Dissolution of Plutonium Metal in 8-10 M Nitric Acid

Rudisill, T. S.; Pierce, R. A.

doi:10.2172/1045615

Cited by 3 publications

(8 citation statements)

References 7 publications

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“…The Pu metal used for the low temperature dissolution flowsheet demonstration experiments is from the same batch of material used to develop the flowsheet currently in use. (1) The samples were prepared from delta phase metal. A thin oxide coating was present on the surface.…”

Section: Methodsmentioning

confidence: 99%

“…Plutonium metal is dissolved in the H-Canyon 6.1D dissolver to prepare feed solution for PuO 2 production. (1) To prepare a dissolver charge, 3013 Pu storage containers are transferred to HB-Line where the inner containers are cut open and the contents transferred to dissolvable carbon steel cans (containing no polymeric gasket materials). The cans are then bagged out of the glovebox into dissolvable nylon bags and transferred to the Hot Crane Maintenance Area (HCMA).…”

Section: Introductionmentioning

confidence: 99%

“…Under the current flowsheet, the dissolving solution is heated to boiling after complete charging of the dissolver until the Pu metal is dissolved. (1) During charging of the 6.1D dissolver for the Batch 5 of Pu metal dissolution, the Savannah River Site (SRS) entered an operational pause. When deliberate operations in H Canyon resumed, the ambienttemperature solution in the dissolver was sampled and the analysis indicated that all the Pu metal had dissolved (without heating).…”

Section: Introductionmentioning

confidence: 99%

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Low temperature dissolution flowsheet for Pu metal

Daniel

Almond

Rudisill

2017

Separation Science and Technology

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The Savannah River National Laboratory was requested to develop a Pu metal dissolution flowsheet at two reduced temperature ranges for implementation in the Savannah River Site H-Canyon facility. The dissolution and H 2 generation rates during Pu metal dissolution were investigated using a dissolving solution at ambient temperature (20-30 °C) and for an intermediate temperature of 50-60 °C. The Pu metal dissolution rate measured at 57 °C was approximately 20 times slower than at boiling (112 -116 °C). The dissolution rate at ambient temperature (24 °C) was approximately 80 times slower than the dissolution rate at boiling Hydrogen concentrations were less than detectable (<0.1 vol %). Low Temperature Dissolution Flowsheet for Pu Metal SRNL-STI-2016-00524 page 19 of 26 * Estimated dissolution rate(1) **Dissolving solution also contained 0.4 g/L Ni and 0.6 g/L Cr

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Section: Methodsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Low temperature dissolution flowsheet for Pu metal

Daniel

Almond

Rudisill

2017

Separation Science and Technology

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“…Plutonium: Plutonium was included in the feed matrix for Cr313 and Cr314 based on the nominal flowsheet 3 . Figure 6 shows that Pu is strongly loaded onto the resin and with minor losses of ~1.5% by 10 BV's of an 8 M HNO 3 wash.…”

Section: Wash and Elution Acid Puritymentioning

confidence: 99%

“…Three levels of ICD limits are given: 1) Column B, 2) Column A and 3) Exceptional. Significant levels of select impurities will be added in the H-Canyon dissolution process 3 but additional information was needed to determine what other impurities need to be removed by the process. The proposed feedstock to this process is part of an inventory characterized as Alternate Feedstocks 2 (AFS-2) and consists of Pu metal from multiple sources.…”

Section: Introductionmentioning

confidence: 99%

Hb-Line Anion Exchange Purification of Afs-2 Plutonium for Mox

Kyser¹,

King²

2012

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DIissolution of low enriched uranium from the experimental breeder reactor-II fuel stored at the Idaho National Laboratory

Daniel

Rudisill

Almond

et al. 2017

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The Idaho National Laboratory (INL) is actively engaged in the development of electrochemical processing technology for the treatment of fast reactor fuels using irradiated fuel from the Experimental Breeder Reactor-II (EBR-II) as the primary test material. The research and development (R&D) activities generate a low enriched uranium (LEU) metal product from the electrorefining of the EBR-II fuel and the subsequent consolidation and removal of chloride salts by the cathode processor. The LEU metal ingots from past R&D activities are currently stored at INL awaiting disposition. One potential disposition pathway is the shipment of the ingots to the Savannah River Site (SRS) for dissolution in H-Canyon. Carbon steel cans containing the LEU metal would be loaded into reusable charging bundles in the H-Canyon Crane Maintenance Area and charged to the 6.4D or 6.1D dissolver. The LEU dissolution would be accomplished as the final charge in a dissolver batch (following the dissolution of multiple charges of spent nuclear fuel (SNF)). The solution would then be purified and the 235 U enrichment downblended to allow use of the U in commercial reactor fuel. To support this potential disposition path, the Savannah River National Laboratory (SRNL) developed a dissolution flowsheet for the LEU using samples of the material received from INL.A dissolution flowsheet for the LEU ingots generated at the INL from the electrochemical processing of the EBR-II fuel was demonstrated at the laboratory scale. Dissolution experiments were performed using samples of the LEU and a carbon steel can and an integrated experiment was performed in which an Al 1100 alloy was dissolved as a surrogate for SNF followed by the dissolution of samples of the LEU and carbon steel can to demonstrate the complete flowsheet. The flowsheet allows the dissolution of a SNF batch in an H-Canyon dissolver using existing flowsheets followed by the dissolution of nominally 75 kg of LEU in the 6.4D dissolver or 45 kg of LEU in the 6.1D dissolver which were recovered from the EBR-II fuel. In the demonstration experiment, the rate of dissolution of the LEU metal was significantly slower than the dissolution rate of the Al 1100 alloy (4.7 mg/min/cm 2 versus 27 mg/min/cm 2 ) which projects to a longer cycle time for the LEU metal (compared to a SNF charge). The H 2 generation rate from the dissolution of samples of the LEU metal and a carbon steel can were monitored by mass spectrometry and Raman spectroscopy and were shown to be inconsequential; therefore, the dissolution of the LEU ingots has no significant impact on the generation of H 2 .

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Dissolution of Plutonium Metal in 8-10 M Nitric Acid

Cited by 3 publications

References 7 publications

Low temperature dissolution flowsheet for Pu metal

Low temperature dissolution flowsheet for Pu metal

Hb-Line Anion Exchange Purification of Afs-2 Plutonium for Mox

DIissolution of low enriched uranium from the experimental breeder reactor-II fuel stored at the Idaho National Laboratory

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