Alkaline extraction of polonium from liquid lead bismuth eutectic

Heinitz, S.; Neuhausen, Jörg; Schumann, D.

doi:10.1016/j.jnucmat.2011.03.043

Cited by 10 publications

(9 citation statements)

References 12 publications

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“…It should be noted that the results of EDX analysis agree with the results of chemical analysis of the LGE and LBE samples from the same test, which showed the Cr, Ni and Mn content in LGE was much high than that in LBE [7]. Fig.…”

Section: Ss 316ln Specimens After Exposure In Lbe and Lgesupporting

confidence: 80%

A comparative study on the compatibility of liquid lead–gold eutectic and liquid lead–bismuth eutectic with T91 and SS 316LN steels

Dai

Gao

Zhang

et al. 2012

Journal of Nuclear Materials

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Section: Ss 316ln Specimens After Exposure In Lbe and Lgesupporting

confidence: 80%

A comparative study on the compatibility of liquid lead–gold eutectic and liquid lead–bismuth eutectic with T91 and SS 316LN steels

Dai

Gao

Zhang

et al. 2012

Journal of Nuclear Materials

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“…This was considered as time zero of the experiment. A silver tube of 2 cm length (Goodfellow, thickness 0.020 ± 0.003 mm, purity 99.9 %) was lining the inside of the end of each column (8), where the temperature was approximately 298 K, to trap polonium species not retained on the SS316L surface. The activity of 206 Po was measured by a HPGe-γdetector in comparison with measurements, in the same geometry, of certified standard reference sources.…”

Section: Thermochromatographymentioning

confidence: 99%

“…Several methods have been considered for removing polonium directly from the LBE, see e. g. Refs. [5,7,8], or to permanently absorb it from the gas plenum above the LBE using dedicated filter materials. For the latter purpose, the first two papers of this series studied the interaction of polonium with different noble metals as candidates for filtering materials [9,10].…”

Section: Introductionmentioning

confidence: 99%

Adsorption of volatile polonium species on metals in various gas atmospheres: Part III – Adsorption of volatile polonium on stainless steel 316L

et al. 2017

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AbstractThis article summarizes the results obtained studying the interaction between polonium and stainless steel 316L in different atmospheres by the thermochromatography method. This issue is particularly important in terms of licensing of the MYRRHA prototype ADS reactor, where highly radiotoxic α-emitting polonium isotopes are produced in lead-bismuth eutectic used as both spallation target material and coolant, while stainless steel 316L is going to be the main structural material. The polonium adsorption enthalpy on stainless steel 316L in inert atmosphere was measured as −147±6 kJ mol−1. The findings obtained using reducing atmospheres show that the affinity of polonium for stainless steel 316L increases with the metallic character of the stainless steel surface. The presence of moisture in inert and reducing atmosphere does not significantly influence the polonium adsorption. Oxidizing atmospheres induce the formation of polonium dioxide which has a stronger interaction with the stainless steel 316L, with an adsorption enthalpy of −225±6 kJ mol−1. A prolonged exposure of the stainless steel to strong oxidants, such as pure oxygen, reduces the metallic character of the stainless steel surface and, consequently, its affinity to the polonium oxide. Furthermore, it was found that in all experiments at least 5 ppm of the total polonium present in the starting material were not retained on the stainless steel 316L surface at all.

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“…The major concern is the formation of 210 Po, which has an inhalation and ingestion radiotoxicity among the highest of all the known radionuclides [4,5]. In a typical neutron environment characteristic of fast reactors (neutron fluxes at the level of 10 15 n/(cm 2 s)) its activity can reach up to 10 11 Bq/kg [6]. In the MYRRHA reactor pool, assuming that all 210 Po is retained in LBE, the estimated production of this radioisotope after one irradiation cycle at nominal power would be at the level of 350 g, or 5.5 Â 10 4 TBq [7].…”

mentioning

confidence: 99%

Nuclear data uncertainty analysis for the Po-210 production in MYRRHA

Fiorito

Stankovskiy

Hernández-Solís

et al. 2018

EPJ Nuclear Sci. Technol.

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MYRRHA is a multi-purpose research reactor able to operate in sub-critical and critical modes and currently in the design phase at SCK•CEN. The choice of LBE was driven by its chemical stability, low melting temperature, high boiling point, low chemical reactivity with water and air and a good neutronic performance. As a drawback, the neutron capture in 209 Bi results in the production of 210 Po, a highly radiotoxic alpha emitter with relatively short half-life (≈138 days). The 210 Po production represents a major safety concern that has to be addressed for the reactor licensing. In this work we used the ALEPH-2 burnup code to accurately calculate the 210 Po production in a MYRRHA operating cycle. The impact of using different nuclear data libraries was evaluated and the reliability of the results was determined by quantifying the uncertainty of the 210 Po concentration. The uncertainty quantification was carried out sampling the currently available nuclear data covariance matrices with the SANDY code. Also, estimates of the sensitivity profiles were obtained with a linear regression approach. The activation yield of the 209 Bi neutron capture reaction was assessed as the largest nuclear data source of uncertainty, however the lack of covariances for such data represent a capital drawback for the 210 Po content prediction.

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Alkaline extraction of polonium from liquid lead bismuth eutectic

Cited by 10 publications

References 12 publications

A comparative study on the compatibility of liquid lead–gold eutectic and liquid lead–bismuth eutectic with T91 and SS 316LN steels

A comparative study on the compatibility of liquid lead–gold eutectic and liquid lead–bismuth eutectic with T91 and SS 316LN steels

Adsorption of volatile polonium species on metals in various gas atmospheres: Part III – Adsorption of volatile polonium on stainless steel 316L

Nuclear data uncertainty analysis for the Po-210 production in MYRRHA

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