Table 2.

Reactor-specific parameters for burnup monitors based methods: (a) effective fission cross-section ratios used in irradiation-averaged fission yield evaluation [14, 16–18]; (b) ²³⁸U contribution to fission and effective absorption cross sections used in the method proposed in Section 5.2; (c) effective absorption-to-fission cross-section ratios for use in the ASTM E244 and E321 methods [13, 30].

			MOX	UO2						U alloy
			PWR/BWR			PWR/BWR	Magnox/AGR	RBMK	Candu	MTR
			< 10% Pu			< 6% enr.	< 5% enr.	< 3% enr.	Nat. U			HEU (20–90% enr.)
			1.8			2.4	2.8	←( * )	1.8			←
(a)			2.2			2.6	2.8	←	2.1			←
			62 × 10−4			23 × 10−4	7.9 × 10−4	←	4.3 × 10−4			←
(b)			7.80%			7.80%	5.60%	3.60%	5.20%			0.50%
			1.3			1.22	1.2	←	1.18			1.2
			0.41			0.16	0.073	←	0.035			0.073
(c)			1.59			←	←	←	←			←
			1.49			←	←	←	←			←