mheslep said:
Assuming you are referring to sodium cooled fast spectrum design something like
this, how does any kind of failure of the remote steam generator off the secondary loop lead to a sodium - water reaction? I would think the hydrogen formation problem is many times more likely in the existing water cooled BWR/PWR designs with water and zirc rods under pressure in the pressure in the primary.
I was referring to the Clinch River Breeder Reactor as it was designed in the 1970s, which did have two sodium loops and a pressurized-water loop (Rankine cycle).
Under normal conditions, the Zr-water reaction takes place slowly over the life of the fuel, which was 3 years, but now more like 4 to 6 years, or up to 8 in some cases. The corrosion produces a relatively small amount of hydrogen. The concern over aggressive hydrogen production applies under accident conditions where the fuel is overheated. I should also add that in PWRs, hydrogen is added to the water (~30-35 cc/kg) to suppress radiolysis of the coolant (water) in the core, and it is also added to BWRs under so-called hydrogen water chemistry, but that has been modified with the use of noble metals with so-called noble metal chemical addition.
In the case of Na-water, that could happen under normal operating conditions. See the link to the NRC backgrounder on steam generator replacement. During the 1970s, it was discovered that Inconel-600 tubes were eroding/corroding faster than anticipated, and occasional tube failure was a part of normal operation at a number of plants. Rather than serving 40 years as designed, many steam generators had to be replaced.
Another article on steam generators - http://www.power-eng.com/articles/print/volume-100/issue-1/features/steam-generator-replacement-overview.html
In the case of the Na-water heat exchanger, the water is necessarily under pressure. It was likely that a tube would fail on the waterside, and if water infiltrated the secondary Na loop, the concern was the vigorous hydrogen production. Now there was a concept that had a double tube (tube-in-tube) design. Nevertheless, the CRBR was cancelled.
I'm not sure about the EBR-II system, so I'll have to look into it.
When I entered graduate school in the early 1980s, I was enthusiastic about fast reactors and fusion. Then we had a visit from a manager of a fast reactor program who informed us that he was letting 300 people go and cancelling a fast reactor project. And fusion was always 10 or so years away. Nevertheless, some my research was on small compact fast reactors for space power applications.