Characterization of Waste Generated from Nuclide Management Process in Waste Burden Minimization Technology for Spent Nuclear Fuel

Table 5

Radiological characteristics of Sr waste form according to Sr/Ba ratio.

Year	0.3	1	3	10	30	100	300	1000
Activity (Bq/g)
SrTiO3	2.711E + 12	2.665E + 12	2.537E + 12	2.136E + 12	1.305E + 12	2.328E + 11	1.690E + 09	5.515E + 01
Sr0.8Ba0.2TiO3	2.058E + 12	2.022E + 12	1.925E + 12	1.621E + 12	9.904E + 11	1.767E + 11	1.283E + 09	4.186E + 01
Sr0.6Ba0.4TiO3	1.468E + 12	1.443E + 12	1.373E + 12	1.156E + 12	7.065E + 11	1.260E + 11	9.151E + 08	2.986E + 01
Sr0.5Ba0.5TiO3	1.194E + 12	1.174E + 12	1.117E + 12	9.404E + 11	5.747E + 11	1.025E + 11	7.444E + 08	2.429E + 01
Sr0.4Ba0.6TiO3	9.329E + 11	9.170E + 11	8.729E + 11	7.348E + 11	4.490E + 11	8.010E + 10	5.816E + 08	1.898E + 01
Sr0.2Ba0.8TiO3	4.457E + 11	4.381E + 11	4.170E + 11	3.510E + 11	2.145E + 11	3.827E + 10	2.779E + 08	9.066E + 00
BaTiO3	4.729E + 05	4.516E + 05	3.958E + 05	2.496E + 05	6.678E + 04	6.631E + 02	1.253E − 03	1.163E − 23
Heat generation (W/m^3)
SrTiO3	1.247E + 06	1.226E + 06	1.167E + 06	9.822E + 05	6.002E + 05	1.071E + 05	7.775E + 02	2.537E − 05
Sr0.8Ba0.2TiO3	9.820E + 05	9.652E + 05	9.188E + 05	7.733E + 05	4.725E + 05	8.430E + 04	6.121E + 02	1.998E − 05
Sr0.6Ba0.4TiO3	7.258E + 05	7.133E + 05	6.790E + 05	5.715E + 05	3.492E + 05	6.230E + 04	4.524E + 02	1.476E − 05
Sr0.5Ba0.5TiO3	6.006E + 05	5.904E + 05	5.620E + 05	4.730E + 05	2.890E + 05	5.156E + 04	3.744E + 02	1.222E − 05
Sr0.4Ba0.6TiO3	4.773E + 05	4.692E + 05	4.466E + 05	3.759E + 05	2.297E + 05	4.098E + 04	2.975E + 02	9.710E − 06
Sr0.2Ba0.8TiO3	2.357E + 05	2.317E + 05	2.205E + 05	1.856E + 05	1.134E + 05	2.023E + 04	1.469E + 02	4.795E − 06
BaTiO3	2.081E − 01	1.987E − 01	1.741E − 01	1.098E – 01	2.940E − 02	2.918E − 04	5.515E − 10	5.117E − 30