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Interaction between BaCO3 and OPC/BFS composite cements at 20 degrees C and 60 degrees C

Publications associées (29)

Validation of spent nuclear fuel decay heat calculations using Polaris, ORIGEN and CASMO5

Andreas Pautz, Dimitri Rochman, Stefano Caruso

Decay heat calculations of spent nuclear fuel (SNF) using Polaris and ORIGEN codes in the SCALE code sys-tem, and CASMO5 code, are validated using measurements from the Clab and GE-Morris facilities. Multiple hypothesis testing, relying on permutations and ...

PERGAMON-ELSEVIER SCIENCE LTD2022

Data-Driven Predictive Models: Calculational Bias in Characterization of Spent Nuclear Fuel

Characteristics of the spent nuclear fuel (SNF) are typically calculated, requiring validation a priori. The validation process relies on the difference between calculations and measurements, namely the bias. Usually, predicting the bias based on benchmark ...

EPFL2022

Delayed Hydride Cracking in Irradiated and Unirradiated Zircaloy-2 Cladding

Aaron William Colldeweih

Zirconium alloys used in the nuclear industry are exposed to extreme conditions undergoing high levels of irradiation damage and corrosion. Zircaloy-2 is used as nuclear fuel cladding in boiling water reactors and for the encapsulation of the spallation ta ...

EPFL2022

Growth and persistence of an aerobic microbial community in Wyoming bentonite MX-80 despite anoxic in-situ conditions

Rizlan Bernier-Latmani, Manon Frutschi, Niels Burzan, Roberta Murad Lima

Microbial activity has the potential to enhance the corrosion of high-level radioactive waste disposal canisters, which, in the proposed Swiss deep geological repository, will be embedded in bentonite and placed in the Opalinus Clay rock formation (OPA). T ...

Frontiers Media SA2022

Effect of different ions on dissolution rates of silica and feldspars at high pH

Karen Scrivener, Barbara Lothenbach, Mahsa Bagheri, Mahdieh Shakoorioskooie

The dissolution kinetics of silica-containing minerals in aggregates influences strongly the process of ASR in concrete. In this paper, the effect of different ions on the dissolution rates of SiO2 (amorphous and quartz) and feldspars at high pH values was ...

Pergamon-Elsevier Science Ltd2022

Uncertainty analyses of spent nuclear fuel decay heat calculations using SCALE modules

Andreas Pautz, Dimitri Rochman, Stefano Caruso

Decay heat residuals of spent nuclear fuel (SNF), i.e., the differences between calculations and measurements, were obtained previously for various spent fuel assemblies (SFA) using the Polaris module of the SCALE code system. In this paper, we compare dec ...

2021

Structural performance and mechanical properties investigation of spent nuclear fuel rods under static and dynamic bending loads

Efstathios Vlassopoulos

Currently, most Spent Nuclear Fuel (SNF) is kept safely in storage either at on-site facilities or at centralized interim storage sites. Moreover, many countries face delays in implementing their waste management programmes for SNF and high-level waste dis ...

EPFL2021

Optimisation of used nuclear fuel canister loading using a neural network and genetic algorithm

Andreas Pautz, Hakim Ferroukhi, Dimitri Rochman, Alexander Vasiliev

This paper presents an approach for the optimisation of geological disposal canister loadings, combining high resolution simulations of used nuclear fuel characteristics with an articial neural network and a genetic algorithm. The used nuclear fuels (produ ...

SPRINGER LONDON LTD2021

Growth and viability of microorganisms in bentonite and their potential activity in deep geological repository environments

Niels Burzan

Radioactive waste is among the most dangerous anthropogenic waste and its safe disposal is a challenging multi-generational task. Many nations have sought for the peaceful application of nuclear fission for the reliable production of electric energy to pow ...

EPFL2021

Interaction between BaCO3 and OPC/BFS composite cements at 20 degrees C and 60 degrees C

Validation of spent nuclear fuel decay heat calculations using Polaris, ORIGEN and CASMO5

Data-Driven Predictive Models: Calculational Bias in Characterization of Spent Nuclear Fuel

Delayed Hydride Cracking in Irradiated and Unirradiated Zircaloy-2 Cladding

Growth and persistence of an aerobic microbial community in Wyoming bentonite MX-80 despite anoxic in-situ conditions

Effect of different ions on dissolution rates of silica and feldspars at high pH

Uncertainty analyses of spent nuclear fuel decay heat calculations using SCALE modules

Structural performance and mechanical properties investigation of spent nuclear fuel rods under static and dynamic bending loads

Optimisation of used nuclear fuel canister loading using a neural network and genetic algorithm

Growth and viability of microorganisms in bentonite and their potential activity in deep geological repository environments

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Validation of spent nuclear fuel decay heat calculations using Polaris, ORIGEN and CASMO5

Data-Driven Predictive Models: Calculational Bias in Characterization of Spent Nuclear Fuel

Delayed Hydride Cracking in Irradiated and Unirradiated Zircaloy-2 Cladding

Growth and persistence of an aerobic microbial community in Wyoming bentonite MX-80 despite anoxic in-situ conditions

Effect of different ions on dissolution rates of silica and feldspars at high pH

Uncertainty analyses of spent nuclear fuel decay heat calculations using SCALE modules

Structural performance and mechanical properties investigation of spent nuclear fuel rods under static and dynamic bending loads

Optimisation of used nuclear fuel canister loading using a neural network and genetic algorithm

Growth and viability of microorganisms in bentonite and their potential activity in deep geological repository environments

Investigation on the effect of eccentricity for fuel disc irradiation tests

Investigation on the effect of eccentricity for fuel disc irradiation tests