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Year : 2010  |  Volume : 33  |  Issue : 4  |  Page : 183-184

Simulation study of (Th-U)O 2 fuel pin clad defect

Radiation Safety Systems Division, Bhabha Atomic Research Centre, Mumbai, India

Correspondence Address:
R K Gopalakrishnan
Radiation Safety Systems Division, Bhabha Atomic Research Centre, Mumbai
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Source of Support: None, Conflict of Interest: None

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Advanced Heavy Water Reactor (AHWR) is being developed in India with the aim of utilizing the vast reserve of thorium as fertile fuel and power production. The AHWR is based on (Th-U)O 2 and (Th-Pu)O 2 fuel and hence studies related to various aspects of reactor operation using thorium is required as a part of development and generation of data on thorium fuel cycle. In this experimental study, an attempt is made to simulate a fuel Clad failure with (Th- 233 U)O 2 fuel pellets. The pellets of 91% T.D. with 0.1w% 233 UO 2 were prepared by conventional dry powder metallurgy of cold compaction and were contained in a 0.3mm thick Al capsule. A pin hole 1.76 mm 2 dia. was drilled on clad to simulate small size clad defect. The pellets immersed in demineralised water were irradiated in a reactor for a known period. The isotopic activity analysis of radionuclides released in the water was done by γ-ray spectrometry. The release of Ac 228 in the water indicates the presence of thorium decay products such as Bi 212 , Tl 208 during fuel failures. This would warrant adequate shielding on the primary heat transport system piping in case of MOX fuelled reactors using thorium.

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