More recently, governments have been supporting research and development of small reactors, but only two examples of one model from Russia have been built. Some private corporations are also working on new reactor designs with their own funds, but none have completed licensing. Generically, these new designs are called SMRs, which stands either for small modular reactors or, less often, small and medium reactors. The International Atomic Energy Agency defines small reactors as less than 300 MWe, and medium reactors as 300-700 MWe. The word modular refers to how proponents see these reactors as being deployed, which would be at power plants with 4 to 20 units.
The main appeal of these reactors is the capital cost of any one of them. Large nuclear reactors have a long history of enormous cost overruns on the initial estimates, which are also enormous. The 1600 MWe European Pressurized Reactor (EPR) currently being built at Olkiluoto in Finland was sold as a turnkey contract for €3.3B, but cost overruns have pushed the price to over €6B - so far. SMR proponents are projecting costs of their reactors from $50M to $1B, depending on the design. But almost all of the designs haven't reached the final detailed design stage, so it is possible (and quite likely) that the estimates could turn out to be as wrong as ones for large reactors. However, even if the estimates are wrong, the smaller reactors would be less risky for utilities to build because an overrun with any one reactor wouldn't threaten to bankrupt the company.
According to proponents, there are several other positive aspects to SMRs, though they don't all have the same ones. For most, the smaller size would allow large sections to be mass manufactured off-site in controlled factory conditions, with only final assembly done on site. This has the potential (in theory) to improve quality assurance over large reactors, which are largely custom built on-site of essentially one-off parts. Some designs are small enough that they would be delivered as pre-fueled packages and then sent back to the factor when the fuel is exhausted. That could significantly reduce the amount of waste generated at the power plant site, eliminate complicated on-site refueling operations, and potentially reduce the chances of fuel theft or proliferation. It would not eliminate the chance of accidents or theft during transit, however, though the latter would be difficult. Most of the designs call for the reactors to be housed underground, which basically eliminates the chance of damage from missiles or airplanes. However, the crisis at Fukushima Dai-ichi has shown that backup systems can be critical. Some of the new designs still require active cooling by a backup system after shutdown, and most leave these systems exposed. Finally, depending on the size, some of the new reactors could be deployed in rural or remote locations where only a moderate amount of power is needed and a large reactor would overwhelm the local grid.
The main question about these designs is whether or not they would, when deployed en mass, end up being safer. Clearly, if there was an accident with any one reactor, it would make less of a mess than a larger reactor would. But I doubt whether 1000 reactors each of 100 MWe would be monitored and inspected as carefully as a set of 100 reactors of 1000 MWe. That means each small reactor deployed has to have a radically lower probability of having its containment breached to make up for poorer monitoring and greater numbers. Some of the designs may actually be that much safer, but until a plant goes through a rigorous licensing process, we have no way of knowing how good any of them are.
Most of the reactors listed below were pulled from two documents from the IAEA (1, 2), with others coming from Wikipedia or general web surfing. Because there are so many of them, I may have missed a few. I've classified some reactors as "abandoned" in the status field if I was unable to find them on the originating organization's website, though the lack of public information doesn't necessarily mean a project has been ended. The converse is true as well.
