JENDL-4.0 and ENDF/B-VII.
fig6
Figure 6: (a and b) 232Th covariance matrix of reaction of JENDL-4.0 and ENDF/B-VII.

5. Conclusions

The impact of thorium cross section uncertainty on thorium utilized ADS reactivity calculation is investigated in this study. The sensitivity calculations were done on 232Th capture cross section of JENDL-4.0 and ENDF/B-VII. As a result, the uncertainty of the caused by 232Th capture cross section of JENDL-4.0 is about 1.3%. The impact of uncertainty of 232Th capture cross section of ENDF/B-VII is small (0.1%). The strong correlation in the cross section for energy group of JENDL-4.0 library is the origin of the difference in uncertainty between JENDL-4.0 and ENDF/B-VII libraries. The uncertainty of JENDL-4.0 is needed to be enhanced in order to provide more reliable results on reactivity calculation for the fast system. The influence of thorium capture cross section on reactivity calculation of ADS system is not significant; thus, it can be used in the thorium utilized ADS design calculation.

Conflict of Interests

The authors declare that there is no conflict of interests regarding the publication of this paper.

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