Time-Dependent Neutronic Analysis of a Power-Flattened Gas Cooled Accelerator Driven System Fuelled with Thorium, Uranium, Plutonium, and Curium Dioxides TRISO Particles

Table 1

Isotopic percentages and densities of the materials used in the investigated ADS.

Material	Density [g/]	Nuclide	Percentage
LBE	11.344	Pb	44.5
	9.8	Bi	55.5
He	0.1786	He	100
ThO2	9.88	^232Th	100
UO2	10.54	^235U	7.5, 15, 22.5
		^238U	92.5, 85, 77.5
PuO2	11.50	^238Pu	3.53535
		^239Pu	45.0154
		^240Pu	26.3505
		^241Pu	15.9640
		^242Pu	9.13483
CmO2	10.55	^242Cm	3.91520
		^243Cm	0.04721
		^244Cm	85.5422
		^245Cm	9.54125
		^246Cm	0.95413
Graphite	2.10	^12C	100
B4C	2.52	^10B	18.431
		^11B	81.569

Discharged PWR-MOX fuel with plutonium recycle, 1000 MWe reactor, 80% capacity factor, 33 MWd/kg, 2.5% thermal efficiency, and 150 days after discharge [28, p. 370, Table 8.5].