By neutron speed, there are:
By major type, there are:
- 14 pressurized water reactors (PWR)
- 13 lead-cooled fast reactors (LMFR or LFR)
- 10 light water reactors (LWR - light water reactors that are not typical BWRs or PWRs)
- 8 sodium-cooled fast reactors (LMFR or SFR)
- 6 high temperature gas-cooled reactors (GCR or HTGR)
- 4 boiling water reactors (BWR)
- 2 molten salt-cooled reactors (? - no common acronym)
- 2 gas-cooled fast reactor (GFR)
- 2 lead-bismuth-cooled fast reactor (LMFR or LFR)
- 1 lithium-cooled fast reactor (? - no common acronym)
- 1 heavy water-moderated pressurized water reactor (HWBWR)
- 1 molten salt reactor (MSR)
Reactor | Type | MWt | MWe | Country | Company | Status | Refuelling |
---|---|---|---|---|---|---|---|
4S | Sodium-cooled fast reactor | 30 | 10 | Japan | Toshiba Power Systems | US pre-licensing | factory |
4S-LMR | Sodium-cooled fast reactor | 135 | 50 | Japan | CRIEPI | concept | factory |
ABV-6 | Pressurized water reactor | 60 | 12 | Russia | OKBM | concept | on-site |
ACACIA | High temperature gas-cooled reactor | 60 | 23 | Netherlands | NRG | abandoned | on-site |
AFPR-100 | Light water reactor | 300 | 100 | USA | PNNL | abandoned | factory |
AFR-300 | Sodium-cooled fast reactor | 800 | 300 | USA | ANL | concept | on-site |
AHTR | Molten salt-cooled reactor | 600 | 300 | USA | ORNL / UCB | concept | on-site |
AHWR | heavy water-moderated boiling water reactor | 260 | 100 | India | NPCIL | detailed design | on-site |
ARC-100 | Sodium-cooled fast reactor | 920 | 300 | USA | Advanced Reactor Concepts | concept | on-site |
BGR-300 | Gas-cooled fast reactor | 300 | 130 | Russia | RRC Kurchatov | concept | factory |
BMN-170 | Sodium-cooled fast reactor | 400 | 170 | Russia | OKBM | abandoned | on-site |
BN GT-300 | Sodium-cooled fast reactor | 730 | 300 | Russia | IPPE | concept | on-site |
BREST | Lead-cooled fast reactor | ? | 300 | Russia | NIKIET | concept | on-site |
CAREM | Light water reactor | 100 | 27 | Argentina | INVAP / CNEA | Argentina pre-licensing | on-site |
CCR | Boiling water reactor | 900 | 300 | Japan | Toshiba Power Systems | abandoned | on-site |
CHTR | Lead-buismuth-cooled fast reactor | 0.1 | 0.02 | India | BARC | concept | factory |
DRX | Pressurized water reactor | 0.75 | 0.15 | Japan | JAERI | abandoned | on-site |
ELENA NTEP | Light water reactor | 3.3 | 0.07 | Russia | RRC Kurchatov | abandoned | factory |
EM2 | Gas-cooled fast reactor | 500 | 240 | USA | General Atomics | concept | factory |
ENHS | Lead-cooled fast reactor | 125 | 50 | USA | LLNL / UCB | concept | factory |
FBNR | Pressurized water reactor | 134 | 40 | Brazil | FURGS | concept | factory |
GT-MHR | High temperature gas-cooled reactor | 600 | 287 | USA | General Atomics | concept | on-site |
GTHTR-300 | High temperature gas-cooled reactor | 600 | 274 | Japan | JAERI | abandoned | on-site |
HTGR | High temperature gas-cooled reactor | 220 | 100 | Japan | First Atomic Power Industry Group | concept | on-site |
HTR-PM | High temperature gas-cooled reactor | 380 | 160 | China | CNNC | prototype construction | on-site |
IRIS | Pressurized water reactor | ? | 335 | USA | Westinghouse (Toshiba) | US pre-licensing | on-site |
ISIS | Pressurized water reactor | 650 | 200 | Italy | Ansaldo Nucleare | abandoned | on-site |
KALIMER | Lead-cooled fast reactor | 392 | 150 | Korea | KAERI | concept | on-site |
KAMADO | Light water reactor | 1000 | 300 | Japan | CRIEPI | abandoned | on-site |
