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JAERI 1287 JNDC Nuclear Data Library of Fission Products Fir

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4 <strong>JNDC</strong> <strong>Nuclear</strong> <strong>Data</strong> <strong>Library</strong> <strong>of</strong> <strong>Fission</strong> <strong>Products</strong> <strong>JAERI</strong> <strong>1287</strong><br />

E, = sensible decay energy <strong>of</strong> nuclide i.<br />

Therefore, the following nuclear data are necessary on each fission-product nuclide to calculate<br />

the decay power <strong>of</strong> fission products by the summation method:<br />

(1) <strong>Fission</strong> yields (yt)<br />

(2) Decay schemes (/;-,)<br />

(3) Half-lives (T,,2=(ln 2)11)<br />

(4) Decay energies (E,)<br />

(5) Neutron reaction cross sections (ai,gk-i)<br />

(6) <strong>Fission</strong> energies.<br />

The sensible fission energy per unit fission in item (6) is necessary on each fissionable<br />

nuclide to calculate the fission rate from the operating power <strong>of</strong> a nuclear reactor. Different<br />

weights Ei become necessary in Eq. (2.1.2) to calculate the different characteristics <strong>of</strong> fission<br />

products. For example, the beta- and gamma-decay energies <strong>of</strong> each nuclide are necessary as<br />

the weight in Eq. (2.1.2) to calculate the beta and gamma decay powers <strong>of</strong> fission products,<br />

respectively. Beta- and gamma-ray spectral data <strong>of</strong> each nuclide are used to calculate the<br />

beta- and gamma-ray spectra <strong>of</strong> fission products. The Q-value <strong>of</strong> each nuclide for beta decay<br />

or electron capture decay becomes necessary to calculate the total decay power <strong>of</strong> fission<br />

products including the antineutrino energy. Q-value is also indispensable in estimating the<br />

unknown decay data as will be shown in Sec. 2.3.<br />

2.2 Decay <strong>Data</strong><br />

The first task <strong>of</strong> our working group was to compile the decay data. When the compilation<br />

work was started out, the 7th edition <strong>of</strong> Table <strong>of</strong> Isotopes (TOI) and Evaluated <strong>Nuclear</strong><br />

Structure <strong>Data</strong> File (ENSDF) had not been available yet. Therefore, we devoted ourselves to<br />

collect the experimental information from various publications, and to put the data into our<br />

own file named as NDFILE 27 \ This work was continued until TOI and ENSDF became<br />

available.<br />

Most <strong>of</strong> the adopted experimental data on the decay have been taken mainly from<br />

Evaluated <strong>Nuclear</strong> Structure <strong>Data</strong> File (ENSDF), <strong>Nuclear</strong> <strong>Data</strong> Sheets and the 7th edition <strong>of</strong><br />

Table <strong>of</strong> Isotopes. Some <strong>of</strong> them not yet compiled in these issues were taken from the journals<br />

published up to early 1980. The accumulated experimental decay data have been processed<br />

by using a computer code PROFP 28) . Furthermore the present library contains the nuclides<br />

with no information on the decay data or lack <strong>of</strong> some items <strong>of</strong> decay data; most <strong>of</strong> them<br />

are short-lived nuclides or short-lived isomers which have been investigated mainly with the<br />

on-line mass separators. For these nuclides some <strong>of</strong> items such as the mean beta- and gammaray<br />

energies, the half-lives and so on have been estimated theoretically (see section 2.3).<br />

The experimental data on the emission probability <strong>of</strong> delayed neutron have been adopted<br />

for 71 precursors compiled by Rudstam in 1977 29 ^. For 23 precursors <strong>of</strong> them which were<br />

identified experimentally but whose emission probabilities were not determined, their neutron<br />

emission probabilities have been estimated with the help <strong>of</strong> the systematics. Many new experimental<br />

results for many precursors have been reported since 1977, and these were reviewed<br />

by Rudstam in 1979 30) . However, the hard time-schedule <strong>of</strong> the compilation prevented the<br />

present library from containing the revised delayed-neutron data reviewed by Rudstam 30 ).<br />

A preliminary calculation based on the revised delayed neutron data shows that the cumulative<br />

yields for some nuclides are affected a little bit, but that the result <strong>of</strong> the summation calculation<br />

is almost unchanged because <strong>of</strong> their small fission yields. The delayed neutron data will<br />

be revised in the 2nd version <strong>of</strong> the <strong>JNDC</strong> FP <strong>Nuclear</strong> <strong>Data</strong> <strong>Library</strong>.

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