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Table II.11 Reactor design parameters of actinide burner reactors<br />

L-ABR 1) P-ABR 2)<br />

Fuel concept pin-bundle coated-particle<br />

material<br />

(64NpAmCm-<br />

36U 3) ) 1.0 N 4) 1.0<br />

(65NpAmCm-<br />

35U 3) ) 1.0 N 4) 1.0<br />

MAs initial loading, kg 918 2870<br />

MAs/U 588/330 1 865/1 005<br />

Reactor power, MWth 180 1 200<br />

Coolant material Lead Helium<br />

Neutron flux, 10 15 n/cm 2·sec 3.1 6.6<br />

Core averaged mean neutron energy, keV 720 720<br />

Reactivity (% ∆k/k)<br />

Coolant-void reactivity/core -1.3 –<br />

Doppler reactivity/core (∆t=300°C) -0.01 -0.01<br />

Kinetic parameters<br />

β eff 2.6×10 -3 2.6×10 -3<br />

l P (sec) 1.3×10 -7 1.5×10 -7<br />

Cycle length, full-power days 550 300<br />

MA burn-up, %/cycle 11 13<br />

1) L-ABR: MA-nitride fuel with lead coolant burner reactor.<br />

2) P-ABR: MA-particle fuel burner reactor.<br />

3) 90% enriched uranium.<br />

4)<br />

15 N enriched.<br />

2.3.4.2 Accelerator-driven transmutation systems<br />

Accelerator-driven systems (ADS, frequently called hybrid systems) combine high-intensity<br />

proton accelerators with spallation targets and a subcritical core with or without blanket (see<br />

Figure II.16). The proton accelerator will be either a linear accelerator (linac) or a circular accelerator<br />

(cyclotron). The high-intensity continuous-wave (CW) proton beam with an energy around 1 GeV and a<br />

current of several tens mA are injected into a target of heavy metal. This results in spallation reaction<br />

that emits neutrons, which enter the subcritical core to induce further nuclear reactions. The subcritical<br />

core can, in principal, be operated with either a thermal or a fast neutron spectrum.<br />

ADSs have unique features to burn MAs and FPs, preferably in the double strata option. They<br />

operate in a subcritical mode and can more easily address safety issues associated with criticality than<br />

in critical systems. They also offer substantial flexibility in overall operation. ADSs can provide more<br />

excess neutrons compared to critical reactors. The excess neutrons may be utilised for transmutation,<br />

conversion, and breeding purposes. These features may be exploitable to prepare a safe and efficient<br />

mean of transmuting nuclear waste. Both homogenous and heterogeneous fuel recycling is possible.<br />

Various concepts of ADS have been proposed with different goals and approaches. Relevant<br />

R&D programmes are being pursued at CEA, JAERI, LANL, CERN, etc. In recent years, all the<br />

system concepts proposed by these groups have converged on a fast neutron spectrum because of its<br />

large neutronic advantage over the thermal one, and the reduced production of higher actinides.<br />

165

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