Application of neutron well coincidence counting for plutonium determination in mixed oxide fuel fabrication plant

Kumar, Pradeep; Ramakumar, K. L.

doi:10.1007/s10967-007-7083-5

Cited by 4 publications

(3 citation statements)

References 13 publications

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“…The PuO 2 content in the various scrap was determined using neutron well co-incidence counting technique [33]. The instrument is calibrated using PuO 2 standards (prepared on wt.…”

Section: Chloride and Fluoride Estimationmentioning

confidence: 99%

Impurity analysis and dissolution behaviour of plutonium bearing impure MOX scrap: an assessment of recycling feasibility

Singh

Kumar

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et al. 2016

J Radioanal Nucl Chem

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A significant quantity of plutonium bearing scrap was getting generated during the fabrication of (U,Pu)O 2 mixed oxide fuel for Indian Prototype Fast Breeder Reactor. This document assesses the feasibility of carrying out recycling of the impure scrap to permit the efficient plutonium recovery and re-use. The impure scrap which constitutes nearly 5 % of the total throughput was examined for impurities present and dissolution behaviour in HNO 3 . On the basis of experimental results obtained recycling methodologies are recommended. This study reveals that not all types of the impure scrap need aqueous recycling methods; some can be dry recycled.

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“…The PuO 2 content in the various scrap was determined using neutron well co-incidence counting technique [33]. The instrument is calibrated using PuO 2 standards (prepared on wt.…”

Section: Chloride and Fluoride Estimationmentioning

confidence: 99%

Impurity analysis and dissolution behaviour of plutonium bearing impure MOX scrap: an assessment of recycling feasibility

Singh

Kumar

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et al. 2016

J Radioanal Nucl Chem

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“…Getting such kind of unconventional standards are absolutely unrealistic and commercially not available. Moreover, in order to have reliable estimation, either standard reference materials, or in house synthetic standards are required to validate the developed methodology . However, for these kind of samples, meeting this criteria is also difficult.…”

Section: Introductionmentioning

confidence: 99%

“…Moreover, in order to have reliable estimation, either standard reference materials, or in house synthetic standards are required to validate the developed methodology. [15,16] However, for these kind of samples, meeting this criteria is also difficult. In such case another independent analytical technique is must for comparative evaluation.…”

Section: Introductionmentioning

confidence: 99%

AES and XRF Based Comparative Evaluation of Metallic Constituents at Trace and Minor Levels in Contaminated Neoprene Gauntlets and Cellulosic Materials

2020

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Conventional characterization of plutonium contaminated neoprene gauntlets and cellulosic materials are highly difficult not only due to the non-geometric and unconventional nature of the sample, but also the radio-toxicity associated with them. An analytical method based on direct current arc atomic emission spectrometric (D.C.Arc AES) technique was developed for direct determination of 22 metallic impurities in contaminated neoprene gauntlets and cellulose samples. The samples were incinerated to powder form and analyzed against seven point standardization using graphite standards. The interference free best performed emission lines of the analytes were chosen as the analytical lines for establishing the calibration curves required for their estimation. The linear dynamic range, sensitivity, detection limit, precession associated with these analytical lines were evaluated in the graphite matrix. Energy dispersive X-ray fluorescence spectrometry has also been employed for comparative evaluation of the analytical performance of the developed AES based method as well as analysis of the actual samples. D.C.Arc AES based method was found to have 20% precession, while that for EDXRF was 10%. However, elements with lower Z values and lower concentration can only be determined by AES.

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Characterisation of nuclear fuel by spectroscopic evaluation of alpha autoradiographs

Devi¹,

Ramkumar²,

Sengupta

et al. 2017

J Radioanal Nucl Chem

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Application of neutron well coincidence counting for plutonium determination in mixed oxide fuel fabrication plant

Cited by 4 publications

References 13 publications

Impurity analysis and dissolution behaviour of plutonium bearing impure MOX scrap: an assessment of recycling feasibility

Impurity analysis and dissolution behaviour of plutonium bearing impure MOX scrap: an assessment of recycling feasibility

AES and XRF Based Comparative Evaluation of Metallic Constituents at Trace and Minor Levels in Contaminated Neoprene Gauntlets and Cellulosic Materials

Characterisation of nuclear fuel by spectroscopic evaluation of alpha autoradiographs

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