Characteristics of the Melt-Dilute Form of Aluminum-Based Nuclear Spent Fuel

Vinson, D.W.

doi:10.2172/799721

Cited by 3 publications

(5 citation statements)

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“…The U composition used for laboratory-scale melts contained 400 ppm C, 125-225 ppm Fe, 125-225 ppm Si, and 50 ppm N2. 1 All other impurities were below 20 ppm. The U component for the laboratory-scale alloys required an oxide removal step with acid just prior to alloy fabrication due to the tendency of U to rapidly form a very stable oxide in air at room temperature.…”

Section: Iiamentioning

confidence: 96%

“…SRNL has conducted extensive research in dilution of fissile materials and production of non-proliferable MWFs since the late 1990s, including evaluating disposition of U-Al spent fuel in Al melts. 1 Fe-based MWFs were investigated to immobilize metallic radioactive species expected from electrometallurgical treatment methods. 2 The goal of this work is to produce a MWF that meets the requirements for a low attractiveness waste, Level D or E, as defined in DOE-STD-1194-2011.…”

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confidence: 99%

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Alloying of U-Al-SS as a Simulant for Pu-Al-SS Alloying

2021

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The Savannah River National Laboratory (SRNL) evaluated several options for disposition of stainlesssteel clad plutonium metal, particularly Pu-10.6 atomic % Al (Pu-1.3 wt % Al) alloy fuel. One technology considered was alloying fuel with stainless steel (SS). The goal of the alloying would be to make a SS-Pu alloy that was a non-proliferable waste form with secondary Pu rich microencapsulated regions distributed throughout the refractory stainless steel. The microencapsulation of the Pu regions should therefore allow the waste form to meet the requirements for a low attractiveness waste as defined by the United States Department of Energy (DOE). Pu bearing alloys at these levels could potentially be suitable for disposal at WIPP. Four metal ingots were successfully fabricated using U and Al as a surrogate for Pu-Al. The U was distributed and microencapsulated by the alloy matrix, thereby setting the stage for subsequent tests using SS-clad fuel elements containing Pu-10.6Al.

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Section: Iiamentioning

confidence: 96%

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confidence: 99%

Alloying of U-Al-SS as a Simulant for Pu-Al-SS Alloying

2021

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“…The assembly with the highest heat generation rate was analyzed from each of EBWR-002, EBWR-004, and EBWR-009 Appendix A files [4][5][6]. These values were found in a memo by Vinson [7]. Rods described by EBWR-001 Appendix A were not considered since the cladding on those rods is made of stainless steel and therefore there is no concern of UZr intermetallic formation.…”

Section: Fuel Assembly Informationmentioning

confidence: 99%

“…This was done because individual data was not available and the power distribution within the core was nearly uniform [30]. EBWR fuel rod heat generation rates were found using Figure 5 in the memo by Vinson [7].…”

Section: Materials Propertiesmentioning

confidence: 99%

Thermal Calculations to Determine Maximum Zircaloy Temperatures During Reactor Operations for Campaign 1 Fuel Assemblies

Truong¹

2023

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“…SRNL has conducted extensive research in dilution of fissile materials and production of non-proliferable MWFs since the late 1990s, including evaluating disposition of U-Al spent fuel in Al melts. [2] Fe-based MWFs were investigated to immobilize metallic radioactive species expected from electrometallurgical treatment methods. [3] The MWF formulation for the current work has few preconditions because the material under consideration has a relatively pure Pu-10.6Al alloy.…”

Section: Introductionmentioning

confidence: 99%

Alloying of Pu-Al with Stainless Steel for Material Disposition

2022

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The Savannah River National Laboratory (SRNL) has evaluated several options for the disposition of stainless-steel clad plutonium metal alloy. One of the technologies under consideration is alloying of the material with stainless steel (SS). The resulting SS-Pu alloy would be a non-proliferable waste form consisting of a secondary Pu composition region microencapsulated in the refractory stainless steel. Two 8-kg ingots were made at SS-1.8Zr-0.4Pu alloys (wt %); 8 kg was determined in a previous study to be the maximum mass of SS ingot at the maximum target Pu loading of 350-g that would result in a SS-4.4Pu alloy (wt %). Two smaller 500-g ingots were also produced at SS-1.6Zr-1.4Pu and SS-1.4Pu (wt %). The 500-g ingots evaluated alloying at a higher Pu concentration than in the 8 kg ingots, and they evaluated the necessity of adding Zr metal to incorporate the Pu and control Pu oxidation. Zr addition was found to be unnecessary to incorporate the Pu and control Pu oxidation. Drill turnings were collected from the large and small ingots and metallographic samples were directly cut from the small ingots. Both were analyzed to validate the structure and composition region formation. Chemical analyses of turnings proved that the Pu was dispersed within the SS ingots.

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Characteristics of the Melt-Dilute Form of Aluminum-Based Nuclear Spent Fuel

Cited by 3 publications

References 0 publications

Alloying of U-Al-SS as a Simulant for Pu-Al-SS Alloying

Alloying of U-Al-SS as a Simulant for Pu-Al-SS Alloying

Thermal Calculations to Determine Maximum Zircaloy Temperatures During Reactor Operations for Campaign 1 Fuel Assemblies

Alloying of Pu-Al with Stainless Steel for Material Disposition

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