Engineering:Sodium-cooled fast reactor
A sodium-cooled fast reactor is a fast neutron reactor cooled by liquid sodium.
The acronym SFR particularly refers to two Generation IV reactor proposals, one based on existing liquid metal cooled reactor (LMFR) technology using mixed oxide fuel (MOX), the other based on the metal-fueled integral fast reactor.
Several sodium-cooled fast reactors have been built, some still in operation, and others are in planning or under construction.
The nuclear fuel cycle employs a full actinide recycle with two major options: One is an intermediate-size (150–600 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel, supported by a fuel cycle based on pyrometallurgical reprocessing in facilities integrated with the reactor. The second is a medium to large (500–1,500 MWe) sodium-cooled reactor with mixed uranium-plutonium oxide fuel, supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors. The outlet temperature is approximately 510–550 degrees Celsius for both.
Sodium as a coolant
Liquid metallic sodium may be used as the sole coolant, carrying heat from the core. Sodium has only one stable isotope, sodium-23. Sodium-23 is a very weak absorber of neutrons. When it does absorb a neutron it produces sodium-24, which has a half-life of 15 hours and decays to magnesium-24, a stable isotope.
The primary advantage of liquid metal coolants, such as liquid sodium, is that metal atoms are weak neutron moderators. Water is a much stronger neutron moderator because the hydrogen atoms found in water are much lighter than metal atoms, and therefore neutrons lose more energy in collisions with hydrogen atoms. This makes it difficult to use water as a coolant for a fast reactor because the water tends to slow (moderate) the fast neutrons into thermal neutrons (though concepts for reduced moderation water reactors exist). Another advantage of liquid sodium coolant is that sodium melts at 371K and boils / vaporizes at 1156K, a total temperature range of 785K between solid / frozen and gas / vapor states. By comparison, the liquid temperature range of water (between ice and gas) is just 100K at normal, sea-level atmospheric pressure conditions. Despite sodium's low specific heat (as compared to water), this enables the absorption of significant heat in the liquid phase, even allowing for safety margins. Moreover, the high thermal conductivity of sodium effectively creates a reservoir of heat capacity which provides thermal inertia against overheating. Sodium also need not be pressurized since its boiling point is much higher than the reactor's operating temperature, and sodium does not corrode steel reactor parts. The high temperatures reached by the coolant (the Phénix reactor outlet temperature was 560 C) permit a higher thermodynamic efficiency than in water cooled reactors. The molten sodium, being electrically conductive, can also be pumped by electromagnetic pumps.
A disadvantage of sodium is its chemical reactivity, which requires special precautions to prevent and suppress fires. If sodium comes into contact with water it reacts to produce sodium hydroxide and hydrogen, and the hydrogen burns when in contact with air. This was the case at the Monju Nuclear Power Plant in a 1995 accident. In addition, neutrons cause it to become radioactive; however, activated sodium has a half-life of only 15 hours.
Another problem is sodium leaks, regarded by critic of fast reactors M.V. Ramana as "pretty much impossible to prevent".
Actinides and fission products by half-life
|Actinides by decay chain||Half-life
|Fission products of 235U by yield<ref>Specifically from thermal neutron fission of U-235, e.g. in a typical nuclear reactor.</ref>|
No fission products
|226Ra№||247Bk||1.3 k – 1.6 k|
|240Pu||229Th||246Cmƒ||243Amƒ||4.7 k – 7.4 k|
|245Cmƒ||250Cm||8.3 k – 8.5 k|
|230Th№||231Pa№||32 k – 76 k|
|236Npƒ||233Uƒ||234U№||150 k – 250 k||‡||99Tc₡||126Sn|
|248Cm||242Pu||327 k – 375 k||79Se₡|
|237Npƒ||2.1 M – 6.5 M||135Cs₡||107Pd|
|236U||247Cmƒ||15 M – 24 M||129I₡|
... nor beyond 15.7 M years
|232Th№||238U№||235Uƒ№||0.7 G – 14.1 G|
Legend for superscript symbols
The operating temperature should not exceed the melting temperature of the fuel. Fuel-to-cladding chemical interaction (FCCI) has to be designed against. FCCI is eutectic melting between the fuel and the cladding; uranium, plutonium, and lanthanum (a fission product) inter-diffuse with the iron of the cladding. The alloy that forms has a low eutectic melting temperature. FCCI causes the cladding to reduce in strength and could eventually rupture. The amount of transuranic transmutation is limited by the production of plutonium from uranium. A design work-around has been proposed to have an inert matrix. Magnesium oxide has been proposed as the inert matrix. Magnesium oxide has an entire order of magnitude smaller probability of interacting with neutrons (thermal and fast) than elements like iron.
The SFR is designed for management of high-level wastes and, in particular, management of plutonium and other actinides. Important safety features of the system include a long thermal response time, a large margin to coolant boiling, a primary system that operates near atmospheric pressure, and intermediate sodium system between the radioactive sodium in the primary system and the water and steam in the power plant. With innovations to reduce capital cost, such as making a modular design, removing a primary loop, integrating the pump and intermediate heat exchanger, or simply find better materials for construction, the SFR can be a viable technology for electricity generation.
The SFR's fast spectrum also makes it possible to use available fissile and fertile materials (including depleted uranium) considerably more efficiently than thermal spectrum reactors with once-through fuel cycles.
