[HTML][HTML] Uncertainty quantification of spent nuclear fuel with multifidelity Monte Carlo

A Albà, A Adelmann, D Rochman - Annals of Nuclear Energy, 2025 - Elsevier
Uncertainty quantification (UQ) of spent nuclear fuel (SNF) is a crucial task that provides
predictions and confidence bounds for important quantities of interest, such as decay heat …

Consistent criticality and radiation studies of Swiss spent nuclear fuel: the CS2M approach

D Rochman, A Vasiliev, H Ferroukhi… - Journal of hazardous …, 2018 - Elsevier
In this paper, a new method is proposed to systematically calculate at the same time canister
loading curves and radiation sources, based on the inventory information from an in-core …

Nuclear data uncertainty quantification in criticality safety evaluations for spent nuclear fuel geological disposal

M Frankl, M Hursin, D Rochman, A Vasiliev… - Applied Sciences, 2021 - mdpi.com
Presently, a criticality safety evaluation methodology for the final geological disposal of
Swiss spent nuclear fuel is under development at the Paul Scherrer Institute in collaboration …

Development and application of data assimilation methods in reactor physics

DJ Siefman - 2019 - infoscience.epfl.ch
Simulations of nuclear reactor physics can disagree significantly from experimental
evidence, even when the most accurate models are used. An important part of this bias from …

Uncertainties of PWR spent nuclear fuel isotope inventory for back-end cycle analysis with STREAM/RAST-K

J Jang, C Kong, B Ebiwonjumi, Y Jo, D Lee - Annals of Nuclear Energy, 2021 - Elsevier
This paper presents a study of uncertainty quantification (UQ) of spent nuclear fuel isotope
inventory. Takahama-3 realistic assays were used for calculation to quantify the impact of …

Preliminary assessment of criticality safety constraints for Swiss spent nuclear fuel loading in disposal canisters

A Vasiliev, J Herrero, M Pecchia, D Rochman… - Materials, 2019 - mdpi.com
This paper presents preliminary criticality safety assessments performed by the Paul
Scherrer Institute (PSI) in cooperation with the Swiss National Cooperative for the Disposal …

Uncertainty quantification of LWR-PROTEUS Phase II experiments using CASMO-5

J Park, W Kim, M Hursin, G Perret, A Vasiliev… - Annals of Nuclear …, 2019 - Elsevier
This paper presents an improved uncertainty quantification technique for the validation of
CASMO-5 on the spent fuel reactivity worth experiments of the LWR-PROTEUS Phase II …

[HTML][HTML] Optimization of Swiss used nuclear fuel canister for final repository: Homogeneous vs. mixed loading

D Rochman, A Vasiliev, H Ferroukhi, M Pecchia - Annals of Nuclear Energy, 2020 - Elsevier
In this paper, the possibilities and advantages of loading mixed used nuclear fuel (UNF)
assemblies into canisters for final repository are presented from a criticality aspect within the …

Effects of materials and design on the criticality and shielding assessment of canister concepts for the disposal of spent nuclear fuel

MM Gutiérrez, S Caruso, N Diomidis - Applied Radiation and Isotopes, 2018 - Elsevier
According to the Swiss disposal concept, the safety of a deep geological repository for spent
nuclear fuel (SNF) is based on a multi-barrier system. The disposal canister is an important …

[PDF][PDF] Criticality safety evaluations for the concept of Swiss PWR spent fuel geological repository

A Vasiliev, J Herrero, D Rochman… - Proceedings of the …, 2018 - tendl.web.psi.ch
ABSTRACT R&D works on the spent fuel criticality safety, including burnup credit, are
ongoing in Switzerland in relation to the preparation of a general license application for a …