High-Fidelity Determination of Nuclide Inventories for Radioactive Waste Disposal

Bykov, V.

doi:10.5075/epfl-thesis-8960

Cited by 1 publication

(3 citation statements)

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“…In order to quantify the amount of radioactive waste arising from nuclear power plant decommissioning, Nagra utilizes AMAC [1], based on three-dimensional MCNP [2] models of the plant.…”

Section: Nagra Advanced Methodology For Activation Characterization (...mentioning

confidence: 99%

“…Due to the small size of samples, substantial computational time is required for good statistics, given the large number of samples and the iterative nature of validation. Therefore, the Generic Sample Activation Model (GSAM) was developed [1]. Instead of implementing the small foils directly, a larger cell (typically a sphere of five centimeter diameter) is used to tally the neutron flux distribution.…”

Section: Methodsmentioning

confidence: 99%

“…This result is then used to define the source in a simple MCNP model representing the sample inside the larger cell. This significantly reduces the computational time, albeit at the cost of introducing additional uncertainty, estimated to be in the order of 20% for a typical case [1].…”

Section: Methodsmentioning

confidence: 99%

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Validation of Neutron Flux and Activation in the Nagra AMAC model of the Mühleberg Power Plant

Bykov

Volmert²,

Pelloux³

et al. 2023

EPJ Web Conf.

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The decommissioning of the Mühleberg Nuclear Power Plant (KKM) is supported by Nagra (National Cooperative for the Disposal of Radioactive Waste) through computational analysis of neutron activation in the reactor components and structures using the Nagra Advanced Methodology for Activation Characterization (AMAC). To validate these calculations, measurements of neutron flux and neutron-induced activity were carried out in the form of two foil activation campaigns (72 samples) and three concrete sampling campaigns (118 samples). Generally, the ratio of calculated to measured activities is in the order of 2 in the proximity of the reactor pressure vessel and 3 in the upper sections of the drywell. As expected, the flux in the lower (spherical) part of the drywell is significantly overestimated due to the simplified modelling of this space. The overestimation, which ratios of up to 10, can be corrected by scaling the calculated radionuclide activity distributions in the vicinity of the validation locations.

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“…In order to quantify the amount of radioactive waste arising from nuclear power plant decommissioning, Nagra utilizes AMAC [1], based on three-dimensional MCNP [2] models of the plant.…”

Section: Nagra Advanced Methodology For Activation Characterization (...mentioning

confidence: 99%

Section: Methodsmentioning

confidence: 99%

See 1 more Smart Citation

Validation of Neutron Flux and Activation in the Nagra AMAC model of the Mühleberg Power Plant

Bykov

Volmert²,

Pelloux³

et al. 2023

EPJ Web Conf.

View full text Add to dashboard Cite

show abstract

High-Fidelity Determination of Nuclide Inventories for Radioactive Waste Disposal

Cited by 1 publication

References 0 publications

Validation of Neutron Flux and Activation in the Nagra AMAC model of the Mühleberg Power Plant

Validation of Neutron Flux and Activation in the Nagra AMAC model of the Mühleberg Power Plant

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