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Science & Global Security
The Technical Basis for Arms Control, Disarmament, and Nonproliferation Initiatives
Volume 16, 2008 - Issue 1-2
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Original Articles

Characteristics of the Gas Centrifuge for Uranium Enrichment and Their Relevance for Nuclear Weapon Proliferation

Pages 1-25 | Received 15 Apr 2008, Accepted 23 Jun 2008, Published online: 28 Oct 2008

Figures & data

Figure 1 Typical mass-velocity profile expected for a centrifuge.

Figure 1 Typical mass-velocity profile expected for a centrifuge.

Figure 2 Optimum withdrawal radii ratio as a function of peripheral velocity.

Figure 2 Optimum withdrawal radii ratio as a function of peripheral velocity.

Table 1 Estimated design characteristics of important centrifuge generations.

Table 2 Design and performance characteristics of hypothetical centrifuges. Equation (Equation6) determines the theoretical maximum performance δUDirac. The overall efficiency and the resulting effective separative performance δURaetz can be determined with Eq. (Equation10) once the radii ratio is selected. The optimum feed rate F✶ and the corresponding separation factor α β depend on the selected countercurrent-to-feed ratio k.

Figure 3 Separative performance of a P1-type machine as a function of the feed rate for fixed internal circulation (top). Values for the countercurrent rates L have been chosen such that δ U is maximized for 10 mg/s (P1-100) and for 4 mg/s (P1-040). These design points are used for an analysis of cascade-performance below. The respective separation factors are also shown (bottom). Results based on the analytical model by Rätz using Eq. (Equation10).

Figure 3 Separative performance of a P1-type machine as a function of the feed rate for fixed internal circulation (top). Values for the countercurrent rates L have been chosen such that δ U is maximized for 10 mg/s (P1-100) and for 4 mg/s (P1-040). These design points are used for an analysis of cascade-performance below. The respective separation factors are also shown (bottom). Results based on the analytical model by Rätz using Eq. (Equation10).

Figure 4 Enrichment level of product stream leaving a P1-type centrifuge (P1-100). At t = 0, the feed rate is gradually reduced from its reference value of 10 mg/s to 5 mg/s over a 30-min period. The separative performance drops slightly from its optimum value (2.5 SWU/yr) to about 2.3 SWU/yr, if the internal circulation is not adjusted. A new equilibrium is obtained within about one hour. In this simulation, the feed material is natural uranium, and the cut is 0.46.

Figure 4 Enrichment level of product stream leaving a P1-type centrifuge (P1-100). At t = 0, the feed rate is gradually reduced from its reference value of 10 mg/s to 5 mg/s over a 30-min period. The separative performance drops slightly from its optimum value (2.5 SWU/yr) to about 2.3 SWU/yr, if the internal circulation is not adjusted. A new equilibrium is obtained within about one hour. In this simulation, the feed material is natural uranium, and the cut is 0.46.

Figure 5 Possible arrangement of 164 machines in a 15-stage cascade.

Figure 5 Possible arrangement of 164 machines in a 15-stage cascade.

Table 3 Results of the simulations for the 164-machine cascade using P1-type centrifuges. The four different modes of operation are each characterized by a specific optimum machine feed rate F✶, which translates into corresponding external feed rates and product rates and ultimately determines the enrichment level of the product leaving the cascade. The separative performance for the cascade (SP-C) and for an average machine (SP-AM) are shown. Values for batch recycling assume 3.5% enriched feedstock, initially produced with P1-135, and are taken after 120 hours of operation.

Figure 6 Transient response of a 164-machine cascade using P1-type technology: Enrichment level of product in batch recycling mode, initiated at t = 0. Depending on the selected default feed rate, a new equilibrium is reached within 24–48 h.

Figure 6 Transient response of a 164-machine cascade using P1-type technology: Enrichment level of product in batch recycling mode, initiated at t = 0. Depending on the selected default feed rate, a new equilibrium is reached within 24–48 h.

Figure 7 Enrichment level of the product recovered from a 164-machine cascade of the second batch recyling step. The machines in this cascade are operated at a reduced flow rate (P1-044); feedstock is 16.3% preenriched material from a first batch recycling step, in which machines are operated at the standard flow rate (P1-135). In this simulation, the target enrichment level of 90% is reached after about 3.5 days.

Figure 7 Enrichment level of the product recovered from a 164-machine cascade of the second batch recyling step. The machines in this cascade are operated at a reduced flow rate (P1-044); feedstock is 16.3% preenriched material from a first batch recycling step, in which machines are operated at the standard flow rate (P1-135). In this simulation, the target enrichment level of 90% is reached after about 3.5 days.

Figure 8 Illustration of the cascade arrangement as proposed for the Libyan enrichment project. Note the asymmetric upstream and downstream connections. Mass values are normalized to one kilogram of product (weapon-grade uranium at 90% enrichment), which is produced in about 4.1 days with this setup, if based on P1-type technology.

Figure 8 Illustration of the cascade arrangement as proposed for the Libyan enrichment project. Note the asymmetric upstream and downstream connections. Mass values are normalized to one kilogram of product (weapon-grade uranium at 90% enrichment), which is produced in about 4.1 days with this setup, if based on P1-type technology.

Table 4 Feed materials required to produce 1 kg of weapon-grade uranium using cascade interconnection. The product enrichment levels for the sub-cascades are taken from the Libyan project as specified in the South African court documents. Product flows have been calculated here such that they match the required feed flow for the following cascade, while using not more than the assigned SWU/machine fraction. Accordingly, all HC-type cascades strip the tails down to natural uranium, which can be recycled back into the C1/C2 cascades. This strategy saves 31 kg of natural uranium and reduces the total demand to 280 kg per kilogram of weapon-grade uranium produced.

Table 5 Summary of the breakout scenario starting from natural uranium. Values for the normalized production rates are for 6000 machines with a total separative capacity of about 15,000 SWU/yr. Batch recycling is extremely resource-intensive compared to cascade interconnection.

Table 6 Summary of the breakout scenario using 3.5% preenriched feed. Values for the normalized production rates are for 2000 machines with a total separative capacity of about 5000 SWU/yr. For the specified strategies, effective production rates would be slightly higher for the less efficient batch recycling mode, which needs a much larger supply of preenriched LEU (90 versus 32 kg per kilogram of weapon-grade uranium produced).

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