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Table 1. Core performance of MA and I transmutation ADS<br />

with proton beam power of 30 MW (1.5 GeV and 20 mA)<br />

Core<br />

Thermal power<br />

K eff<br />

Core height/diameter (cm)<br />

Fuel compositions<br />

Initial heavy metal loading (kg)<br />

Transmutation of MA (kg/300 days) 250<br />

Blanket<br />

Thickness (cm)<br />

NaI/(NaI+ZrH) (%)<br />

Initial iodine loading (kg)<br />

Transmutation of I (kg/300 days)<br />

800 MW<br />

0.95<br />

100/115<br />

60%MA + 40%Pu<br />

4 000<br />

Axial<br />

25<br />

50<br />

765<br />

35<br />

Radial<br />

16<br />

40<br />

839<br />

22<br />

An analysis of beam trip transient was made for the accelerator-transmutation plant [5]. Transient<br />

of the primary coolant temperature, the water/stream temperature, the water/steam pressure, the<br />

turbine flow rate were required at a time of 380 s after beam trip to prevent from overcooling. The<br />

maximum temperature swing was 185°C in lead-bismuth, and 82°C for in water/steam for the case<br />

when beam recovered at a time of 370 s. The temperature change during beam trip transient is shown<br />

in Figure 2.<br />

3. Scenario studies of ADS introduction in future fuel cycle<br />

The effect of ADS on MA transmutation: transmutation performance by ADS has been studied<br />

by assuming the existence of MA of 100 tons. As the MA transmuter, we selected the ADS system<br />

with 800 MW thermal power with a 1.5 GeV and 20 mA proton beam, and with the core having an<br />

effective neutron multiplication factor of 0.95. With the assumption of a load factor of 80%, the net<br />

MA transmutation rate becomes approximately 250 kg/y. The system inventories of MAs in ADS fuel<br />

cycle will be reduced from around 80 tons in 2050 to 20 tons in 2100, and will be minimised in 2150.<br />

MA of 100 tons , that is, will be transmuted during 120 years.<br />

Dependence of MA and iodine build-up on fuels, burn-up and cooling times: the amount of the<br />

MAs produced in LWRs with UO 2<br />

/ MOX fuels and an FBR with MOX fuel have been investigated<br />

for various conditions such as fuel compositions, burn-up and cooling time duration as shown in<br />

Table 2. For the UO 2<br />

-LWRs, MA build-up increases slightly with increasing burn-up. The MA buildup<br />

quantities for full MOX fuelled LWR are more than three times for the UO 2<br />

fuelled LWRs. In<br />

addition, MOX-FBR produces about two times MA comparative with UO 2<br />

-LWR.<br />

536

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