Economic Viability of Metallic Sodium-Cooled Fast Reactor Fuel in Korea

Table 2

Characteristics of reference SFR spent fuel.

New fuel
Nuclides	Annual input (g); (600 MW × 6)	Ratio (%)
^234U	4.19𝐸−02	0.11
^235U	2.05𝐸−02	0.05
^236U	1.53𝐸−02	0.04
^238U	2.73𝐸+01	70.35
U	2.72𝐸+01	70.55
^237Np	2.57𝐸−01	0.67
^238Pu	3.20𝐸−01	0.83
^239Pu	4.81𝐸+00	12.46
^240Pu	3.46𝐸+00	8.97
^241Pu	7.47𝐸−01	1.93
^242Pu	7.65𝐸−01	1.98
Pu	1.01𝐸+01	26.17
^241Am	3.89𝐸−01	1.01
^242Am	2.17𝐸−02	0.06
^243Am	2.95𝐸−01	0.76
^242Cm	3.77𝐸−04	0.00
^243Cm	1.71𝐸−03	0.00
^244Cm	2.00𝐸−01	0.52
^245Cm	6.44𝐸−02	0.17
^246Cm	3.69𝐸−02	0.10
MA	1.27𝐸+00	3.28
TRU	1.14𝐸+01	29.45
Total (HM)	3.862𝐸+01
Spent fuel
Nuclides	Annual output (g); (600 MW × 6)	Ratio (%)
^234U	3.72𝐸−02	0.11
^235U	1.04𝐸−02	0.04
^236U	1.68𝐸−02	0.05
^237U	1.10𝐸−04	0.00
^238U	2.37𝐸+01	72.07
^239U	4.00𝐸−05	0.00
U	23.809	72.3
^237Np	1.36𝐸−01	0.41
^238Np	1.53𝐸−04	0.00
^239Np	5.76𝐸−03	0.02
^238Pu	3.09𝐸−01	0.92
^239Pu	3.66𝐸+00	11.10
^240Pu	3.00𝐸+00	9.09
^241Pu	5.05𝐸−01	1.53
^242Pu	6.84𝐸−01	2.08
Pu	8.15𝐸+00	24.72
^241Am	2.69𝐸−01	0.82
^242MAm	3.25𝐸−03	0.01
^242Am	1.06𝐸−04	0.00
^243Am	2.37𝐸−01	0.72
^244Am	5.43𝐸−05	0.00
^242Cm	2.07𝐸−02	0.06
^243Cm	1.90𝐸−03	0.01
^244Cm	2.05𝐸−01	0.62
^245Cm	6.29𝐸−02	0.19
^246Cm	3.67𝐸−02	0.11
^247Cm	2.18𝐸−03	0.01
^248Cm	1.70𝐸−04	0.00
MA	9.81𝐸−01	2.98
TRU	9.13𝐸+00	27.72
Total (HM)	3.294𝐸+01

Burnup: 91,429 MWd/tHM, cooling: 5 years, calculation code: Origen 2.1, conversion ratio: 0.60.