News accounts dealing with how much uranium Iran might possess of a composition close to what is needed for making a nuclear bomb―and, relatedly, how quickly Iran might be able to produce what it would need for one such bomb or more―can be confusing to those not deeply familiar with the relevant physics and technology. This essay seeks to clarify the matter for those willing to put up with a bit of arithmetic.
On Uranium Fission
Natural uranium—the form of the element found in nature―is composed of two isotopes: U238 (making up 99.3 percent of natural uranium) and U235 (0.7 percent). Because the two isotopes have the same number of protons and, thus, the same number of electrons surrounding their nuclei, their chemical behavior is essentially identical. But the difference in their numbers of neutrons―143 for U235 and 146 for U238―means not only that the two isotopes differ slightly in mass but also that they differ significantly in how they behave in nuclear reactions.
Specifically, the U235 nucleus is quite unstable in terms of how readily it fissions when struck by a free neutron, breaking into two large fragments of intermediate atomic weight (“fission products”) and releasing two or three more neutrons and large quantities of nuclear energy. The result is that, in suitable circumstances, U235 can sustain a nuclear chain reaction. (A chain reaction requires that an average of at least one of the neutrons released from the fission of one U235 atom induces another fission in a second U235 atom, and so on.)
If the concentration of U235 atoms is high enough, and if the accompanying concentrations of U238 and other elements that absorb neutrons without fissioning are not too high, U235 can sustain a chain reaction. It has this capability, moreover, whether the neutrons impinging on it are “slow” (with velocity close to that corresponding to the temperature of the environment where the reactions are taking place) or “fast” (with velocity closer to the much higher speed the neutrons carried upon emission).
By contrast, U238 has negligible probability of fissioning when struck by a slow neutron; and, while it may fission when struck by a fast neutron, the likelihood that an incident fast neutron will be captured without inducing fission is too high for U238 to sustain a chain reaction on its own, even in a fast-neutron environment.
Despite its inability to sustain a nuclear chain reaction by itself, U238 is not useless in nuclear-reactor and nuclear-weapon applications. U238 fission by fast neutrons adds something to the total energy produced in both nuclear reactors and nuclear bombs. And non-fission absorption of slow or fast neutrons by U238 produces unstable U239, which, in a reactor, transforms itself in two steps, over hours and days, into useful plutonium-239 (Pu239).
Once created, some of the Pu239 (and other plutonium isotopes produced by additional neutron absorption) undergo fission in the reactor, thus contributing to its nuclear-energy production. Those plutonium isotopes that have not yet undergone fission remain in the “spent” nuclear fuel after it is removed from the reactor. This plutonium can be separated in a fuel-reprocessing plant from the fission products and unreacted uranium in the spent-fuel, for subsequent use either in nuclear reactors or nuclear weapons.
On Uranium Enrichment for Nuclear Reactors and Bombs
Nuclear reactors based primarily on the U235 chain reaction can use either slow or fast neutrons, depending on reactor design. Reactor types relying on slow neutrons (also termed “thermal” neutrons, with reactors relying on them likewise called “thermal” reactors), require incorporation of materials called “moderators” to slow down the fast neutrons emitted by fission. The best moderators are graphite and “heavy water” (deuterium oxide, D2O), although ordinary water (“light water," H2O) suffices in that role in the Light Water Reactors (LWRs) that dominate global nuclear-electricity generation today. Fast-neutron nuclear reactors and nuclear weapons (the latter depending entirely on fast neutrons) lack moderators.
Achieving a chain reaction in LWRs and most other reactor types requires the U235 fraction be increased beyond its 0.7% level in natural uranium, by means of “uranium enrichment.” The U235 concentration deemed optimal in today’s LWRs is around 5%, but some advanced reactor designs work best with U235 at a concentration approaching 20%. That happens to be the concentration at which making a nuclear explosive from uranium becomes theoretically possible (although hardly practical, because of the very large mass of 20%-enriched uranium required for an explosive chain reaction). To minimize the mass of enriched uranium needed for a fission bomb or warhead, a U235 concentration above 90% is preferred, with 93% often cited as ideal.
Practical approaches for uranium enrichment, whether for energy or weapon purposes, depend on selective removal of U238 by exploiting the very small mass difference between it and U235. Currently, the most cost-effective technology for achieving this separation consists of arrays of hundreds to thousands of very specialized, chained centrifuges, each one operating on gaseous uranium hexafluoride (UF6). The rotors in the centrifuges spin at 50,000 rpm or more, driving the slightly heavier U238F6 molecules more strongly toward the cylinder’s circumference, leaving the UF6 near the axis slightly enriched in U235.
Uranium gas centrifuges operate continuously rather than in the batch mode typical of centrifuges for other purposes, with the slightly enriched UF6, extracted near the centrifuge axis and passed forward to the next centrifuge in the chain, while the slightly depleted UF6 is extracted near the circumference and passed backward to the previous centrifuge. That the mass difference between the two uranium isotopes is so small means the degree of enrichment that can be accomplished in a single centrifuge is also small, which is why chaining multiple centrifuges together is necessary to achieve a useful degree of enrichment in the final product.
The magnitude of an enrichment task can be measured by:
- the amount of unenriched or low-enriched uranium feed required to obtain the desired quantity of uranium product at a specified higher level of enrichment;
- the amount of “separative work” that the laws of thermodynamics require for the degree of sorting of the heavy and light nuclei needed to provide the specified concentration of U235 in the desired quantity of product;
- the number of centrifuges to produce the desired quantity in a specified time; and
- the amount of electrical energy needed to power the production process.
We consider these factors in order, providing example cases where enrichment, starting from natural uranium, is to 5% U235 for use in a contemporary light-water power reactor (LWR) or to 93% U235 for use in a fission explosive.
The amount of uranium input required can be calculated from simple “balance” equations, requiring only the total quantities of U235 and U238 isotopes are conserved in the process. The answer depends only on the U235 concentration in the feed, the U235 concentration desired in the enriched product, and the residual concentration of U235 in the depleted-uranium waste stream (called the “tails”); it does not depend on the technological process used for enrichment, assuming only that material losses in the process are negligible. With that assumption, the balance equations reveal that the mass of the required uranium feed is larger than the mass of enriched product by the ratio, F/P = (xp – xt)/(xf – xt), where xp is the desired enrichment level of the product, xf is the enrichment level of the feed, and xt is that of the tails.