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Figure 3. Neutron spectra averaged over fuel<br />

pins in the reference core, in FA with B 4<br />

C, and<br />

in Fa with H 2<br />

Zr. Neutron cross-section<br />

in the reaction 209 Bi(n,γ) is also shown<br />

Figure 4. <strong>Energy</strong> distribution of plutonium<br />

burn-up in the reference core,<br />

in FA with B 4<br />

C, and in FA with HZr<br />

Table 5. <strong>Energy</strong> dependence of B Pu,<br />

plutonium burn-up rate (%) versus the neutron energy in the<br />

ADS EAP-80 in different cores containing: reference fuel elements,<br />

fuel elements with thin B 4<br />

C cladding, Fuel elements with H 2<br />

Zr matrix.<br />

Ei<br />

Here B Pu<br />

(E i-1,<br />

E i<br />

) = m<br />

∫ [ Σ 239 ( E) + Σ 239 ( E) − Σ 238<br />

( E)<br />

] Φ( E)<br />

dE.<br />

f C C<br />

Ei−1<br />

Neutron energy<br />

(MeV)<br />

<strong>Energy</strong> dependence of plutonium B Pu<br />

(E i-1,<br />

E i<br />

) burn-up,<br />

%<br />

(E i-1,<br />

E i<br />

) Reference core.<br />

Enrichment 23.2%<br />

Core with B 4<br />

C cladding.<br />

Enrichment 45.0%<br />

Core with ZrH 2<br />

matrix.<br />

Enrichment 20.0%<br />

0 – 10 -4 3.78% 0.284% 71.10%<br />

10 -4 – 10 -3 9.78% 0.73% 14.66%<br />

10 -3 – 10 -2 8.89% 4.06% 1.08%<br />

10 -2 – 10 -1 4.74% 19.47% 0.00%<br />

10 -1 – 1 54.81% 56.39% 6.87%<br />

1 – 10 18.0% 19.07% 6.29%<br />

B Pu<br />

, (kg/FPY) 13.7 25.2 24.8<br />

817

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