Stainless steel release rate evaluation in ITER operating conditions P. Schindler- V. Blet CEA/DEN/DTN/STRI/LTCD Cadarache France.

Slides:



Advertisements
Similar presentations
"Jožef Stefan" Institute, Dept. of Surface Engineering and Optoelectronics Slovenian Fusion Association (SFA). MHEST Deuterium retention in ITER -grade:
Advertisements

Hongjie Zhang Purge gas flow impact on tritium permeation Integrated simulation on tritium permeation in the solid breeder unit FNST, August 18-20, 2009.
Primary Water Chemistry
Behaviour of Ruthenium in high temperature oxidising conditions Ulrika Backman & Ari Auvinen & Jorma Jokiniemi & Maija Lipponen& Riitta Zilliacus SAFIR.
Pre-Filming Method of Reducing Metal Release from Alloy 690 for SG in Primary Water of PWR 2009 ISOE Asian ALARA Symposium Aomori September 9, 2009 Sumitomo.
IAEA Sources of Radiation Nuclear Fuel Cycle – Enrichment Day 4 – Lecture 6(2) 1.
Be/FS joining for ITER TBM Ryan Matthew Hunt FNST Meeting August 18, 2009 A collaboration between UCLA, SNL-Livermore, Brush-Wellman, Axsys Inc. and Bodycote.
1 WASTE CHARACTERIZATION METHODS S. Vanderperre Belgatom Vanderperre, Belgatom, chapter 7.
Cr and Co release reduction from stainless steels in PWR and BWR 2009 ISOE Asia ALARA Symposium Aomori EPRI Radiation Protection Conference September 9,
M. GIRARD – CEA / EFDA MEETING - CADARACHE, January th, 2005 Task TW4 – TSS - SEA 5.5 Validation of EU Safety Computer codes Validation of PACTITER.
Kick off meeting EFDA Task TW6-TSS-SEA2.1 Garching 10th/10/2006 ENEA Engineering approach of the potential accident scenario leading to the worst release.
Chromatography CHEMISTRY Chromatography Chromatography is a technique for separating species based on physical or chemical properties. Usually.
May 22nd & 23rd 2007 Stockholm EUROTRANS: WP 1.5 Task Containment Assessment IP-EUROTRANS DOMAIN 1 Design WP 1.5 Safety Assessment of the Transmutation.
Overview of radioactivity vs. chemical toxicity issues for Overview of radioactivity vs. chemical toxicity issues for potential target materials presented.
ARIES Meeting General Atomics, February 25 th, 2005 Brad Merrill, Richard Moore Fusion Safety Program Pressurization Accidents in ARIES-CS.
1 Wilfrid Farabolini 23 feb. 04Direction de l’Energie Nucléaire Tritium Control A Major Issue for a Liquid Metal Blanket.
Safety assessment for Safety assessment for potential target materials: radioactivity vs. chemical toxicity presented by: Susana Reyes ARIES Group Meeting.
Induced Activity Calculations in Support of D&D Activities at SLAC Joachim Vollaire, Radiation Protection Department.
Oxidation of Graphite Walls: Preliminary Results from SOMBRERO Safety Analysis S. Reyes, J. F. Latkowski Lawrence Livermore National Laboratory Laser IFE.
1 THERMAL & MECHANICAL PRELIMINARY ANALYSIS ELM COIL ALTERNATE DESIGN Interim Review July 26-28, 2010 In-Vessel Coil System Interim Review – July 26-28,
Corrosion of Ceramics By Brian Cox For ME 406 Professor Sandwith Professor Kent.
Experimental Class 5 Steam Generator
Tokamak GOLEM (for fusion education) Tokamak GOLEM just in operation (plasma in the chamber) major radius R = 0.4 m plasma current < 10 kA toroidal magnetic.
Lead Technology Task 6.2 Materials for mechanical pump for HLM reactors M. Tarantino – ENEA Work Package Meeting – ENEA Bologna, November 17th, 2010.
Mechanical Design Of Process Equipment.
RIC 2009 Thermal Hydraulics & Severe Accident Code Development & Application Ghani Zigh USNRC 3/12/2009.
Finite Elements Modelling of Tritium Permeation
1 DTN / PACTITER - Kick off meeting of the contracts TW5-TSS-SEA5.6, Cadarache 26/10/05 Necessary work for PACTITER Development and validation F. Dacquait*,
Vessel Vacuum Tritium Permeation & PbLi/Water Safety Issues Paul Humrickhouse INL Fusion Safety Program October 13 th -14 th, 2011 ARIES Meeting Gaithersburg,
Handling of Future Human Actions in the safety assessment SR-Site Eva Andersson.
Lead Technology Task 6.2 Materials for mechanical pump for HLM reactors M. Tarantino, I. Di Piazza, P. Gaggini Work Package Meeting Karlsruhe, November.
Completion of Water-Cooled Backup Study Eric Pitcher TAC-10 November 5, 2014.
,Yalta,17-th Symposium of AER1 IMPACT OF CHANGED FUEL PERFORMANCES ON SAFETY BARRIER EFFECTIVENESS AT NORMAL OPERATION OF NPP WITH VVER A.V.
