Fused Salt Selection
The salt mixtures are chosen to make the reactor safer and more practical. Fluorides are favored because fluorine does not need expensive isotope separation (as chlorine does). It does not easily become radioactive under neutron bombardment. It also absorbs fewer neutrons and slows ("moderates") neutrons better. Low-valence fluorides boil at high temperatures, though many pentafluorides and hexafluorides boil at low temperatures. They also must be very hot before they break down into their simpler components, such molten salts are "chemically stable" when maintained well below their boiling points.
Reactor salts are usually close to eutectic mixtures to reduce their melting point. A low melting point simplifies melting the salt at startup and reduces the risk of the salt to freeze in the heat exchanger.
Some salts are so useful that isotope separation is worthwhile. Chlorides permit fast breeder reactors to be constructed using molten salts. Not nearly as much work has been done on reactor designs using them. Chlorine must be purified to chlorine-37 to reduce production of sulfur tetrafluoride when the radioactive chlorine decays to sulfur. Similarly, any lithium present in a salt mixture must be in the form of purified lithium-7 to reduce tritium production (the tritium forms hydrogen fluoride).
Due to the high "redox window" of fused fluoride salts, the chemical potential of the fused salt system can be changed. Fluorine-Lithium-Beryllium ("FLiBe") can be used with beryllium additions to lower the electrochemical potential and almost eliminate corrosion. However, since beryllium is extremely toxic, special precautions must be engineered into the design to prevent its release into the environment. Many other salts can cause plumbing corrosion, especially if the reactor is hot enough to make highly reactive hydrogen.
To date, most research has focused on FLiBe, because Lithium and Beryllium are reasonably effective moderators, and form a eutectic salt mixture with a lower melting point than each of the constituent salts. Beryllium also performs neutron doubling, improving the neutron economy. This process occurs when the Beryllium nucleus re-emits two neutrons after absorbing a single neutron. For the fuel carrying salts, generally 1% or 2% (by mole) of UF4 is added. Thorium and plutonium fluorides have also been used.
| Material | Total neutron capture relative to graphite (per unit volume) |
Moderating ratio (Avg. 0.1 to 10 eV) |
|---|---|---|
| Heavy water | 0.2 | 11449 |
| Light water | 75 | 246 |
| Graphite | 1 | 863 |
| Sodium | 47 | 2 |
| UCO | 285 | 2 |
| UO2 | 3583 | 0.1 |
| 2LiF–BeF2 | 8 | 60 |
| LiF–BeF2–ZrF4 (64.5–30.5–5) | 8 | 54 |
| NaF–BeF2 (57–43) | 28 | 15 |
| LiF–NaF–BeF2 (31–31–38) | 20 | 22 |
| LiF–ZrF4 (51–49) | 9 | 29 |
| NaF–ZrF4 (59.5–40.5) | 24 | 10 |
| LiF-NaF–ZrF4 (26–37–37) | 20 | 13 |
| KF–ZrF4 (58–42) | 67 | 3 |
| RbF–ZrF4 (58–42) | 14 | 13 |
| LiF–KF (50–50) | 97 | 2 |
| LiF–RbF (44–56) | 19 | 9 |
| LiF–NaF–KF (46.5–11.5–42) | 90 | 2 |
| LiF–NaF–RbF (42–6–52) | 20 | 8 |
Read more about this topic: Molten Salt Reactor
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