Immobilisation of Higher Activity Wastes from Nuclear Reactor Production of ⁹⁹Mo

Table 2

Analysed ILLW compositions from tanks at ANSTO that were produced from irradiated LEU UO₂ target produced at ANSTO.

Chemical composition		Nuclide	Half-life	Analysed activity of primary ILLW waste (MBq/L)	Analysed activity of secondary ILLW waste (MBq/L)
U (primary waste)	70–200 g/L	^144Ce	284 d	10–3500	16–6000
U (secondary waste)	8–35 g/L	^134Cs	2.07 y	0.35–5.3	<DL−2.4
Mg	<0.02–0.6 g/L	^137Cs	30.07 y	2600–8000	170–1800
Fe	< 0.05–0.4 g/L	^60Co	5.27 y	0.6–2	0.1–1
NH4^+	75–800 mg/L	^155Eu	4.76 y	<DL−90	<DL−20
HNO3	0.6–0.8 M	^95Nb	35.06 d	1–80	4–1100
Al	<DL−0.6 g/L	^106Ru/^106Rh	1.02 y/29.6 s	<DL−970	<DL−420
		^125Sb	2.77 y	<DL−13	<DL−18
		^95Zr	64 d	0.6–50	1–610
		^90Sr	28.78 y	2600–7700	120–1700
		^141Ce	32.5 d	<DL−1.3	<DL−30
		^91Y	58.51 d	<DL−125	<DL−380
		^103Ru	39.35 d	<DL−1.5	<DL−32
		^144Pr	17.2 m	nd	<DL−6

# Note: the data in this table are for from ~1 to 16 years after the tanks were filled. Lower activity values are generally from older waste. nd: not detected; DL: detection limit.