The energy spectrum of α-particles emitted from used CANDU™ fuel

Garisto, Frank

doi:10.1016/0306-4549(89)90118-7

Cited by 17 publications

(10 citation statements)

References 4 publications

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“…In order to evaluate the ratio of theoretical dose rates expected at the reactional interface, it is necessary to know the average energy of the alpha particles at the interface. It can be estimated using the following relationship [22] (Equation 4)…”

Section: Resultsmentioning

confidence: 99%

Spent nuclear fuel/water interface behavior: Alpha dose rate profile determination for model surfaces and microcracks by using Monte-Carlo methods

Tribet

Mougnaud

Jégou

2017

Journal of Nuclear Materials

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This work aims to better understand the nature and evolution of energy deposits at the UO2/water reactional interface subjected to alpha irradiation, through an original approach based on Monte-Carlo-type simulations, using the MCNPX code. Such an approach has the advantage of describing the energy deposit profiles on both sides of the interface (UO2 and water). The calculations have been performed on simple geometries, with data from an irradiated UOX fuel (burnup of 47 GWd.tHM-1 and 15 years of alpha decay). The influence of geometric parameters such as the diameter and the calculation steps at the reactional interface are discussed, and the exponential laws to be used in practice are suggested. The case of cracks with various different apertures (from 5 to 35 µm) has also been examined and these calculations have also enabled new information on the mean range of radiolytic species in cracks, and thus on the local chemistry.

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Section: Resultsmentioning

confidence: 99%

Spent nuclear fuel/water interface behavior: Alpha dose rate profile determination for model surfaces and microcracks by using Monte-Carlo methods

Tribet

Mougnaud

Jégou

2017

Journal of Nuclear Materials

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“…1) corresponds to the dissolution of a $0.1 lm thick layer. Because this thickness is much smaller than the range of the alpha particles in the Pu-doped material ($12.4 lm [22]), the alpha dose at the solid/water interface should be relatively constant during the experiment. The alpha dose is determined by the volume of the Pudoped UO 2 that can contribute to dose, and this volume is determined by the mean path length of alpha-particles in a UO 2 matrix (i.e., $12.4 lm [22]).…”

Section: Figs 3 and 4 Show Uerõs For The 167 D And 270 D Experimentsmentioning

confidence: 99%

The effects of alpha-radiolysis on UO2 dissolution determined from batch experiments with 238Pu-doped UO2

Stroes-Gascoyne

Garisto

Betteridge

2005

Journal of Nuclear Materials

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“…where r = range of α-radiation in the solid and x = segment height. A derivation for CANDU fuel 12 gives even a smaller percentage of radiation energy, which is effective in the adjacent solution.…”

Section: Resultsmentioning

confidence: 99%

Radiolysis and corrosion of238Pu-doped UO2 pellets in chloride brine

Kelm

Bohnert

2002

J Chem Sci

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Deaerated 5 M NaCl solution is irradiated in the presence of UO 2 pellets with α-radiation from 238 Pu. Experiments are conducted with 238 Pu doped pellets and others with 238 Pu dissolved in the brine. The radiolysis products and yields of mobilized U and Pu from the oxidative dissolution of UO 2 are determined. Results found for radiolysis products and for the oxidation/dissolution of pellets immersed in Pu containing brine are similar to results for Pu doped pellets, where the radiation chemical processes occur only in the liquid layer of some 10 µm thickness adjacent to the pellet. The yield of radiolysis products is comparable to earlier results, that of mobilized U from the pellets is < 1% of the total amount of oxidized species. Thus, the radiation chemical yield (G-value) for mobilized hexavalent U is < 0⋅01 ions/ 100 eV. In spite of the low radiation yield for the corrosion, the rate of UO 2 dissolution is higher than expected for the concentrations of long-lived oxidizing radiolysis compounds found in the solutions.

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The energy spectrum of α-particles emitted from used CANDU™ fuel

Cited by 17 publications

References 4 publications

Spent nuclear fuel/water interface behavior: Alpha dose rate profile determination for model surfaces and microcracks by using Monte-Carlo methods

Spent nuclear fuel/water interface behavior: Alpha dose rate profile determination for model surfaces and microcracks by using Monte-Carlo methods

The effects of alpha-radiolysis on UO2 dissolution determined from batch experiments with 238Pu-doped UO2

Radiolysis and corrosion of238Pu-doped UO2 pellets in chloride brine

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