Uranium oxidation rate summary for the spent nuclear fuel project

Pajunen, A.

doi:10.2172/782326

Cited by 8 publications

(12 citation statements)

References 6 publications

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“…Hot cell studies that dried N Reactor fuel elements in moist inert gas, where rates can be inferred from isothermal periods at 5OoC and 75'C (Lawrence, 1998) Fuel clement shipping observations at approximately 20°C, where gas generation rates were measured (Briggs and Roe, 1997, Attached as Appendix 10.1 to Pajunen, 1999) Assessment of all relevant reaction rate data has been documented in Pajunen, 1999 which confirms that the reaction rates currently used in SNF Project calculations are appropriately conservative. Peer review of Pajunen, 1999 was provided by Fauske and Associates.…”

Section: Basis Of Closurementioning

confidence: 77%

“…These limited data do not provide a sufficient basis to conclude N Reactor fuel oxidation rates are faster than the uranium metal used in tests by other investigators. However, a sensitivity analysis (Pajunen, 1999, Attached as Appendix 10.2), specific to the SNF Project systems, concluded that the MCO is thermally stable for conditions encountered by the SNF process systems, even if the dry air oxidation rates were conservatively applied in project analyses. Also, air ingress accidents are limited by safety class design features.…”

Section: Discussionmentioning

confidence: 99%

“…Fuel element shipping observations allow an estimate of liquid water oxidation reaction rates at approximately 2OoC under real plant conditions (Pajunen, 1999, Attached as Appendix 10.1).…”

Section: Discussionmentioning

confidence: 99%

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Uranium oxidation rates issue closure package

Sexton¹

1999

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Section: Basis Of Closurementioning

confidence: 77%

Section: Discussionmentioning

confidence: 99%

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Uranium oxidation rates issue closure package

Sexton¹

1999

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“…As discussed in section 7.2.1, above, Figures 4-2 and 5-2 of the Uranium Oxidation Rate Summary for the Spent Nuclear Fuel Project (Pajunen 1999), indicate that the air ingress case of Table 3-2 would reduce the overall uranium corrosion rate by more than the above factor of two difference between the heats of reaction. Therefore, the water ingress case will control.…”

Section: Evaluation Of Impurities Listed For the Air Ingress Case Of mentioning

confidence: 88%

“…Fuel Project (Pajunen 1999), the only impact from the air ingress case of Table 3-2 would be a reduction in the uranium corrosion rate.…”

Section: Based On Figures 4-2 and 5-2 Of The Uranium Oxidation Rate Smentioning

confidence: 99%

Evaluation of helium impurity impacts on Spent Nuclear Fuel project processes (OCRWM)

Sherrell¹

1999

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This document identifies the types and quantities of impurities that may be present within helium that is introduced into multi-canister overpacks (MC0)s by various SNF Project facilities, including, but not limited to the Cold Vacuum Drying (CVD) Facility (CVDF). It then evaluates possible impacts of worst case impurity inventories on MCO drying, transportation, and storage processes. Based on the evaluation results, this document: 1) concludes that the SNF Project helium procurement specification can be a factor-of-ten less restrictive than a typical vendor's standard offering (99.96% pure versus the vendor's 99.997% pure standard offering); 2) concludes that the CVDF's current 99.5% purity requirement is adequate to control the quality of the helium that is delivered to the MCO by the plant's helium distribution system; and 3) recommends specific impurity limits for both of the above cases.

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Reactive Behavior of K-Basin Spent Nuclear Fuel

Abrefah¹,

Siciliano²,

Damschen³

et al. 2002

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ph: (865) 576-8401 fax: (865) 576-5728 email: reports@adonis.osti.gov Available to the public from the National Technical Information Service, U.S. Department of Commerce, 5285 Port Royal Rd., Springfield, VA 22161 ph: (800) 553-6847 fax: (703) 605-6900 email: orders@ntis.fedworld.gov online ordering: http://www.ntis.gov/ordering.htmThis document was printed on recycled paper. SummaryThe Hanford Spent Nuclear Fuel Project focuses its efforts on determining how to safely move the degraded N-Reactor spent fuel from water-stored basins to a dry storage facility. As part of this effort, the project initiated experimental studies to address issues relating to the chemical reactivity of the degraded/corroded metallic uranium material. The studies generated a limited set of data on chemical reaction rates of the N-Reactor spent fuel in dry-air, moist-air, and moist-inert atmospheres for comparison with published data on unirradiated/irradiated metallic uranium. Based on the laboratory data, the project chose to use a conservative enhancement factor in analyzing the oxidation behavior of the spent metallic fuel. However, there is a need for the project to increase the fuel throughput for the drying-treatment process by implementing certain design optimization steps. The study discussed in this paper re-evaluated the previous laboratory data in conjunction with the cold vacuum drying (CVD) process experience and determined whether the built-in level of conservatism could accommodate the potential changes in the process without compromising public and worker safety.Evaluations based on laboratory data on samples taken from the corroded N-Reactor spent fuel showed no reactivity enhancement for the degraded metallic uranium in moist atmospheres. The established oxidation reaction-rate constant was used to accurately determine the reactive surface areas of corroded N-Reactor fuel elements. The surface areas calculated for six different N-Reactor elements that were stored in the K-West Basin and shipped to Pacific Northwest National Laboratory for drying studies ranges from as low as 0.0018 m 2 for a broken element to 8.1 m 2 for a highly corroded spent nuclear fuel (SNF) element 5744U based on the measured reaction-rate constant for the K-Basin SNF (k SNF ). On the other hand, if the literature-averaged rate constant (k Lit ) is used, the calculated areas are between 0.0002 and 1.1 m 2 .

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Uranium oxidation rate summary for the spent nuclear fuel project

Cited by 8 publications

References 6 publications

Uranium oxidation rates issue closure package

Uranium oxidation rates issue closure package

Evaluation of helium impurity impacts on Spent Nuclear Fuel project processes (OCRWM)

Reactive Behavior of K-Basin Spent Nuclear Fuel

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