Radioactive contamination measurements of the primary sodium pipes in FBTR by gamma spectrometry

Jose, M.T.; Ravi, T.; Krishnakumar, D. N.; Meenakshisundaram, V.

doi:10.1016/j.anucene.2008.12.030

Cited by 7 publications

(2 citation statements)

References 2 publications

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“…The gamma spectrometric measurement was performed on primary sodium pipes after 651 effective full power days of operation of fast breeder test reactor (FBTR), Kalpakkam, India, under two scenarios such as sodium circulating at 453 K and sodium drained out from the pipes [7]. The radionuclides observed before sodium draining were 54 Mn, 58 Co, 60 Co formed by neutron activation of structural material and 22 Na, 24 Na, 203 Hg formed by neutron activation of sodium and soluble impurities in sodium.…”

Section: Fast Breeder Test Reactor (Fbtr)mentioning

confidence: 99%

Nickel foam for trapping Manganese and Cobalt from Liquid Sodium

Jana

Manivannan

Mahato

et al. 2014

Trans Indian Inst Met

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In the absence of fuel pin failure, major radiation burden in primary heat transport system of a sodium cooled fast reactor is due to long-lived and high gamma active corrosion products 54 Mn, 60 Co and 58 Co. For minimizing the radiation burden to operation and maintenance personnel, radionuclide traps are essential to concentrate and contain these radionuclides in a particular location of primary system. To remove activated corrosion products from primary sodium, use of nickel foam as radionuclide trap material has been proposed as a candidate trap material for fast reactors as against the use of nickel in form of rolled sheet and pall rings. This paper describes about the effectiveness of nickel foam for trapping manganese and cobalt from liquid sodium.

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Section: Fast Breeder Test Reactor (Fbtr)mentioning

confidence: 99%

Nickel foam for trapping Manganese and Cobalt from Liquid Sodium

Jana

Manivannan

Mahato

et al. 2014

Trans Indian Inst Met

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“…Thus, the corrosion rate at different section of the loop cannot be simply represented by the corrosion product concentrations at different locations of the loop. In situ gamma spectrometric measurements of radionuclides have been proposed to be utilized in the primary system of nuclear reactors to characterize the migration and deposition of radioactive elements during the reactor operation 27,28 .…”

mentioning

confidence: 99%

Radionuclide tracing based in situ corrosion and mass transport monitoring of 316L stainless steel in a molten salt closed loop

Wang,

Olson,

Falconer

et al. 2024

Nat Commun

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In the study, we report an in situ corrosion and mass transport monitoring method developed using a radionuclide tracing technique for the corrosion study of 316L stainless steel (316L SS) in a NaCl–MgCl2 eutectic molten salt natural circulation loop. This method involves cyclotron irradiation of a small tube section with 16 MeV protons, later welds at the hot leg of the molten salt flow loop, generating radionuclides 51Cr, 52Mn, and 56Co at the salt–alloy interface. By measuring the activity variations of these radionuclides at different sections along the loop, both the in situ monitoring of the corrosion attack depth of 316L SS and corrosion product transport and its precipitation in flowing NaCl–MgCl2 molten salt are achieved. While 316L SS is the focus of this study, the technique reported herein can be extended to other structural materials being used in a wide range of industrial applications.

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