Projet SAMOFAR Coordinateur scientifique : Jan Leen Kloosterman (TU DELFT) Manager : Karin van der Graaf (TU Delft) WP1 : Integral safety approach and.

Slides:



Advertisements
Similar presentations
Properties of Elements
Advertisements

Current status of R&D on MSR fuel salt reprocessing
Study of Electrochemical Processes for Separation of the Actinides and Lanthanides in Molten Fluoride Media R. Tulackova (Zvejskova), K. Chuchvalcova Bimova,
DICTRA Mobility Database for Zr alloys C. Toffolon-Masclet, C. Desgranges and J.C. Brachet CEA Saclay, France C. Toffolon-Masclet et al., CALPHAD XLI,
1 Nuclear Division - GLF FP6 - Proposal for a Specific Targeted Research Project on Innovative Technologies for the Sodium cooled fast Reactor ITSR - FP6.
LEFT CLICK OR PRESS SPACE BAR TO ADVANCE, PRESS P BUTTON TO GO BACK, PRESS ESC BUTTON TO END LEFT CLICK OR PRESS SPACE BAR TO ADVANCE, PRESS P BUTTON.
Investigation of "dry" recriticality of the melt during late in-vessel phase of severe accident in Light Water Reactor D.Popov, KNPP, BG O.Runevall, KTH,
Nuclear Fuel Production Fissile Nuclei Uranium and Plutonium 235 U 239 Pu.
Honors Biology Mr. Luis A. Velázquez
The Nature of Molecules
Thorium molten salts, theory and practice Paul Madden (Oxford, UK) & Mathieu Salanne & Maximilien Levesque (UPMC, France) Euratom Project, 13 Groups Molten.
Radioactive Nuclides in Japan
Fundamentals of Neutronics : Reactivity Coefficients in Nuclear Reactors Paul Reuss Emeritus Professor at the Institut National des Sciences et Techniques.
16-1 Voltammetry Electrochemistry techniques based on current (i) measurement as function of voltage (E appl ) Working electrode §(microelectrode) place.
Types of reactors.
3F03-Exam Review Exam Review April KC Availability: Exam review Tues April 7 th 11:00-1:00 Wed April 8 th 9:30-12:30 Thurs April 9 th 11:00-1:00.
ULB Nuclear Fuel Cycle Nuclear Fuel reprocessing Sellafield - UK.
1 I. STRUCTURE OF SUBSTANCES I.3. The order of filling orbitals.
1 G. Ducros International VERCORS Seminar, October 15-16th, 2007 – Gréoux les Bains, France FP release from VERCORS tests: semi-volatile, low-volatile.
Chemical Families. Groups of Elements   Lanthanides Li 3 He 2 C6C6 N7N7 O8O8 F9F9 Ne 10 Na 11 B5B5 Be 4 H1H1 Al 13 Si 14 P 15 S 16 Cl.
Organization of The Periodic Table Mrs. Russotto.
18-1 RFSS: Lecture 17 Forensics in Nuclear Applications From Nuclear Forensics Analysis Readings §Glasstone: Effects of Nuclear Weapon Outline Isotopics.
FAST MOLTEN SALT REACTOR –TRANSMUTER FOR CLOSING NUCLEAR FUEL CYCLE ON MINOR ACTINIDES A.Dudnikov, P.Alekseev, S.Subbotin.
1-1 Lecture 1: RDCH 702 Introduction Class organization §Outcomes §Grading Chart of the nuclides §Description and use of chart §Data Radiochemistry introduction.
Slide 1 Author D:/DATA/POWERPNT/Hugon/InnconceptsFP5toFP6 INNOVATIVE CONCEPTS FOR NUCLEAR FISSION ENERGY: FROM FP5 TO FP6 Michel Hugon DG RTD-J-4.
Liquid Fluoride Thorium Reactors. Overview Introduction to nuclear reactors Fundamentals of LFTR (Liquid Fluoride Thorium Reactors) Economic viability.
