Elemental composition in sealed plutonium–beryllium neutron sources

Xu, N.; Kuhn, Kevin J.; Gallimore, David; Martínez, A.; Schappert, Michael Francis; Montoya, Dennis Patrick; Lujan, Elmer; Garduno, Katherine; Tandon, Lav

doi:10.1016/j.apradiso.2014.10.013

Cited by 11 publications

(5 citation statements)

References 12 publications

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“…Pu(IV) was retained on the column while trace impurity cations passed through after several washes, as they have minimum retention to the AG-MP-1 resin. Raffinate was collected and adjusted to the desired acid molarity with DI water [6] prior to be analyzed for trace elements by ICP-OES.…”

Section: Sample Preparationmentioning

confidence: 99%

Novel sample introduction system to reduce ICP-OES sample size for plutonium metal trace impurity determination

Montoya

Manard

2015

J Radioanal Nucl Chem

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A new methodology for trace elemental analysis in plutonium metal samples was developed by interfacing the novel micro-FAST sample introduction system with an ICP-OES instrument. This integrated system, especially when coupled with a low flow rate nebulization technique, reduced the sample volume requirement significantly. Improvements to instrument sensitivity and measurement precision, as well as long term stability, were also achieved by this modified ICP-OES system. The sample size reduction, together with other instrument performance merits, is of great significance, especially to nuclear material analysis.

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Section: Sample Preparationmentioning

confidence: 99%

Novel sample introduction system to reduce ICP-OES sample size for plutonium metal trace impurity determination

Montoya

Manard

2015

J Radioanal Nucl Chem

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“…In the case of two concentrations of HNO 3 are employed, switching from 10 M HNO 3 to 8 M HNO 3 is performed manually. The elution sequence was controlled by a MX Series II selector valve (IDEX Health and Science, Rohnert Park, CA, US), following the separation protocol as previous described [17]. A custom Labview program was written to automatically control syringe pumps and selector valve, using the process parameters listed in Table 1.…”

Section: Trace Element Separation Proceduresmentioning

confidence: 99%

“…Flow rate for elution could impact the separation. In our conventional column separation protocol, gravity flow is used for elution [17]. However, a much lower flow rate is used for the microcolumn separation to avoid backpressure build-up.…”

Section: Trace Element Separation and Matrix Recoverymentioning

confidence: 99%

Solid-phase extraction microfluidic devices for matrix removal in trace element assay of actinide materials

Gao

Manard

Castro

et al. 2017

Talanta

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Advances in sample nebulization and injection technology have significantly reduced the volume of solution required for trace impurity analysis in plutonium and uranium materials. Correspondingly, we have designed and tested a novel chip-based microfluidic platform, containing a 100-µL or 20-µL solid-phase microextraction column, packed by centrifugation, which supports nuclear material mass and solution volume reductions of 90% or more compared to standard methods. Quantitative recovery of 28 trace elements in uranium was demonstrated using a UTEVA chromatographic resin column, and trace element recovery from thorium (a surrogate for plutonium) was similarly demonstrated using anion exchange resin AG MP-1. Of nine materials tested, compatibility of polyvinyl chloride (PVC), polypropylene (PP), and polytetrafluoroethylene (PTFE) chips with the strong nitric acid media was highest. The microcolumns can be incorporated into a variety of devices and systems, and can be loaded with other solid-phase resins for trace element assay in high-purity metals.

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“…Therefore, PuBe is favorable for situations desiring little to no gamma interactions during sample activation experiments. Like 241 AmBe, PuBe has a stable neutron yield and does not need to be replenished often [18]. Although PuBe has desirable properties as a neutron source, its use has been in decline in recent years due to the inherent need for plutonium.…”

Section: Pubementioning

confidence: 99%

Design, Construction, and Modeling of a²⁵²Cf Neutron Irradiator

Anderson

Holbert

Bowler

2016

Science and Technology of Nuclear Installations

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Neutron production methods are an integral part of research and analysis for an array of applications. This paper examines methods of neutron production, and the advantages of constructing a radioisotopic neutron irradiator assembly using252Cf. Characteristic neutron behavior and cost-benefit comparative analysis between alternative modes of neutron production are also examined. The irradiator is described from initial conception to the finished design. MCNP modeling shows a total neutron flux of 3 × 105 n/(cm2·s) in the irradiation chamber for a 25 μg source. Measurements of the gamma-ray and neutron dose rates near the external surface of the irradiator assembly are 120 μGy/h and 30 μSv/h, respectively, during irradiation. At completion of the project, total material, and labor costs remained below $50,000.

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Elemental composition in sealed plutonium–beryllium neutron sources

Cited by 11 publications

References 12 publications

Novel sample introduction system to reduce ICP-OES sample size for plutonium metal trace impurity determination

Novel sample introduction system to reduce ICP-OES sample size for plutonium metal trace impurity determination

Solid-phase extraction microfluidic devices for matrix removal in trace element assay of actinide materials

Design, Construction, and Modeling of a²⁵²Cf Neutron Irradiator

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Elemental composition in sealed plutonium–beryllium neutron sources

Cited by 11 publications

References 12 publications

Novel sample introduction system to reduce ICP-OES sample size for plutonium metal trace impurity determination

Novel sample introduction system to reduce ICP-OES sample size for plutonium metal trace impurity determination

Solid-phase extraction microfluidic devices for matrix removal in trace element assay of actinide materials

Design, Construction, and Modeling of a252Cf Neutron Irradiator

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Product

Resources

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Design, Construction, and Modeling of a²⁵²Cf Neutron Irradiator