Posted on 09/01/2005 1:14:18 PM PDT by cowboyway
Similar designs in the US have been done (on paper) by Argonne and other researchers. If you google for
STAR-LM, SSTAR, EPBR, 'nuclear battery' (UC Berkeley design), you'll find more info.
more links:
http://www.rae.anl.gov/research/ardt/hlmr/
"STAR-LM"
"The small modular reactor is envisioned to be liquid-metal-cooled and run up to 30 years without requiring fresh fuel. At that point, the fuel would be cut out for burial or for reprocessing. The fuel feedstock could be natural or depleted uranium, or the reactor might run on excess weapons-grade plutonium."
"The reactor would have a sealed core -- a feature to make it more proliferation-resistant. It also would have passive safety features, so it would go into a safe shutdown mode without human intervention."
The designs seems simple enough and with enough margins on operation and safety that IMHO they are the most promising form of "fast" reactors. I do think eventually we will need both 'once-through' and 'fast' breeder type reactors. What's really neat is that IMHO these fast reactors could probably build at LOWER cost than a PWR/BWR, due to lower complexity of system overall.
Key points:
1. The core sits in a pool of lead at near atmospheric pressure. The kind of corrosion and need for active safety measures that pressurized systems creates goes away. lead is liquid over a huge range of temperatures.
Moreover, if you use air or CO2 instead of steam to power the turbines, you would avoid the corrosive components and extreme pressures of current nukes entirely. All but the reactor core would be similar to a gas turbine plant.
2. "Pb-208 (54% of naturally-occurring lead) is transparent to neutrons. " This means you can have a 'fast' reactor, ie, breeder type that uses the fuel much more efficiently.
The problem with 'fast' reactors is that they seem more dangerous due to margins of going super-critical.
But this is the beauty of Pb: the high melting point and
lack of above atmospheric pressure make this
Unlike sodium it wont create fires if exposed to air. So it has advantages over sodium-cooled.
3."Natural convection heat transport at all power levels eliminates the need for main coolant pumps further contributing to cost competitiveness."
I feel this design and the PBMR are probably the safest designs of nuclear power plants, because of passive heat removal and margins.
4. Experience of Russians is a valuable validator of the concepts:
"A smaller and newer Russian design is the Lead-Bismuth Fast Reactor (SVBR) of 75-100 MWe. This is an integral design, with the steam generators sitting in the same Pb-Bi pool at 400-480°C as the reactor core, which could use a wide variety of fuels. ... (Russia built 7 Alfa-class submarines, each powered by a compact 155 MWt Pb-Bi cooled reactor, and 70 reactor-years operational experience was acquired with these.)"
5. Long life of the fuel in the reactor is positive for nuclear proliferation reasons, nuclear waste reasons and operating cost reasons.
So I think we should develop this design. IMHO, it's a winner.
"A power station with 16 such modules is expected to supply electricity at lower cost than any other new Russian technology as well as achieving inherent safety and high proliferation resistance."
So what are the construction/operating-cost differences between these and the helium gas-turbine designs? One thing's for sure, in the US proliferation is not a worry.
"...with Iran in a race with France to become the second Islamic nation with the bomb."
Heh heh! I like that..that's a good one!
I'd like to see a powerplant with eight 400MW helium gas turbine reactors, on a rotating schedule with 7 reactors fully on line and one down for preventive maintenance (and as a reserve). Imagine one of those in each of the 50 States.
Sounds like Saudi Arabia's worst nightmare.
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