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RRFM 2009 Transactions - European Nuclear Society

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1.00E+06<br />

1.00E+05<br />

Volume activity (Bq/l)<br />

1.00E+04<br />

1.00E+03<br />

1.00E+02<br />

1.00E+01<br />

15.5.1996 15.5.1998 14.5.2000 14.5.2002 13.5.2004 13.5.2006 12.5.2008<br />

Date of sampling<br />

Figure 2 Time dependence of volume activity of 239 Np<br />

3. Neutron activation analysis of evaporated water samples<br />

0.5 l primary circuit water was evaporated on Al foil, and similarly demineralised water<br />

sample was prepared. Evaporated water samples were irradiated in the reactor core for 24 h.<br />

Then the induced activities were measured.<br />

Fission products activities for evaporated sample of primary circuit water were much higher<br />

then for demineralised water. Then source of fission products does not origin from<br />

demineralised water.<br />

The resulted mass concentrations for December 2006 are 0.25 μg/l for 235 U and 1.00 μg/l for<br />

235 U. Similar measurement was made in November 2008 and concentrations decreased (see<br />

Table 1).<br />

4. Data analysis<br />

Radionuclides in the water are produced by activation of stable nuclides and by fission of<br />

fissile nuclides, mainly 235 U [3]. Demineralized water used for primary circuit water includes<br />

small concentration of natural uranium. Fuel assemblies include uranium with enrichment of<br />

36 %. Also uranium from surface contamination of fuel cladding has that enrichment.<br />

Increased activities of fission products in 1996 were due to a damaged fuel assembly in the<br />

reactor core. That assembly was removed from the reactor core and since that time the<br />

activities of fission products in primary circuit water decreased until November 2006.<br />

In 2005 more detailed analysis of data was made [4]. From comparison of theoretical results<br />

and measured values of volume activities of fission products and 239 Np the enrichment of the<br />

irradiated uranium was estimated. The resulted 39 % enrichment has high uncertainty due<br />

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