Materials Integration by Fission Reactor Irradiation and Essential Basic Studies for Overall Evaluation Presented by N.Yoshida and K.Abe At the J-US Meeting,
Periodic Table Li 3 He 2 C6C6 N7N7 O8O8 F9F9 Ne 10 Na 11 B5B5 Be 4 H1H1 Al 13 Si 14 P 15 S 16 Cl 17 Ar 18 K 19 Ca 20 Sc 21 Ti 22 V 23 Cr.
What are characteristics for: – Metal – Nonmetal – Metalloid.
FP 6 Integrated Project: FUETRA Proposal TWG-ADS Roadmap, Fuel Cycle sub-group report recommendations, Fuel Cycle studies (CEA, ITU, NEA...) EFTTRA collaboration.
KIT – University of the State of Baden-Wuerttemberg and National Research Center of the Helmholtz Association Institute for Neutron Physics and Reactor.
Oxygen Potential in High Burnup LWR Fuel using Themochimica in MOOSE/BISON Theodore M. Besmann.
Groups in the Periodic Table. Alkali Metals  Group # 1  1 valence electron  Properties: very soft and shiny, low density (some float in water), most.
1DEN/CAD/DTN/DIR Genova 2010 April 22nd LEADER WP6 Task 6.3 Assessment, validation and adaptation of oxygen control and purification strategy (CEA-5, ENEA-1,
The Uranium Fuel Cycle Robert Tsai November 21, 2006.
Workshop SERPENT and Multiphysics – February 2015 E. MERLE-LUCOTTE Professor at CNRS-IN2P3-LPSC / Grenoble INP - PHELMA For the MSFR team - M. ALLIBERT,
A report on the ALISIA Information Day
Dr. M. Brovchenko & Prof. E. Merle-Lucotte LPSC/IN2P3/CNRS - Grenoble INP, France EVOL Winter School 04/11/2013 in Orsay, France.
History of the Periodic Table. “Early chemists describe the first dirt molecule.”
Metals Many of the objects around you contain metals. What are the objects that will set off the metal detector? Metals.
I. STRUCTURE OF SUBSTANCES
S2 SCIENCE CHEMICAL REACTIONS
Transmutation of spent nuclear fuel
Uranium Enrichment Louis Croquette.
3rd Meeting of the Norwegian Thorium Report Committee
A First Course on Kinetics and Reaction Engineering
Boreskov Institute of Catalysis,
RDCH 702: Lecture 10 Radiochemistry in reactors
CHEM 312: Lecture 16 Radiochemistry in reactors Part 2
THE HALOGENS.
Aqueous and Pyrochemical reprocessing of thorium fuel
CHEM 312: Lecture 19 Forensics in Nuclear Applications
RFSS: Lecture 16 Radiochemistry in reactors
New radiochemical technologies of spent nuclear fuel reprocessing
THE HALOGENS.
KS4 Chemistry The Periodic Table.
Trends of the Periodic Table
Periodic Table Kelter, Carr, Scott, Chemistry A Wolrd of Choices 1999, page 74.
AQA GCSE Atomic structure and periodic table part 2
Halogens.
Adsorption techniques for gas purification
A First Course on Kinetics and Reaction Engineering
Edexcel Topic 1: Key concepts in chemistry
RF activity in frame of IEA Fusion Neutronics 2001 D
HALOGENS.
Decommissioning of Spent Nuclear Fuel Ponds   University of Leeds Student Sustainability Research Conference 2019, Leeds, UK. Alexander P. G. Lockwood,
Electron Configurations and the Periodic Table
Introduction to the session Reactor Models
Presentation transcript:

