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Title: Shield assessment of the radioactive waste storage facility
Authors: Bhargava, Pradeep
Sharma, V K
Keywords: Reactor;Radiation;Safety;Fuel;Uranium;QADCG
Issue Date: Nov-2012
Publisher: NISCAIR-CSIR, India
Abstract: Alpha-contaminated solid radioactive waste is generated in several plants in the front-end and back-end of the nuclear fuel cycle. Typical plants producing such waste include MOX fuel fabrication plants, fuel reprocessing plants and waste management facilities. The main contaminants of concern are uranium, plutonium and the other actinides. The disposal of such waste needs to be carried out in accordance with regulatory guidelines which require that alpha-contaminated solid waste consignments at levels > 4000 Bq/g may not be disposed of in the near-surface disposal facilities. It is recommended that such waste should be stored temporarily in storage facilities from where they can be retrieved at a later date for ultimate disposal. The storage and disposal of alpha-contaminated waste is occasionally complicated by the co-existence of high radiation fields from the - sources present in the waste. Typical examples include 137+134Cs and 60Co on zircaloy hulls. This requires that the alpha waste carrying high external fields be stored in shielded vaults. Since the analysis involves for the most part shielding of large number of sources and their complex geometries, an elaborate point Kernel method based computer code QAD CG is used. Sources in the drums containing Alpha Waste are estimated on the basis of maximum contact dose rate on the drum which is 6960 mGy/h. The gamma emitting nuclide shall be assumed to be represented by 137Cs to convert the given dose rate in to the activity. A selection of 1000 mm as the side wall and top slab concrete thickness is found to be acceptable. The maximum lateral dose rate is 0.131 µGy/h, and maximum top slab dose rate is 0.651 µGy/h.
Page(s): 836-839
ISSN: 0975-1041 (Online); 0019-5596 (Print)
Appears in Collections:IJPAP Vol.50(11) [November 2012]

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