Abstract
Reactivity of LiF-BeF{sub 2}-ThF{sub 4}-UF{sub 4} and (TRU)Cl{sub 3}-NaCl (TRU: transuranium elements) molten salts with burnup has been thermodynamically analyzed with a free-energy minimization method. The results on the fluoride salts reproduced the operational experience of an experimental molten salt reactor (MSRE), particularly the distribution of fission products in the primary system and the corrosion of Hastelloy N. A possibility of U-Pd alloy segregation, which has been neglected, was newly identified. The results on the TRU chloride system indicate possibilities of (1) accumulation of PdTe which acts as a chemical potential source to cause the structural alloy corrosion, (2) segregation of Np-Pu-Pd alloys, (3) difficulty in valence control unlike that in the fluoride salts and (4) condensation of ZrCl{sub 4} vapor in the off-gas system. It was shown that the understanding of alloy systems Ni-Cr-Fe-Te, Pd-Ag-Te, U(Np)-Zr-Te etc. is important in feasibility studies of nuclear systems based on the molten salts. (author).
Ogawa, Toru
[1]
- Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Citation Formats
Ogawa, Toru.
Analysis of chemical reactivity of burnup molten salts.
Japan: N. p.,
1993.
Web.
Ogawa, Toru.
Analysis of chemical reactivity of burnup molten salts.
Japan.
Ogawa, Toru.
1993.
"Analysis of chemical reactivity of burnup molten salts."
Japan.
@misc{etde_10150747,
title = {Analysis of chemical reactivity of burnup molten salts}
author = {Ogawa, Toru}
abstractNote = {Reactivity of LiF-BeF{sub 2}-ThF{sub 4}-UF{sub 4} and (TRU)Cl{sub 3}-NaCl (TRU: transuranium elements) molten salts with burnup has been thermodynamically analyzed with a free-energy minimization method. The results on the fluoride salts reproduced the operational experience of an experimental molten salt reactor (MSRE), particularly the distribution of fission products in the primary system and the corrosion of Hastelloy N. A possibility of U-Pd alloy segregation, which has been neglected, was newly identified. The results on the TRU chloride system indicate possibilities of (1) accumulation of PdTe which acts as a chemical potential source to cause the structural alloy corrosion, (2) segregation of Np-Pu-Pd alloys, (3) difficulty in valence control unlike that in the fluoride salts and (4) condensation of ZrCl{sub 4} vapor in the off-gas system. It was shown that the understanding of alloy systems Ni-Cr-Fe-Te, Pd-Ag-Te, U(Np)-Zr-Te etc. is important in feasibility studies of nuclear systems based on the molten salts. (author).}
place = {Japan}
year = {1993}
month = {Jan}
}
title = {Analysis of chemical reactivity of burnup molten salts}
author = {Ogawa, Toru}
abstractNote = {Reactivity of LiF-BeF{sub 2}-ThF{sub 4}-UF{sub 4} and (TRU)Cl{sub 3}-NaCl (TRU: transuranium elements) molten salts with burnup has been thermodynamically analyzed with a free-energy minimization method. The results on the fluoride salts reproduced the operational experience of an experimental molten salt reactor (MSRE), particularly the distribution of fission products in the primary system and the corrosion of Hastelloy N. A possibility of U-Pd alloy segregation, which has been neglected, was newly identified. The results on the TRU chloride system indicate possibilities of (1) accumulation of PdTe which acts as a chemical potential source to cause the structural alloy corrosion, (2) segregation of Np-Pu-Pd alloys, (3) difficulty in valence control unlike that in the fluoride salts and (4) condensation of ZrCl{sub 4} vapor in the off-gas system. It was shown that the understanding of alloy systems Ni-Cr-Fe-Te, Pd-Ag-Te, U(Np)-Zr-Te etc. is important in feasibility studies of nuclear systems based on the molten salts. (author).}
place = {Japan}
year = {1993}
month = {Jan}
}