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Next-Gen Nuclear Power Plant Breaks Ground In China
An anonymous reader writes "The construction of first next-generation Westinghouse nuclear power reactor breaks ground in Sanmen, China. The reactor, expected to generate 12.7 Megawatts by 2013, costs 40 billion Yuan (~US$6 billion; that's a lot of iPods.) According to Westinghouse, 'The AP1000 is the safest and most economical nuclear power plant available in the worldwide commercial marketplace, and is the only Generation III+ reactor to receive Design Certification from the US Nuclear Regulatory Commission.' However, Chinese netizens suspect China is being used as a white rat to test unproven nuclear technologies (comments in Chinese)." Update: 04/20 07:28 GMT by T : As several readers have pointed out, this plant will generate much more than 12.7 Megawatts -- more like 1100 MWe.
solar panels on my own roof ... For greener energy, I think the premium is worth it.
Except for all the lead, mercury and cadmium needed to produce PV cells.
"I don't know, therefore Aliens" Wafflebox1
I doubt investors viewed a nuclear plant that's completely shut down for the better part of 6 years for cleanup as a sound investment.
You're correct. Nuke plants must be designed like modern chemical plants, which are more complex than nuke plants, handle boatloads of hazardous chemicals and have high availability.
"I don't know, therefore Aliens" Wafflebox1
It also states that this is a Pressurized Water Reactor, so it's probably more about generating by-products (esp. tritium) than it is about generating energy.
What are you talking about? If the control rods are Li then you get T. But if you want more interesting byproducts you leave the water out and go for a fast neutron spectrum *and* you get more tritium.
Its pretty clear that this is about generating electricity.
If information wants to be free, why does my internet connection cost so much?
At a cost of $5.85 billion, and assuming a lifetime of 40 years, an interest rate of 6%, this nuclear plant will have an annual mortgage of $389 million. With a nameplate rating of 1100 MW, if it runs 92% of the time, it will produce 8.9 billion kWh per year, so the capital repayments will amount to $0.044/kWh, assuming it doesn't go over budget. Assuming an optimistic cost for fuel around $0.005/kwh, this gives a total cost of $0.049/kWh, neglecting the cost of maintenance, waste disposal, and any risk of contamination or weapons proliferation.
Now let's look at a new wind farm. A 50 MW wind farm would cost around $96 million (at $1923/kW), which yields an annual capital repayment of $7.5 million (assuming a lifetime of 25 years). If the plant runs at a 35% capacity factor, it will produce 153 million kWh per year. So the total cost will be $0.049/kWh.
So, which would you rather spend $0.049/kWh on -- a nuclear plant that might go over budget, might leak radiation at some point during its life, whose waste will need to be carefully controlled and permanently stored somewhere that hasn't yet been identified; or a wind farm whose costs are much more certain and which comes without all those ancillary risks?
Yes, any individual wind farm will not provide a firm supply of power. But if a lot of wind farms are used, and they are combined with solar, geothermal and other renewable resources, they will provide a fairly stable power supply. There is also a lot of potential for reshaping electricity loads to match the supply of power (e.g., recharge electric vehicles when the wind is blowing or the sun is shining). And finally, if you must have a firm supply of power, you can convert a wind farm into a completely firm supply (at 35% of its nameplate rating) by spending about 10% extra and building rarely-used natural gas peaker plants ($634/kW * 35% = $222kW).
You've started with wrong numbers. The 40 billion Yuan cost is not for one reactor; it is for two of the same kind.
http://news.xinhuanet.com/english/2009-04/19/content_11217433.htm
So in fact, under your assumptions, the levelized cost of these reactors is 1/2 the cost of wind.
I did some reading on wikipedia about the various nuclear reactors recently. So being a lay-person, there's some existing common wisdom.
The placement of the nuclear reactor to the sea is a safety issue. You NEED guaranteed large cool water in the condenser stage or reactor goes boom. Wiki says thermal heat is regularly used as hot-water heaters - similar to geothermal heating in iceland. Whether anybody actually uses this is anybody's guess.. Obviously you'd need to pipe the hot water to end locations, so existing suburbia obviously isn't anywhere near able to handle this.
As for breeder reactors:
A) All fission reaction is of a breeding nature. The ratio of bred material is what the different processes produce. The bred ratio varies from 0.5 to 1.2. Where 1.01 is the accepted min ratio to be called a breeder reactor (producing more fissile fuel than originally introduced).
