Search Results - "GLATZ, J. P"
-
1
Demonstration of a SANEX Process in Centrifugal Contactors using the CyMe4-BTBP Molecule on a Genuine Fuel Solution
Published in Solvent extraction and ion exchange (01-03-2009)“…Efficient recovery of minor actinides from a genuine spent fuel solution has been successfully demonstrated by the CyMe 4 -BTBP/DMDOHEMA extractant mixture…”
Get full text
Journal Article -
2
Electrorefining of irradiated experimental metallic fuel at high lanthanides concentration in the LiCl–KCl electrolyte
Published in Journal of nuclear materials (01-12-2019)“…An electrorefining process for homogeneous group-selective recovery of actinides from metallic nuclear fuel in molten LiCl–KCl has been investigated. The…”
Get full text
Journal Article -
3
On the electrochemical formation of Pu–Al alloys in molten LiCl–KCl
Published in Journal of nuclear materials (2012)“…► Pu–Al alloys formation in a molten LiCl–KCl eutectic. ► Electrochemical reduction of Pu 3+ on Al and inert W cathodes from 400 °C to 550 °C. ► Pu reduction…”
Get full text
Journal Article -
4
On the formation of U–Al alloys in the molten LiCl–KCl eutectic
Published in Journal of nuclear materials (15-08-2008)“…U–Al alloy formation has been studied in the temperature range of 400–550 °C by electrochemical techniques in the molten LiCl–KCl eutectic. Cyclic voltammetry…”
Get full text
Journal Article -
5
Separation of actinides from irradiated An–Zr based fuel by electrorefining on solid aluminium cathodes in molten LiCl–KCl
Published in Journal of nuclear materials (01-04-2015)“…•Electrorefining process in molten LiCl-KCl using solid Al electrodes was demonstrated.•High separation factors of actinides over lanthanides were…”
Get full text
Journal Article -
6
Electrochemistry of uranium in molten LiF–CaF2
Published in Journal of nuclear materials (01-11-2012)“…This article is focused on the electrochemical behaviour of U ions in molten LiF–CaF2 (79–21wt.%) eutectic. On a W electrode, U(III) is reduced in one step to…”
Get full text
Journal Article -
7
Electrochemical reduction of CerMet fuels for transmutation using surrogate CeO2-Mo pellets
Published in Journal of nuclear materials (01-08-2017)“…One of the concepts chosen for the transmutation of minor actinides in Accelerator Driven Systems or fast reactors proposes the use of fuels and targets…”
Get full text
Journal Article -
8
Actinides recovery from irradiated metallic fuel in LiCl–KCl melts
Published in Journal of nuclear materials (01-11-2015)“…Electrorefining of irradiated metallic fuels was successfully demonstrated: Actinides (U, Pu, Np, Am and Cm) in the fuels were dissolved in LiCl–KCl melts with…”
Get full text
Journal Article -
9
Anodic dissolution of irradiated metallic fuels in LiCl–KCl melt
Published in Journal of nuclear materials (01-09-2014)“…Electrorefining is the main step in pyro-process of spent nuclear fuels, where actinides are recovered and separated from fission products. In the present…”
Get full text
Journal Article -
10
Electrochemistry of thorium in LiCl–KCl eutectic melts
Published in Electrochimica acta (30-09-2007)“…This work presents a study of the electrochemical properties of Th chloride ions dissolved in a molten LiCl–KCl eutectic, in a temperature range of 693–823 K…”
Get full text
Journal Article -
11
Study of thermodynamic properties of Np–Al alloys in molten LiCl–KCl eutectic
Published in Journal of nuclear materials (01-10-2009)“…Pyrochemical methods are investigated worldwide within the framework of Partitioning and Transmutation concepts for spent nuclear fuel reprocessing…”
Get full text
Journal Article -
12
Electrochemical behaviour of americium ions in LiCl–KCl eutectic melt
Published in Electrochimica acta (20-05-2006)“…This work presents a study on the electrochemical properties of AmCl 3 in a molten LiCl–KCl eutectic, at a temperature range of 733–833 K. Transient…”
Get full text
Journal Article -
13
Zirconium behaviour during electrorefining of actinide-zirconium alloy in molten LiCl-KCl on aluminium cathodes
Published in Journal of nuclear materials (15-04-2016)“…A pyrochemical electrorefining process for the recovery of actinides from metallic nuclear fuel based on actinide-zirconium alloys (An–Zr) in a molten salt is…”
Get full text
Journal Article -
14
Investigation of electrorefining of metallic alloy fuel onto solid Al cathodes
Published in Journal of nuclear materials (15-01-2007)“…This work concerned the electrorefining of UZr and UPuZr alloys on a solid aluminium cathode, in the LiCl–KCl eutectic melt containing U3+, Pu3+, Np3+, Zr2+ or…”
Get full text
Journal Article Conference Proceeding -
15
Recovery of actinides from actinide–aluminium alloys by chlorination: Part II
Published in Journal of nuclear materials (01-04-2014)“…A chlorination route is being investigated for recovery of actinides from actinide–aluminium alloys, which originate from pyrochemical recovery of actinides…”
Get full text
Journal Article -
16
Recovery of actinides from actinide–aluminium alloys by chlorination: Part I
Published in Journal of nuclear materials (01-07-2011)“…Pyrochemical processes in molten LiCl–KCl are being developed in ITU for recovery of actinides from spent nuclear fuel. The fuel is anodically dissolved to the…”
Get full text
Journal Article -
17
Exhaustive electrolysis for recovery of actinides from molten LiCl–KCl using solid aluminium cathodes
Published in Journal of radioanalytical and nuclear chemistry (01-12-2010)“…An electrorefining process in molten chloride salts using solid aluminium cathodes is being developed in Institute for Transuranium Elements in order to…”
Get full text
Journal Article -
18
Separation of plutonium from lanthanum by electrolysis in LiCl–KCl onto molten bismuth electrode
Published in Journal of nuclear materials (15-04-2005)“…This work presents a study on the electroseparation of plutonium from lanthanum using molten bismuth electrodes in LiCl–KCl eutectic at 733K. The reduction…”
Get full text
Journal Article -
19
The use of the electrochemical quartz crystal microbalance (EQCM) in corrosion studies of UO2 thin film models
Published in Journal of nuclear materials (01-12-2011)Get full text
Journal Article -
20
Instant release fraction and matrix release of high burn-up UO2 spent nuclear fuel: Effect of high burn-up structure and leaching solution composition
Published in Journal of nuclear materials (01-08-2012)“…Two weak points in Performance Assessment (PA) exercises regarding the alteration of Spent Nuclear Fuel (SNF) are the contribution of the so-called Instant…”
Get full text
Journal Article