EBR-II blanket fuel leaching test using simulated J-13 well water.

Fonnesbeck, J. E.

doi:10.2172/754233

Cited by 4 publications

(5 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Similar tests on non-irradiated N Reactor fuel at 25°C (Abrefah et al 2000) are at or lower than the rate forecast by the STP rate law. The 90°C rate datum for uranium metal blanket fuel irradiated to ~30,000 MWD/MTU (Fonnesbeck et al 1998) also is shown in Figure 3.3 and likewise is consistent with the STP rate. Comparable corrosion-rate measurements of non-irradiated EBR-II fuel metal in anoxic liquid water by hydrogen gas generation were conducted at the same 90°C temperature by the same laboratory (Fonnesbeck 2000(Fonnesbeck , 2003.…”

Section: Correspondence Of Irradiated Uranium Metal Corrosion Rates Isupporting

confidence: 72%

“…Overall, the paired findings for the irradiated and non-irradiated N Reactor fuel at 25°C Einziger 1998 andAbrefah et al 2000, respectively) and irradiated and non-irradiated EBR-II fuel at 90°C (Fonnesbeck et al 1998and Fonnesbeck 2000, 2003 show irradiation to increase rates. However, the effects of irradiated fuel crumbling or increased surface area were not investigated.…”

Section: Correspondence Of Irradiated Uranium Metal Corrosion Rates Imentioning

confidence: 89%

See 1 more Smart Citation

Uranium Metal Reaction Behavior in Water, Sludge, and Grout Matrices

Delegard

Schmidt²

2008

View full text Add to dashboard Cite

This report was originally published in September 2008. In May 2009, it was discovered that, in the introductory paragraphs of Section 2.1, the units for the reaction enthalpy of uranium metal with water to form uranium dioxide and hydrogen and the reaction enthalpy of hydrogen with oxygen to form water were incorrectly given as kcal/mole rather than kJ/mole. This version of the report, Revision 1, corrects the units for both enthalpies to kJ/mole. Other small editorial changes also were made.iii SummaryThis report summarizes information and data on the reaction behavior of uranium metal in water, in water-saturated simulated and genuine K Basin sludge, and in grout matrices. This information and data are used to establish the technical basis for metallic uranium reaction behavior for the K Basin Sludge Treatment Project (STP). The specific objective of this report is to consolidate the various sources of information into a concise document to serve as a high-level reference and road map for customers, regulators, and interested parties outside the STP (e.g., external reviewers, other DOE sites) to clearly understand the current basis for the corrosion of uranium metal in water, sludge, and grout.The generation of hydrogen gas through oxidation/corrosion of uranium metal by its reaction with water can potentially create a flammable atmosphere during sludge handling, grouting, or subsequent transport and storage operations. Consequently, a thorough understanding of the uranium metal content and its reaction behavior, both in sludge and in grouted sludge matrices, is essential to the process designs and for management of sludge. Results of studies of this reaction and its characteristics have been reported in the technical literature for over 60 years. More focused studies of the reaction in simulated and genuine K Basin sludge and in grout matrices have been conducted in the past 10 years. The outcomes of these studies, provided in the present review, show that: The reaction of uranium metal with anoxic liquid water is highly exothermic and produces stoichiometric uranium dioxide (UO 2 ) and hydrogen. The reaction apparently proceeds through a uranium hydride intermediate that can sequester part of the hydrogen during the initial reaction. The corrosion reaction occurs isotropically such that the uranium particle size decreases at a constant rate at a given temperature. Based on a survey of 32 studies giving 128 data points, the corrosion rate follows an Arrhenius dependence on temperature (i.e., the logarithm of the rate is proportional to the inverse absolute temperature) from at least 24°C to 350°C. The rate law was adopted for the STP. A 95% confidence level on the predicted rate is plus/minus about a factor of three. The STP rate law is essentially the same as used in the application to license the Yucca Mountain repository. Dissolved oxygen inhibits the reaction of uranium metal with liquid water, but the more rapid anoxic reaction can follow the lower oxic rates at times that are difficult to predict...

show abstract

Section: Correspondence Of Irradiated Uranium Metal Corrosion Rates Isupporting

confidence: 72%

Section: Correspondence Of Irradiated Uranium Metal Corrosion Rates Imentioning

confidence: 89%

Uranium Metal Reaction Behavior in Water, Sludge, and Grout Matrices

Delegard

Schmidt²

2008

View full text Add to dashboard Cite

show abstract

“…In immersion oxidation tests performed on irradiated uranium, around 10% uranium hydride was observed in the reaction products of some of the samples that were not completely oxidized. 75 Since uranium hydride is an intermediate product that oxidizes to UO 2 , a transient amount of residual UH 3 is expected to form while the U metal is still reacting and if the UH 3 oxidation rate is less than the U metal oxidation rate, as has been reported. 80,81 In some studies, the presence of hydride has been speculated to increase the reaction rate of uranium metal oxidation.…”

Section: Uranium-hydride Effects On Uranium Metal Oxidationmentioning

confidence: 88%

“…The similarity between oxidation rates of KW SNF and U metal is also consistent with dissolution rates of irradiated uranium metal fuel reported by Gray and Einziger at PNNL and Fonnesbeck at Argonne National Laboratory-West (ANL-W). 74,75 The effects of irradiation on uranium metal oxidation are summarized as follows. Irradiation does not increase the intrinsic oxidation rate of uranium metal.…”

Section: Irradiation Effects On Uranium Metal Oxidationmentioning

confidence: 99%

Review of oxidation rates of DOE spent nuclear fuel : Part 1 : nuclear fuel.

Hilton¹

2000

View full text Add to dashboard Cite

“…The corrosion of the highly irradiated EBR-II blanket fuel was tested in closed vessels with initially aerated simulated groundwater and air cover gas (Fonnesbeck et al 1998). The vessels were opened weekly for sampling, fresh aerated water was added, and the vessels were reclosed.…”

Section: Uranium Metal Corrosion Rates In Oxic Liquid Watermentioning

confidence: 99%