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

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3.3. EVALUATION OF MASS DISTRIBUTION DATA<br />

FROM 252 Cf SPONTANEOUS FISSION<br />

The mass distribution <strong>of</strong> 252 Cf spontaneous<br />

fission was evaluated on <strong>the</strong> basis <strong>of</strong> seven sets <strong>of</strong><br />

available experimental data. The measured data<br />

were modified on <strong>the</strong> basis <strong>of</strong> <strong>the</strong> authors’ adopted<br />

standards and g ray intensities by using our newly<br />

evaluated values, and <strong>the</strong> originally assigned uncertainties<br />

were adjusted. The evaluated experimental<br />

data were fitted with a spline function. In addition, a<br />

symmetric spline function fit <strong>of</strong> all experimental<br />

data was per<strong>for</strong>med by symmetric reflection <strong>of</strong> <strong>the</strong><br />

light mass peak into <strong>the</strong> heavy mass peak. These two<br />

sets <strong>of</strong> fitted data are recommended as reference <strong>for</strong><br />

<strong>the</strong> mass distribution <strong>of</strong> 252 Cf spontaneous fission.<br />

Uncertainties in <strong>the</strong> recommended data were<br />

considerably reduced compared to <strong>the</strong> measured<br />

values. The light and heavy mass peaks are not<br />

completely symmetric. Fine structure has been<br />

observed in experimental mass distributions around<br />

A = 109–112 and A = 136–139, which is probably<br />

real, but could not be reproduced in <strong>the</strong> evaluation<br />

due to inconsistencies in <strong>the</strong> measurement results.<br />

These phenomena and <strong>the</strong>ir physical background<br />

should be investigated fur<strong>the</strong>r.<br />

3.3.1. Introduction<br />

The average number and spectrum <strong>of</strong><br />

neutrons from <strong>the</strong> spontaneous fission <strong>of</strong> 252 Cf are<br />

used as standards in neutron data measurements<br />

and evaluations, and internationally recommended<br />

data have been published [3.3.1]. The same is true<br />

<strong>for</strong> <strong>the</strong> mass distribution data <strong>of</strong> 252 Cf spontaneous<br />

fission that are used as reference in fission yield<br />

data measurements and evaluations. As requested<br />

by <strong>the</strong> CRP, <strong>the</strong>se yield data were evaluated and<br />

represent a continuation <strong>of</strong> our reference fission<br />

yield data evaluation following <strong>the</strong> completion <strong>of</strong><br />

235 U and 238 U yield evaluations in 2001 [3.3.2].<br />

All data were evaluated on <strong>the</strong> basis <strong>of</strong> <strong>the</strong><br />

available experimental data, and <strong>the</strong> results are<br />

summarized in this section. The collection,<br />

evaluation and processing <strong>of</strong> <strong>the</strong> experimental data<br />

are described in Sections 3.3.2 and 3.3.3, <strong>the</strong> results<br />

are given in Section 3.3.4 toge<strong>the</strong>r with a discussion<br />

Liu Tingjin<br />

China Institute <strong>of</strong> Atomic Energy, China<br />

<strong>of</strong> some problems encountered, and <strong>the</strong> conclusions<br />

are given in Section 3.3.5.<br />

3.3.2. Collection and evaluation<br />

<strong>of</strong> experimental data<br />

As part <strong>of</strong> our evaluation ef<strong>for</strong>t to derive 252 Cf<br />

mass distributions, we collected experimental chain<br />

yield, CU yield and fragment mass yield data, which<br />

we retrieved from <strong>the</strong> EXFOR data library or<br />

collected as publications found in CINDA and<br />

elsewhere. Since our goal is to evaluate <strong>the</strong> mass<br />

distribution, we primarily collected and used<br />

experiments in which chain yields and fragment<br />

mass yields were measured <strong>for</strong> a wider range <strong>of</strong><br />

product nuclides. However, chain yields <strong>for</strong> low<br />

yield product nuclides and CU yields were also<br />

collected and reviewed in case <strong>the</strong>y were needed<br />

(due to <strong>the</strong> lack <strong>of</strong> primary data), or to see whe<strong>the</strong>r<br />

some supplementary in<strong>for</strong>mation and data could be<br />

obtained <strong>for</strong> <strong>the</strong> evaluation. As a result <strong>of</strong> this<br />

selection, <strong>the</strong> following eight sets <strong>of</strong> data were<br />

considered <strong>for</strong> <strong>the</strong> evaluation.<br />

3.3.2.1. Schmitt et al. [3.3.3]<br />

The kinetic energy and flight time <strong>of</strong> fission<br />

fragments were measured by means <strong>of</strong> surface<br />

barrier semiconductor detectors. The linear signal<br />

<strong>of</strong> <strong>the</strong> detector was used to determine <strong>the</strong> fragment<br />

energy E, and <strong>the</strong> flight time was determined by<br />

means <strong>of</strong> a ‘time pick<strong>of</strong>f’ scheme in which<br />

trans<strong>for</strong>mer coupling was employed. The energy<br />

and mass distributions were deduced from <strong>the</strong>se<br />

energy and time <strong>of</strong> flight spectra, in which <strong>the</strong><br />

energy was calibrated with 79,81 Br and 127 I ions<br />

produced from <strong>the</strong> ORNL tandem van de Graaff<br />

accelerator and <strong>the</strong> mass resolution was 1.8 amu <strong>for</strong><br />

79 Br (2.25%) and 3.2 amu <strong>for</strong> 127 I (2.5%). The postneutron<br />

emission mass distribution <strong>of</strong> <strong>the</strong> fission<br />

fragments was also given. The data were adjusted<br />

<strong>for</strong> mass resolution with <strong>the</strong> following <strong>for</strong>mula:<br />

s d NC( A)<br />

NC( A) = NU( A)<br />

- ¥<br />

dA<br />

2<br />

2 2<br />

2<br />

(3.3.1)<br />

87

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