KLT-40S | Pressurized water reactor | 150 | 35 | Russia | OKBM/ Atomstroyexport | production | on-site |
LSPR | Lead-cooled fast reactor | 150 | 53 | Japan | RLNR-TIT | abandoned | factory |
MARS | Molten salt-cooled reactor | 16 | 6 | Russia | RRC Kurchatov | abandoned | factory |
MARS | Pressurized water reactor | 600 | 150 | Italy | U. of Rome / ENEA | abandoned | on-site |
MASLWR | Pressurized water reactor | 150 | 45 | USA | NuScale | US pre-licensing | factory |
MBRU-12 | Sodium-cooled fast reactor | 48 | 12 | Russia | OKBM | abandoned | factory |
MDP | Sodium-cooled fast reactor | 840 | 325 | Japan | CRIEPI | abandoned | on-site |
mPower | Pressurized water reactor | 400 | 125 | USA | Babcock & Wilcox | US pre-licensing | on-site |
MRX | Pressurized water reactor | 100 | Japan | JAERI | abandoned | on-site | |
MSBWR | Boiling water reactor | ? | 50 | USA | GE / Purdue | abandoned | on-site |
MSR-FUJI | Molten salt reactor | 450 | 200 | Japan | ITHMSI | concept | continuous |
NP-300 | Pressurized water reactor | ? | 300 | France | Areva NP | abandoned | on-site |
Package Reactor | Light water reactor | 25 | ? | Japan | Hitachi / Mitsubishi | abandoned | on-site |
PBMR | High temperature gas-cooled reactor | 400 | 165 | South Africa | PBMR (ESKOM) | abandoned after starting US pre-licensing | on-site |
PEACER-300 | Lead-cooled fast reactor | 850 | 300 | Korea | Seoul Nat. U. | concept | on-site |
PFPWR-50 | Light water reactor | 50 | n/a | Japan | Hokkaido U. | concept | factory |
Power Module | Lead-bismuth-cooled fast reactor | 75 | 25 | USA | Hyperion Power Generation | US pre-licensing | factory |
PRISM | Lead-cooled fast reactor | 840 | 311 | USA | GE-Hitachi | US pre-licensing | on-site |
PSRD | Light water reactor | 100 | 31 | Japan | JAEA | concept | factory |
PWBWR | Lead-cooled fast reactor | 450 | 150 | Japan | RLNR-TIT | abandoned | on-site |
RAPID | Lithium-cooled fast reactor | 10 | 1.2 | Japan | CRIEPI | abandoned | factory |
RBEC-M | Lead-cooled fast reactor | 900 | 340 | Russia | RRC Kurchatov | abandoned | on-site |
RMWR | Boiling water reactor | 955 | 330 | Japan | Hitachi / JAERI | concept | on-site |
RUTA-70 | Light water reactor | 70 | n/a | Russia | NIKIET / IPPE | concept | on-site |
SMART | Pressurized water reactor | 330 | 90 | Korea | KAERI | Korea license | on-site |
SPINNOR | Lead-cooled fast reactor | 55 | 20 | Indonesia | ITB | concept | factory |
SSTAR | Lead-cooled fast reactor | 45 | 20 | USA | ANL / LLNL / LANL / INL / UCB | concept | factory |
STAR-H2 | Lead-cooled fast reactor | 400 | n/a | USA | ANL / OrSU / TA&M / OhSU | concept | factory |
STAR-LM | Lead-bismuth-cooled fast reactor | 400 | 178 | USA | ANL | concept | factory |
SVBR-75/100 | Lead-cooled fast reactor | 280 | 100 | Russia | IPPE / OKB Gidropress | concept | factory |
TPS | Light water reactor | 64 | 16 | USA | General Atomics | abandoned | on-site |
UNITHERM | Pressurized water reactor | 20 | 7 | Russia | NIKIET | concept | factory |
V-SPINNOR | Lead-cooled fast reactor | 17 | 6 | Indonesia | ITB | concept | factory |
VBER-300 | Pressurized water reactor | 850 | 295 | Russia | OKBM | concept | on-site |
VK-300 | Boiling water reactor | 750 | 250 | Russia | NIKIET | concept | on-site |
VKR-MT | Light water reactor | 890 | 300 | Russia | RRC Kurchatov | abandoned | factory |
Note: I'll probably edit this post frequently as I find more information.
Added 2011/06/08: The Union of Concerned Scientists has provided some testimony to Congress on SMRs.
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