D. Serrano‐Purroy

发表

Recovery of minor actinides from HLLW using the DIAMEX process

J. Glatz, R. Malmbeck, P. Baron, 2005 .

Demonstration of a SANEX Process in Centrifugal Contactors using the CyMe4‐BTBP Molecule on a Genuine Fuel Solution

A. Geist, G. Modolo, J. Glatz, 2009 .

Demonstration of a TODGA based Extraction Process for the Partitioning of Minor Actinides from a PUREX Raffinate

G. Modolo, J. Glatz, R. Malmbeck, 2009 .

First demonstration of a centrifugal solvent extraction process for minor actinides from a concentrated spent fuel solution

G. Modolo, J. Glatz, C. Madic, 2005 .

DIAMEX Counter‐Current Extraction Process for Recovery of Trivalent Actinides from Simulated High Active Concentrate

G. Modolo, R. Malmbeck, P. Baron, 2007 .

Towards an optimized flow-sheet for a SANEX demonstration process using centrifugal contactors

G. Modolo, J. Glatz, R. Malmbeck, 2009 .

Dissolution experiments of commercial PWR (52 MWd/kgU) and BWR (53 MWd/kgU) spent nuclear fuel cladded segments in bicarbonate water under oxidizing conditions. Experimental determination of matrix and instant release fraction

D. Serrano‐Purroy, J. Pablo, E. González-Robles, 2015 .

Reducing uncertainties affecting the assessment of the long-term corrosion behavior of spent nuclear fuel.

J. Glatz, D. Serrano‐Purroy, T. Fanghänel, 2013, Inorganic chemistry.

Contribution of phases segregated from the UO2 matrix to the release of radionuclides from spent nuclear fuel and duration of the Instant Release Fraction (IRF)

J. de Pablo, D. Serrano‐Purroy, J. Pablo, 2020 .

Dynamic leaching studies of 48 MWd/kgU UO2 commercial spent nuclear fuel under oxic conditions

F. Clarens, J. Glatz, D. Serrano‐Purroy, 2013 .

Instant release fraction and matrix release of high burn-up UO2 spent nuclear fuel: Effect of high burn-up structure and leaching solution composition

F. Clarens, J. Glatz, D. Serrano‐Purroy, 2012 .

Leaching of 53 MW/d kg U spent nuclear fuel in a flow-through reactor

J. de Pablo, F. Clarens, J. Glatz, 2009 .

Instant release of fission products in leaching experiments with high burn-up nuclear fuels in the framework of the Euratom project FIRST- Nuclides

E. Curti, D. Serrano‐Purroy, Z. Hózer, 2017 .

Advanced aqueous reprocessing in P&T strategies: Process demonstrations on genuine fuels and targets

C. Apostolidis, J. Glatz, G. Pagliosa, 2004 .

Towards a DIAMEX process using high active concentrate. Production of genuine solutions

G. Modolo, J. Glatz, R. Malmbeck, 2005 .

An Automated SeaFAST ICP-DRC-MS Method for the Determination of 90Sr in Spent Nuclear Fuel Leachates

D. Serrano‐Purroy, S. Millet, S. Van Winckel, 2020, Molecules.

Influence of the interpellet space to the Instant Release Fraction determination of a commercial UO2 Boiling Water Reactor Spent Nuclear Fuel

D. Serrano‐Purroy, J. Pablo, I. Casas, 2018 .

In fl uence of the interpellet space to the Instant Release Fraction determination of a commercial UO 2 Boiling Water Reactor Spent Nuclear Fuel

D. Serrano‐Purroy, J. Pablo, I. Casas, 2017 .

Molybdenum release from high burnup spent nuclear fuel at alkaline and hyperalkaline pH

J. Llorca, F. Clarens, D. Serrano‐Purroy, 2023, Nuclear Engineering and Technology.

Instant release fraction corrosion studies of commercial UO2 BWR spent nuclear fuel

D. Serrano‐Purroy, J. Pablo, I. Casas, 2017 .

Dissolution of high burn-up spent nuclear fuel at high-pH

F. Clarens, D. Serrano‐Purroy, I. Casas, 2023, Radiochimica Acta.