Am. Bhagwat et al., RADIOLOGICAL SAFETY EXPERIENCE IN THE FABRICATION OF ALLOY PLATE FUELS BEARING U-233 PU/, Nuclear technology, 103(2), 1993, pp. 246-256
The first incidence of U-233-bearing fuel fabrication in India was the
production of aluminum-clad Al-U-233 alloy fuel for the Kamini resear
ch reactor. The reactor physics experiments for this fuel are now bein
g carried out in the Purnima III critical assembly, where Al-Pu alloy
plate fuels will also be used. Both types of fuels were fabricated in
the radiometallurgy laboratories of Bhabha Atomic Research Centre. The
hazard potential of each step, evaluated from the site-specific radio
logical field data, is summarized The parameters analyzed for this pur
pose include external and internal radiation hazards, contamination ha
zards, age of fuel, material (i.e., time after separation), and experi
mental thermoluminescent detector exposure data. Gamma spectrometric d
ata of the finished fuel plates were also analyzed for their utility i
n checking the material inventory. The collective dose equivalent from
the fabrication operations for 12 subassemblies (9 bearing 233 U and
3 bearing plutonium) was 67 mSv, arising from external exposures only.
The internal exposure was nil. Fabrication of fuel plates constituted
>60% of the total exposure. Fabrication of fuel subassemblies and qua
lity control inspection at all the stages accounted for the remaining
radiation exposure. Handling of U-233/Pu-bearing fuels is likely to in
crease in the years ahead in India. In this context, analysis of radio
logical field data has yielded useful guidelines for future work.