User:David MacQuigg/Sandbox/Integral Fast Reactor: Difference between revisions

From Citizendium
Jump to navigation Jump to search
(Replaced content with "content moved to main space")
Tag: Replaced
 
(One intermediate revision by the same user not shown)
Line 1: Line 1:
{{Subpages}}
content moved to main space
The '''Integral Fast Reactor''' (IFR) is Argonne Lab's best design,<ref name=IFR/> a metal-fueled, sodium-cooled, pool-type <ref name=pool/> [[Fast neutron reactor|Fast Neutron Reactor]], addressing all the issues raised in [[Nuclear_power_reconsidered]] (safety, waste management, weapons proliferation, and cost). "Integral" refers to the on-site reprocessing of the spent fuel.
{{Image|Rod with Metal Fuel.png|right|350px|Fig.1 Fuel rod with high burnup and inherent safety.<ref name=IFRfig6.1/>}}
{{Image|Sodium-Cooled Fast Reactor.png|right|350px|Fig.2 Pool-type reactors have enormous heat capacity, and molten sodium will expand when hot, allowing convection to cool the core if the pump ever fails.}}
{{Image|Oxide fuel (9% burnup).png|right|350px|Fig.3 Oxide fuel after 9% burnup.<ref name=OxideFuel/> Normal LWR burnup is limited to 5 or 6%.}}
{{Image|Metal fuel rod.png|right|350px|Fig.4 Metal fuel rod after 12% burnup.<ref name=MetalFuel/>}}
 
== Choice of Fuel and Coolant ==
The IFR has a unique design for its fuel rods that accommodates much higher burnup than in light water reactors (LWRs) and also provides inherent safety if temperatures increase. To contrast IFR metal fuel with LWR oxide fuel, LWR fuel is "strong fuel, weak cladding", and IFR fuel is "weak fuel, strong cladding".
 
In standard light water reactor (LWR) fuel rods, the lower thermal conductivity of oxide (UO2) results in higher fuel temperatures that increase fission gas swelling. To avoid fuel-clad mechanical interaction that can cause cladding failure, there is a gap between the fuel and cladding. The gap is filled with helium gas for thermal bonding. If burnup is too high, however, the swelling and/or the oxide fuel cracking from thermal stresses will cause mechanical contact and strain the cladding to failure. These problems have been addressed in LWR fuel designs, but maximum burnup is limited by these effects to typically 5-6% of the total energy in the fuel.
 
In metallic IFR fuel, the fuel thermal conductivity is much larger than it is for UO2, so the fuel temperature and consequent fission gas swelling are more moderate. Fission gas more readily escapes the fuel meat and accumulates in the plenum above the fuel without unduly increasing the fuel rod internal pressure. As in LWR fuel, there is a radial gap between fuel and cladding, but the gap is filled with liquid metal sodium and has much higher thermal conductivity. Because metal fuel is weaker than UO2, mechanical contact with the clad is less consequential. The IFR fuel rod is illustrated in Figure 1.
 
In oxide-fueled LWRs clad with zirconium alloy, two chemical effects are disadvantageous. First, as happened at Fukushima, if the cladding temperature becomes too high in the presence of water, the zirconium alloy (used because of its low neutron capture cross section) rapidly oxidizes, weakening the cladding and producing hydrogen gas. Second, in the event of a cladding breach, the oxide fuel meat reacts with water and corrodes. In the IFR, parasitic fast neutron capture in cladding is far lower than parasitic thermal neutron capture in LWR cladding, so steel cladding can be used without adversely impacting the neutron economy. Steel does not suffer the rapid oxidation or hydrogen generation at high temperature that zirconium alloys do. If there is a cladding breach, fission products entering the coolant are bound there rather than released.
 
The thermal expansion coefficient of metallic fuel provides a negative reactivity feedback. If the fuel temperature increases, the fuel and coolant both expand, increasing neutron leakage from the core and thereby reducing the neutron chain reaction naturally. In other words, the temperature and power reactivity feedback coefficients are negative -- the hallmark of a stable system.
 
== The Fuel Cycle ==
As in other fission reactors, the spent fuel is a mixture of uranium, transuranics, fission products, and fuel material diluents. In LWRs, recycling fuel material more than one time becomes impractical, but the IFR’s fast neutron spectrum makes repeated recycling entirely feasible. The IFR fuel cycle chemistry, pyroprocessing, is the "Goldilocks" chemistry -- good enough to recycle the materials into the reactor again, but not so selective as to make the recycled material attractive for diversion for a nuclear weapon. It uses electrochemical deposit of the recycle material on a cathode in a molten salt bath, rather like the re-deposit of lead on the electrode in a lead-acid battery.
 
The chemistry of the IFR fuel recycling process does not allow extraction of pure plutonium, and many of the radioactive rare earth fission products stay in the recycled fuel material. This makes the material unattractive from a nuclear weapons material diversion standpoint -- it is too radioactive, contains non-fissile uranium, and is processed either in a highly radioactive argon-gas-atmosphere hot cell or as fully formed highly radioactive fuel elements. Further chemical separation and probably isotopic enrichment would be required, a situation not different in kind from starting with unprocessed fuel. So the IFR adds little or nothing to proliferation risk.<ref name=ProlifRisk/>
 
The recycle system demonstrated at Argonne National Laboratory over the decades is a batch process that does not require hundreds or thousands of miles of piping containing concentrate nitric acid bearing radioactive material, so it is expected to be substantially cheaper than the aqueous reprocessing used outside of the United States<reference to Plentiful Energy here>. Recycle facilities could economically service a cluster of IFR reactors co-located at one site, as was the case with EBR-II at Argonne-West.
 
