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This article refers to:
High burn-up operation and MOX burning in LWR; Effects of burn-up and extended cooling period of spent fuel on vitrification and disposal

Kawai K, Sagara H, Takeshita K, et al. High burn-up operation and MOX burning in LWR; Effects of burn-up and extended cooling period of spent fuel on vitrification and disposal. J Nucl Sci Technol. 2018.

https://doi.org/10.1080/00223131.2018.1480427

When the above article was first published online, the in-text citation for references 10, 11, 15, 16, and 17 were cited in wrong place. Those places are listed below:

Section 2.4.1

The repository with vertical emplacement concept in crystalline rock (hard rock) at the depth of 1,000m below the surface [10].

The previous report [10] describes that the … occupied area per waste package is 44.4m2. Furthermore, the report [10] … negligibly small.

Here all of three [10] should be replaced by [11]

Section 2.4.2

The upper temperature limit … the report [10].

However, it is reported … buffer material [10].

Here both [10] should be replaced by [11].

Section 3.3

In the case of 4 years … in the previous report [10], are needed for approximately 50 years on UO2 fuel, and 80 years on MOX fuel.

Here [10] should be replaced by [11].

Section 2.4.2

So analysis without gap was … this calculation [14,15].

Here [14,15] should be replaced by [15, 16].

Section 3.1.2

As the representatives of transuranium … 238Pu (T1/2 = 87.7y) are listed [16]. The … of 241Pu (T1/2 = 14.29y) [16]. 238Pu generating from alpha decay of 242Cm (T1/2 = 162.8d) significantly … spent fuel [16].

Here all of three [16] should be replaced by [17].

These errors have been corrected in both print and online versions.

Taylor & Francis apologizes for these errors.

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