Projet SAMOFAR Coordinateur scientifique : Jan Leen Kloosterman (TU DELFT) Manager : Karin van der Graaf (TU Delft) WP1 : Integral safety approach and system integration E. Merle (CNRS/IN2P3/LPSC) WP2 : Physical and chemical properties required for safety analysis O. Benes (JRC) WP3 : Experimental proof of shut-down and decay heat removal concepts M. Ricotti (CIRTEN) WP4 : Accidental Transients D. Lathouwers (TU Delft) WP5 : Safety evaluation of the chemical plant S. Delpech (CNRS/IN2P3/INO) WP6 : Training, education and dissemination of results J.L. Kloosterman (TU Delft) WP7 : Project management K. Van der Graaf (TU Delft)

Principal objectif du WP5 Etudier de la chimie du traitement du sel combustible, proposer un design pour l’unité de retraitement et étudier les besoins en sûreté de l’unité. Partenaires du WP5: - CNRS - ITU - CEA - CINVESTAV

Extraction réductrice Extraction réductrice Schéma de traitement Matière fissile, Np et déchets Etape 3 Désextraction Ln dans LiCl-LiF et précipitation Ln2O3 déchets Bullage de gaz Xe, Kr, … Métaux nobles Cœur du réacteur LiF-ThF4-(UF4-UF3) Etape 5 Contrôle du potentiel redox et composition U/Th Etape 1 Fluoration Extraction U, Np, Pu, I, Tc, Te Nb, Mo, Se … Etape 2.A Extraction réductrice An (Bi-Li1) déchets Etape 2.C Désextraction An dans LiF-ThF4 propre Etape 2.B Extraction réductrice Ln (Bi-Li2) Etape 4 Régénération de la composition des sels et des phases métalliques

WP5 Task 5.1 Evaluation of nuclide inventory at various stages in the chemical plant (CNRS, ITU) A reprocessing scheme has been established in the EVOL project. The different steps have been validated both by bibliographic study and experimental determinations. The determination of the nuclide inventory at various stages of the chemical plant requires the knowledge of basic data such as activity coefficients and redox potential values. This task is dedicated to the determination of fundamental data such as activity coefficients both in metallic and salt phases (CNRS, ITU), the calculation of the separation/extraction efficiencies and the elemental inventory. The experimental validation of the reductive extraction between LiF-ThF4/Bi-Li will be done and the extraction kinetic will be studied for actinides (ITU) and lanthanides (CNRS).

WP5 Task 5.2 Coupling of neutronic and reprocessing efficiencies (CNRS) The reprocessing efficiencies (Task 5.1) have to be coupled with the neutronics in order to determine the stage number of each reprocessing step, especially for the reductive extraction. The increase of the extraction stages can lead to an improve efficiency. The size of the chemical plant will depend on the number of stages. The fuel salt purity level (against fission products) required by neutronic calculations (realized in the WP1) helps to define a design for the chemical plant in relation with WP1 (CNRS).   Task 5.3 Evaluation of Re-criticality issues (CNRS, CEA) Calculation of criticality based on the nuclide inventory to avoid fissile concentration in a part of the chemical plant (in relation with task 5.1) (CNRS, CEA).

WP5 Task 5.4 Design and safety of the chemical plant (CNRS, CEA, ITU) The radioprotection of the chemical plant will be calculated based on the nuclide inventory at each stage of the reprocessing (in relation with task 5.1, 5.3 and 5.4) (CEA, CNRS, ITU). Two reprocessing steps require gas flows. The on-line reprocessing which consists in injection of He the reactor core to extract the gaseous fission products and the noble metal. Management of the gas and of the elements extracted by this step has to be studied from safety point of view. Calculations of residual heat, radioactivity decrease in the tanks and size of the tanks have to be performed (CNRS, CEA). The second step which requires gas flow is the fluorination step. Fluorine is injected in the molten salt to extract U, Np and several FP. The gas extracted is adsorbed on NaF traps heated at different temperatures to perform the separation. The gases are separated and reduced by reaction with hydrogen gas. The separation efficiency of this step will be determined based on the experimental feedback from ORNL available.

WP5 Task 5.5 Material issues (CNRS, CINVESTAV)and KI (collaboration) The compatibility of materials in the several structures of the chemical plant will be assessed in this task. Recommendations on the material structure will be given especially for the fluorination plant, the reductive extraction line and the lanthanide oxide precipitation tank. Ni-based alloys with ZrO2 coatings will be studied to evaluate their compatibility with non active fluoride molten salts (CINVESTAV) and active salts (CNRS). For compatibility with liquid Bi pools, studies to evaluate the resistance of Mo will be done (CNRS, KI).

Méthodologie

Méthodologie CNRS CNRS - ITU CNRS - CEA

Méthodologie

Méthodologie pour le calcul de l’inventaire Estimation des fonctions de transfert d’une phase à une autre pour tous les éléments du cœur. - Bibliographie (rapports ORNL) - Partie expérimentale (choix de certains éléments majeurs) - Détermination de données fondamentales (coefficients d’activité, potentiels redox) - Etudes cinétiques

       00 00

THANKS FOR YOUR ATTENTION