B) Any of the high breeder reactors utilize some aspect of fast-fission. Canada, India and Russia (and France?). Fast fission requires the ABSENCE of water, as water (either light or heavy(deutreonic)) captures energetic neutrons. Instead reaction-neutral coolants are used such as sodium, molten lead, etc. The problem here is related to safety. It is harder to produce intrinsic stability into non-water-based fission. Namely, in boiler-based reactors, when a greater ratio of steam is produced, the reaction naturally slows down, thus naturally regulating the system if electronic control mechanisms don't catch and compensate the control rods in time. With non steam based systems, you use complex chemical fission-poisons (in high-pressure based reactors as found in subs) or are fully reliant on control-rod actuators. (possible single point of failure). (note: I could be wrong about liquid metal based systems not having alternate backup mechanisms such as fission-poisons)
C) Chernobyl was a fast-fission reactor. And it's melt-down was related to the inability to shutdown quickly enough.. (specifically pressure-valve failures and insufficient monitoring which would have initiated the shutdown sooner) The environmental DAMAGE, however was due exclusively to the fact that it was a warhead manufacturing site, and the construction apparatus is too large to enclose with a hardened concrete barrier.
D) 70% of Thorium is in India. Thus, even though Thorium is (likely) a less efficient starting process for a breeder reactor, it's a better long-term strategy for India so as to provide energy independence. This isn't true of most countries.
E) Breeder reactors are the basis of nuclear warheads, thus it's an extremely hot-button issue. The US and Russia specifically discontinue their breeder reactors to comply with arms control. Russia now strip-mines their old warhead supply to fuel existing reactors both domestically and abroad. I suspect that China is not indifferent to this topic as well. The french reprocessing plant is actively/heavily monitored by the UN (IAEA).
F) The French rebreeding process is apparently NOT cost effective by any measure. The reason they do it is similar to the Indian Thorium objective - international energy independence.. China is not likely to be short-supplied of uranium mineral deposits - but I'm not aware of their status. I know Canda has massive Uranium supplies.
Currently boiler and pressure based reactors are 'cheap' to build and are cheap to operate (so long as raw Uranium ore is cheap). They both require 'pre-processing' of the ore to increase the concentration of U-235 to a sufficient level. So it's slightly more expensive in the long run as both ore prices will increase over time, and the added cost of pre-processing.
heavy-water and liquid-metal and inert-gas based reactors facilitate 'raw' Uranium, (e.g. U-238 and possibly thorium), and thus make the operating costs MUCH cheaper, but they don't have the longevity of trivial passive boiler-based plants, and thus the high capital costs are for shorter terms - and thus the average cost is higher.
-Michael
Not true. India has constructed thermal breeder reactors that use thorium-uranium fuel and heavy water moderator / coolant.
Nope. You just need to ensure you don't moderate the neutron spectrum. Supercritical water coolant has a high enough heat capacity and low enough neutron absorption cross section to make this feasible. Google for the Fast SCWR if you doubt me.
Nothing could be further from the truth. Chernobyl was a thermal spectrum reactor that was heavily moderated with graphite and cooled by water. Wikipedia has a good article about the causes of the chernobyl disaster. In summary it was caused by a heavily over moderated design ( the opposite of a fast reactor ) in combination with flawed control rod design and the lack of a containment building.
U-233 in thorium fuel has a much better capture to fission ratio than U-235 and Pu-239 which means you don't need a fast reactor to set up a breeding cycle. The waste products are also less long lived since the thorium cycle only produces trace actinides.
Every single plutonium based nuclear weapons program in existence has used low-burnup thermal reactors and not fast reactors. Furthermore most designs of fast reactors are not practical to be run on a frequent refueling cycle, making them substantially less suitable to produce weapons grade plutonium than more traditional methods. The reprocessing methods needed to recover the minor actinides are also unsuitable for separating pure plutonium, making the entire fuel cycle significantly less prone to proliferation than the thermal + PUREX cycle.
Russia has commercial breeder reactors in operation and actively develops fast breeder technology, including their BREST project based on lead coolant and dry reprocessing.
Only if you compare it to coal or traditional nuclear. Compared to wind and other low-co2 energy sources it works out cheaper. In addition the French programs currently aim for research. Commercial reactors would likely use different designs to optimize economics rather than flexibility of the experiments that can be run. In addition they use the PUREX process for recycling the waste as opposed to newer dry-reprocessing methods. Because dry reprocessing uses salt rather than water ( a moderator ) criticality problems are heavily reduced allowing the plant to be smaller and cheaper. Furthermore while liquid sodium reactors are indeed more expensive than pressurized water reactors, it is fully possible to use other coolants such as Lead or Supercritical water. These would with high probability lead to a much cheaper plant ( by 30% or so ) since the lack of a phase change in the coolant allows the plant to be simpler and smaller. In addition the higher temperature increases the efficiency to about 45% as opposed to 33% for more traditional designs.