Sodium-cooled reactors have included:
|Model||Country||Thermal power (MW)||Electric power (MW)||Year of commission||Year of decommission||Notes|
|BN-350||Soviet Union||135||1973||1999||Was used to power a water de-salination plant.|
|BN-600||Soviet Union||1470||600||1980||Operational||Together with the BN-800, one of only two commercial fast reactors in the world.|
|BN-800||Soviet Union/ Russia||2100||880||2015||Operational||Together with the BN-600, one of only two commercial fast reactors in the world.|
|BN-1200||Russia||2900||1220||2036||Not yet constructed||Is in the developement. Will be followed by BN-1200M as a model for export.|
|CRBRP||United States||1000||350||Never built||Never built|
|Fermi 1||United States||200||69||1963||1975|
|Sodium Reactor Experiment||United States||20||65||1957||1964|
|S1G||United States||United States naval reactors|
|S2G||United States||United States naval reactors|
|PFBR||India||500||2020||Under construction||Under construction|
|Monju||Japan||714||280||1995/2010||Operational/1995||Suspended for 15 years. Reactivated in 2010|
|Superphénix||France||3000||1242||1986||1997||Largest SFR ever built. Suffered a terrorist attack during its construction.|
Most of these were experimental plants, which are no longer operational. On November 30, 2019, CTV reported that the 3 Canadian provinces of New Brunswick, Ontario and Saskatchewan are planning an announcement about an interprovincial plan to cooperate on small sodium fast modular nuclear reactors from New Brunswick-based ARC Nuclear Canada.
- Fast Flux Test Facility, United States, a sodium-cooled fast neutron reactor
- Fast breeder reactor
- Fast neutron reactor
- Integral fast reactor
- Lead-cooled fast reactor
- Gas-cooled fast reactor
- Generation IV reactor
- Fanning, Thomas H. (May 3, 2007). "Sodium as a Fast Reactor Coolant" (PDF). Nuclear Engineering Division, U.S. Nuclear Regulatory Commission, U.S. Department of Energy. Archived from the original on January 13, 2013. https://web.archive.org/web/20130113134710/http://www.ne.doe.gov/pdfFiles/SodiumCoolant_NRCpresentation.pdf.
- Bonin, Bernhard; Klein, Etienne (2012). Le nucléaire expliqué par des physiciens.
- Martin, Richard (2015-10-21). "TerraPower Quietly Explores New Nuclear Reactor Strategy". Technology Review. http://www.technologyreview.com/news/542686/terrapower-quietly-explores-new-nuclear-reactor-strategy/. Retrieved 2016-12-23. ""The problem with sodium is that it has been pretty much impossible to prevent leaks," says nuclear physicist M.V. Ramana, a lecturer at Princeton University’s Program on Science and Global Security and the Nuclear Futures Laboratory."
- Plus radium (element 88). While actually a sub-actinide, it immediately precedes actinium (89) and follows a three-element gap of instability after polonium (84) where no nuclides have half-lives of at least four years (the longest-lived nuclide in the gap is radon-222 with a half life of less than four days). Radium's longest lived isotope, at 1,600 years, thus merits the element's inclusion here.
- Milsted, J.; Friedman, A. M.; Stevens, C. M. (1965). "The alpha half-life of berkelium-247; a new long-lived isomer of berkelium-248". Nuclear Physics 71 (2): 299. doi:10.1016/0029-5582(65)90719-4. Bibcode: 1965NucPh..71..299M.
"The isotopic analyses disclosed a species of mass 248 in constant abundance in three samples analysed over a period of about 10 months. This was ascribed to an isomer of Bk248 with a half-life greater than 9 y. No growth of Cf248 was detected, and a lower limit for the β− half-life can be set at about 104 y. No alpha activity attributable to the new isomer has been detected; the alpha half-life is probably greater than 300 y."
- This is the heaviest nuclide with a half-life of at least four years before the "Sea of Instability".
- Excluding those "classically stable" nuclides with half-lives significantly in excess of 232Th; e.g., while 113mCd has a half-life of only fourteen years, that of 113Cd is nearly eight quadrillion years.
- "Neutronic Assessment of Transmutation Target Compositions in Heterogeneous Sodium Fast Reactor Geometries" (PDF). Idaho National Laboratory, U.S. Department of Energy. February 2008. Archived from the original on 2012-02-12. https://web.archive.org/web/20120212184011/http://www.inl.gov/technicalpublications/Documents/3901052.pdf.
- "The Sodium-Cooled Fast Reactor (SFR)" (PDF). Argonne National Laboratory, US Department of Energy. October 2002. http://www.ipd.anl.gov/anlpubs/2002/10/44547.pdf.
- Idaho National Laboratory Sodium-cooled Fast Reactor Fact Sheet
- Generation IV International Forum SFR website
- INL SFR workshop summary
- Richardson JH (November 17, 2009). "Meet the Man Who Could End Global Warming". Esquire. Archived from the original on November 21, 2009. https://web.archive.org/web/20091121055813/http://www.esquire.com/features/best-and-brightest-2009/nuclear-waste-disposal-1209-2. "... Eric Loewen is the evangelist of the sodium fast reactor, which burns nuclear waste, emits no CO
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