Flyboy said:
There is a practical upper limit to how thermally efficient a PWR can be, mainly because of the upper limits of the primary coolant loop being, well, pressurized water. The switch to a different primary loop coolant is, imo, long overdue. You can run the coolant loop at a higher temperature, which if my understanding is correct, produces better efficiency. It certainly will reduce the risk of boiling off the coolant if you get a leak, so there’s much higher safety margin there.
Some of the German pre-Konvoi plants realized nearly 37.6% thermal efficiency, which was actually realized on the secondary side with improved turbine blade designs and improved sealing at the blade tips to reduce by-pass flow.
The has been consideration of supercritical LWRs, at higher temperature and pressure. Three major challenges are the internal pressure of the fuel elements (about 30% of fission products are Xe,Kr isotopes, and smaller fraction (Se, Br, Sr; Te, I, Cs) are volatile or gaseous depending on fuel temperature), the corrosion of the structural materials (fuel cladding, core support structure, and primary loop (reactor pressure vessel, piping and coolant pumps, and heat exchangers).
Increasing the primary system temperature, even if one deploys a low-vapor-pressure salt, shifts the challenges to the heat exchange and secondary side; what thermodynamic cycle will be used to spin the turbines - Brayton (gas), Rankine (water to steam to water), or ? Now the secondary side has to withstand the higher temperature corrosion environment. How often will major components (heat exchange, piping, reheaters, turbines) have to be replaced? Also, what happens if the heat exchanger tubing/plate is breached, and the secondary coolant enters the primary system.
And there are other challenges - depending on the fuel design. How to level out the burnup in the fuel? What will be the disposition of used fuel? How to handle breached (failed) fuel?
Another interesting problem is the photo-disintegration of Be from gammas above the threshold for the reaction. There are some other photonuclear reactions of concern.
Flyboy said:
On the flip side, you now have irradiated salts that you have to figure out what to do with, as well as needing to figure out what kinds of problems can crop up. You won’t have, what, 70ish years of service experience with a salt coolant loop like you do with PWRs.
There is that challenge as well. When we built the first LWRs, we did so with essentially no experience. There we small cores/reactors like Saxton, Zorita, and Shippingport. The folks went with what they knew in terms of structural alloys used in conventional power plants, e.g., type 300 stainless steels, and in some cases, Ni-based alloys, e.g., Inconels and Incoloys, some of which came from the X-aircraft programs.
It took a couple of decades to adjust the compositions and tweak the manufacturing processes to get improved performance. Zircaloys were developed in the 1950s, and because standard in the 1970s, but still it took a couple of decades to make improvements in performance, and in some cases, newer alloys were developed in the early 2000 into the 2010s. Accident tolerant fuel development is still ongoing. Since it takes 5 to 6 years to get to the design life in a reactor, with a lead time for development of 5 to 10 years, and a couple of year after irradiation to get PIE results, and perform additional testing (e.g., simulated LOCA and transient testing) not permissible in commercial power reactors, it can take up to 15 years to vet a new design. In parallel, one has to develop a suite of codes that simulate the performance of the fuel, reactor and power plant under normal, off-normal, design basis (hypothetical) accident (DBA) and now beyond-design-basis accident (BDBA) conditions.