Effect of the [U(IV)]/[U(III)] ratio on selective chromium corrosion and tellurium intergranular cracking of Hastelloy N alloy in the fuel LiF-BeF2-UF4 salt

Progress in the Science and Technology of Nuclear Reactors using Molten Salts

Open Access

Table 1

The [U(IV)]/[U(III)] ratio and metal impurities (wt.%) content in the fuel 71.2LiF-26.8BeF₂-2UF₄ salt mixture before and after corrosion tests.

Fuel salt	[U(IV)]/ [U(III)]	Ni	Cr	Fe	Cu	Te
After melting and 4 h exposure at T = 700 °C before beryllium treatment	1.7 × 10⁵	0.046	0.018	0.054	0.012	–
After double beryllium treatment and 2 h exposure at T = 700 °C	200	0.002	0.021	0.011	0.015	–
After 256 h specimens exposure in the corrosion test 1 at T = 700–720 °C and adding 5 g of Te metal for the first time	35	0.006	0.0026	0.019	0.0039	0.0029
After 248 h specimens exposure in corrosion test 2 at T = 760–800 °C and adding 1.63 g of NiF₂ and 5 g of Te metal for the second time	90	0.029	0.0043	0.0051	0.006	0.02

– Elements are not added and detected.

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