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COMPLETE DOCUMENT (1862 kb) - OECD Nuclear Energy Agency

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As a part of MA nuclear data evaluation, the analysis of a 237 Np sample irradiated in JOYO<br />

has been performed. Additional irradiation test of 237 Np, 241 Am, 243 Am and 244 Cm samples in JOYO was<br />

started in August, 1994.<br />

Measurements of keV-neutron capture cross-sections of RE nuclides ( 147 Sm, 148 Sm, 150 Sm,<br />

140 Ce, 141 Pr, 153 Eu, 143 Nd, 145 Nd) have been performed to evaluate the accuracy of the nuclear data<br />

libraries using the 3-MeV Pelletron accelerator of the Research Laboratory for <strong>Nuclear</strong> Reactors at the<br />

Tokyo Institute of Technology [152].<br />

2.3.6 Interaction between plutonium incineration and minor actinide production<br />

2.3.6.1 Present day PWRs<br />

If present day PWRs could be licensed to accept 100% MOX containing depleted U, the<br />

balance of Pu consumption would be around 60 to 70 kg/TWhe during successive recyclings, but with<br />

concomitant production of minor actinides arising from 8 to 20 kg/TWhe. However, for high burn-ups<br />

in the range of 50 GWd/tHM, the number of plutonium recyclings in MOX assemblies with depleted<br />

uranium support is liable to be limited to two or three due to the degradation of certain safety-related<br />

coefficients, and particularly of the coolant void reactivity coefficient, which tends to become positive<br />

locally when the plutonium content substantially exceeds 12%.<br />

2.3.6.2 Other alternatives<br />

Other alternatives have been investigated, based on the use of PWRs, but with design changes<br />

intended to limit the Pu content of the MOX assemblies, and hence to restore the safety and reliability of<br />

multi-recycling.<br />

High moderation reactors (HMRs)<br />

3.<br />

High moderation reactors (HMRs) have a moderation ratio (moderator volume/fuel volume) of<br />

Compared with a standard PWR (in which the ratio is 2), the enhanced moderation helps to<br />

lower the Pu content of the MOX loaded with each recycle (one-third in the first recycle) and to improve<br />

Pu consumption per TWhe.<br />

Thus the consumption of Pu would increase from about 70 kg/TWhe in the first recycle to<br />

nearly 110 kg/TWhe at equilibrium, but the production of minor actinides would rise from 10 kg/TWhe<br />

to nearly 34 kg/TWhe.<br />

The Pu content would be stabilised around 20%, which is relatively high, requiring further<br />

physical feasibility studies for this type of reactor.<br />

174

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