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Fission Product Yield Data for the Transmutation of Minor Actinide ...

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FIG. 2.2.1. Independent charge yields per 100 fissions<br />

determined from <strong>the</strong> X ray yield measurements <strong>for</strong><br />

238 U(n,f) involving four incident neutron energy bins<br />

(black dots): threshold-6 MeV, 11–20 MeV, 20–50 MeV,<br />

50 MeV and above. Average energies are labelled: 3 MeV,<br />

14 MeV, 30 MeV, 190 MeV, and <strong>the</strong> histograms correspond<br />

to calculations obtained at <strong>the</strong> average energies with Wahl<br />

systematics [2.2.7].<br />

2.2.3. Results<br />

2.2.3.1. Charge yields<br />

Coincidence between photon and fission<br />

fragment detection in <strong>the</strong> active target experiment<br />

permitted prompt K X ray measurements [2.2.3].<br />

Due to <strong>the</strong> large number <strong>of</strong> K X ray lines (five per<br />

element), <strong>the</strong> X ray energy spectrum is quite<br />

complex. Never<strong>the</strong>less, <strong>the</strong> energies and relative<br />

intensities <strong>of</strong> <strong>the</strong>se lines are known to a high<br />

precision [2.2.4]. Within <strong>the</strong> limits <strong>of</strong> <strong>the</strong> recorded<br />

statistics, <strong>the</strong> contributions <strong>of</strong> <strong>the</strong> different elements<br />

produced <strong>for</strong> different groups <strong>of</strong> incident neutron<br />

energy can be de-convolted by fitting <strong>the</strong> data with<br />

a parametric function <strong>of</strong> one free parameter per<br />

element. In <strong>the</strong> 1970s, Reisdorf and collaborators<br />

measured <strong>the</strong> X ray yields per fission fragment<br />

Y(Z) in spontaneous and low energy neutron<br />

induced fission [2.2.5]. Y(Z) would appear to<br />

depend only weakly on <strong>the</strong> nature <strong>of</strong> <strong>the</strong> fissioning<br />

system. By applying Reisdorf’s prescription to our<br />

X ray yields it is possible to extract an elemental<br />

distribution <strong>of</strong> <strong>the</strong> primary fission fragments, as<br />

shown in Fig. 2.2.1. The X ray data have been<br />

corrected <strong>for</strong> self-absorption and detection<br />

efficiency with point source calibrations and a<br />

Monte Carlo N Particle Transport Code (MCNP)<br />

simulation [2.2.6]. The preliminary results exhibit<br />

<strong>the</strong> expected increase in <strong>the</strong> probability <strong>for</strong><br />

symmetric fission as one goes towards high incident<br />

neutron energies. Moreover, <strong>the</strong>y agree quite well<br />

with <strong>the</strong> systematics from Wahl <strong>for</strong> 14 MeV<br />

neutrons [2.2.7], particularly at 14 MeV. At 50 MeV<br />

and above, <strong>the</strong> symmetric region gap fills up. These<br />

results agree with <strong>the</strong> mass distribution measurements<br />

<strong>of</strong> Zöller et al. [2.2.8] <strong>for</strong> <strong>the</strong> same system.<br />

2.2.3.2. Fragment excitation functions<br />

From <strong>the</strong> inclusive gamma ray measurements,<br />

more than one hundred post-neutron fission<br />

fragments were identified from Ge to Nd. Among<br />

<strong>the</strong>m <strong>the</strong> even–even nuclei are particularly interesting.<br />

Indeed, <strong>the</strong> 2 + to 0 + (G.S.) transition <strong>of</strong> <strong>the</strong><br />

ground state rotational band <strong>of</strong> an even–even<br />

fragment is usually fed at 100% in <strong>the</strong> de-excitation<br />

process [2.2.9]. Measuring <strong>the</strong> corresponding<br />

gamma ray intensities gives a measurement <strong>of</strong> <strong>the</strong><br />

fragment production <strong>for</strong> 23 bins <strong>of</strong> incident neutron<br />

energies. In some cases, because <strong>of</strong> pollution or<br />

conversion <strong>of</strong> <strong>the</strong> 2 + to 0 + (G.S.) transition, higher<br />

transitions in <strong>the</strong> G.S. band are used. In cases where<br />

no singles data are usable, coincidence data best<br />

describe <strong>the</strong> production cross-section, but with<br />

much lower statistics (only three bins <strong>of</strong> incident<br />

neutron energies). In this way <strong>the</strong> fragment<br />

production cross-section has been extracted <strong>for</strong><br />

about thirty even–even post-neutron emission<br />

fragments as a function <strong>of</strong> incident neutron energy.<br />

The fragment production excitation functions are<br />

extracted from Ref. [2.2.10] and shown in Figs 2.2.2–<br />

2.2.31 <strong>for</strong> 92 Sr to 150 Ce. Up to three experimental<br />

FIG. 2.2.2. 92 Sr: best experimental data from <strong>the</strong> cyan<br />

points divided by 1 × 1 (BR from adopted levels <strong>of</strong> <strong>the</strong><br />

evaluated nuclear structure data file (ENSDF)).<br />

17

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