In countries not licensed for fuel processing, return of the spent fuel to a secure location could be handled as any other reactor with solid fuel rods. Rods are easy to count, and the number in transit at any one time can be small enough to avoid theft of a large quantity.
 
== Safety ==
The safety of the IFR design is ensured by several features:<br>
1) The metal fuel, a low melting point alloy of U-Pu-Zr, will melt if the rod ever gets too hot. The fuel then expands upward in the steel cladding, shutting down the fission reactions (see Figure 1). The IFR is "walk away safe".<br>
2) Many of the fission products bind chemically with sodium, reducing the risk of fission product release if there is fuel failure.<br>
3) Convection and a large thermal inertia in the large pool of molten sodium will easily handle the decay heat after a shut-down (see Figure 2).<br>fuel
4) The reactor vessel has no penetrations below the top of the pool, eliminating the possibility of sodium leakage.<br>
5) There is no high pressure or any water near the reactor vessel.<br>
6) The entire reactor vessel is not filled solid, to allow for thermal expansion and contraction during operation. The space above the sodium pool is filled with argon gas so that air never contacts the sodium.<br>
Full-scale reactor tests were conducted at Argonne National Laboratory (West) in Idaho (now Idaho National Laboratory), in which the primary coolant pump was stopped with the reactor running at full power. All safety systems were disabled, and the control rods were held fully withdrawn. These "unprotected loss-of-flow tests" simulate the
extreme scenario where all safety systems and operator actions have failed.
The chain reaction was terminated by core expansion, and the core was cooled by natural circulation, without fuel damage or radioactive leakage.<ref name=IFRtests/>
 
== Waste Management ==
Fuel rods have an advantage over molten salt fuels in that the fission products are contained in the rod. This means a smaller volume of radioactive spent fuel. Also rods are easy to identify and count, which may be advantageous in preventing diversion. A [https://citizendium.org/wiki/ThorCon_nuclear_reactor#/media/File:ThorCon_Fuel_Cycle.png typical 500 MWe MSR] produces 13 tonnes of spent nuclear fuel salt per year. A 500 MWe PWR (they are normally about 1000 MWe) would produce about 11 tonnes of heavy metal and fission product waste per year. A 500 MWe IFR would produce about 5 tonnes per year of heavy metal and fission product waste per year. Note: SNF can be reprocessed, and the final amount of HLW will depend on the details of that process.
 
== Weapons Proliferation ==
The chemistry of the IFR fuel process does not allow extraction of weapons-grade material at any point in the cycle.
Spent fuel is a mix of uranium, plutonium, and various actinides.
Processing would be necessary by some other unrelated process, a situation not different in kind from starting with unprocessed fuel.
So the IFR adds little or nothing to proliferation risk.<ref name=ProlifRisk/>
In countries not licensed for fuel processing, return of the spent fuel to a secure location could be handled as any other reactor with solid fuel rods. Rods are easy to count, and the number in transit at any one time can be small enough to avoid theft of a large quantity.
 
== Cost ==
*No enormous pressure vessel with 6-inch steel walls.
*No huge containment building with 6-foot thick, steel reinforced concrete walls.
 
== Notes and References ==
{{Reflist|refs=
<ref name=IFR>[http://www.thesciencecouncil.com/pdfs/PlentifulEnergy.pdf ''PLENTIFUL ENERGY The Story of the Integral Fast Reactor''], Charles Till and Yoon Il Chang, 2011.
</ref>
<ref name=pool>
The alternative "loop-type" is necessary in standard Pressurized Water Reactors. A low pressure coolant allows a larger "pool-type" reactor vessel capable of absorbing all the heat in an emergency shutdown. See [http://www.thesciencecouncil.com/pdfs/PlentifulEnergy.pdf Till & Chang, Section 5.4] ''The Reactor Configuration Choice''.
</ref>
<ref name=IFRfig6.1>''Schematic of the metal fuel rod.'' Fig.6.1 in [http://www.thesciencecouncil.com/pdfs/PlentifulEnergy.pdf Till & Chang, Chapter 6] ''IFR Fuel Characteristics''.
</ref>
<ref name=OxideFuel>''Oxide fuel (9% burnup)'' Fig.6.5 in [http://www.thesciencecouncil.com/pdfs/PlentifulEnergy.pdf Till & Chang, Chapter 6] ''IFR Fuel Characteristics''.</ref>
<ref name=MetalFuel>''Metal fuel (12% burnup)'' Fig.6.6 in [http://www.thesciencecouncil.com/pdfs/PlentifulEnergy.pdf Till & Chang, Chapter 6] ''IFR Fuel Characteristics''.</ref>
 
<ref name=IFRtests>''Experimental Confirmations of Limited Damage in the Most Severe Accidents'',[http://www.thesciencecouncil.com/pdfs/PlentifulEnergy.pdf Till & Chang, Section 7.10].
</ref>
<ref name=ProlifRisk>''Nonproliferation Aspects of the IFR,'' [http://www.thesciencecouncil.com/pdfs/PlentifulEnergy.pdf Till & Chang, Chapter 12].
</ref>
}}

Latest revision as of 11:09, 5 May 2023

content moved to main space

Retrieved from "https://citizendium.org/wiki/index.php?title=User:David_MacQuigg/Sandbox/Integral_Fast_Reactor&oldid=891166"