M. Yoda, S. I. Abdel-Khalik, D. L. Sadowski, B. H. Mills, and J. D. Rader G. W. Woodruff School of Mechanical Engineering Correlations for the Plate Divertor.
EUROTRANS – DM1 ENEA Activities on EFIT Safety Analysis ENEA – FIS/NUC Bologna - Italy WP5.1 Progress Meeting Tractebel / Brussels, March 17, 2006 G. Bandini,
Mechanical and fluidic integration of scintillating microfluidic channels into detector system 1 Davy Brouzet 10 th September 2014.
Experimental part: Measurement the energy deposition profile for U ions with energies E=100 MeV/u - 1 GeV/u in iron and copper. Measurement the residual.
HIGH HEAT FLUX PEAKING FACTORS AND ENHANCEMENT Ronald D. Boyd Sr., PhD, PE, PI Distinguished Professor, Honeywell Professor, Director of the Thermal Science.
1DTN / STRI /LTCD 28/03/06 Chemistry aspects of the ITER cooling water : impact on the experiments in the CEA loops DEN/CAD/DTN.
Hazard Categorization Reduction via Nature of the Process Argument Chelise Van De Graaff J. Todd Taylor Chad Pope, PhD, PE Idaho National Laboratory.
REDUCING SCALE DEPOSITION BY PHYSICAL TREATMENT Sungmin Youn and Professor X. Si, Calvin College REDUCING SCALE DEPOSITION BY PHYSICAL TREATMENT Sungmin.
 The symbol of chromium is Cr  Scientist Louis Nicolas vauquelin discovered chromium in 1797  The origin of its name is from the Greek word name chorma.
ERMSAR 2012, Cologne March 21 – 23, 2012 Main results of the ISTC Project #3876 “Thermo- Hydraulics of U-Zr-O Molten Pool under Oxidising Conditions in.
ERMSAR 2012, Cologne March 21 – 23, 2012 Experimental Determination and Analysis of Iodine Mass Transfer Coefficients from THAI Test Iod-23 K. FISCHER,
Solid Targets for Neutron Spallation Sources Eric Pitcher Los Alamos National Laboratory Presented to: AHIPA Workshop October 20, 2009.
PRESENTATION OF CFD ACTIVITIES IN CV GROUP Daniel Gasser.
Vincent MASSAUT Meeting 28/03/ Meeting on ITER water chemistry and implication on the PACTITER development / CORELE experiments Garching / Cadarache.
The analytical techniques most widespread for certification in the iron and steel industry are X-ray Fluorescence Spectrometry (XRF), Arc/Spark Optical.
Analysis on the amount of graphite dust deposited on steam generator of HTGR Wei Peng 1, Tian-qi Zhang 1, Su-yuan Yu 2 * 1 Institute of Nuclear and new.
IAEA-TM 02/03/2005 1G. Falchetto DRFC, CEA-Cadarache Association EURATOM-CEA NON-LINEAR FLUID SIMULATIONS of THE EFFECT of ROTATION on ION HEAT TURBULENT.
1 G. Cambi, D.G. Cepraga, M. Frisoni Enea & Bologna University Team OSIRIS neutronic and activation simulation with Scalenea-ANITA in support of PACTITER/CORELE.
Neutron double differential distributions, dose rates and specific activities from accelerator components irradiated by 50 – 400 MeV protons F. Cerutti.
ISOE Asian Technical Center 2005ALARA Mini-Workshop Fugen Nuclear Power Station, JAEA- 1 Demonstration of Zinc Injection Technique in Fugen Nuclear Power.
Kick Off Meeting of the contracts TW5-TSS-SEA5.6., TW5-TSS-SEA5.5.D8-9 - CEA Cadarache. October 26th, 2005 Associazione EURATOM ENEA sulla FUSIONE Task.
OBJECTIVE 3 Students will identify that density is a fundamental property of matter. Changes in pressure and temperature can change the density of a material.
Chemistry 18.1.
Date of download: 10/13/2017 Copyright © ASME. All rights reserved.
Date of download: 12/30/2017 Copyright © ASME. All rights reserved.
Pressurized Water Reactor
Modified Design of Aries T-Tube Divertor Concept
Stainless Steel Water Well Casing.
Chapter Three Sections 3.1 through 3.4
SAFETY AND SITTING ASSESSMENT FOR NPPs DEPLOYMENT IN INDONESIA
Phoebus 2A, Nuclear Thermal Element
Chemistry 18.1.
Rates of Reaction 18.1 The heat given off by the corrosion reaction of an iron-magnesium alloy with salt water can produce a hot meal. The rate of reaction.
I. Di Piazza (ENEA), R. Marinari, N. Forgione (UNIPI), F
Preliminary Analysis of Loss of Vacuum Events in ARIES-RS
TRL tables: power conversion and lifetime
Chemistry 18.1.
Presentation transcript:

Stainless steel release rate evaluation in ITER operating conditions P. Schindler- V. Blet CEA/DEN/DTN/STRI/LTCD Cadarache France

In order to validate this code, an experimental program has been launched in the CORELE test facility in ITER representative conditions. OBJECTIVE The Activated Corrosion Products in the Tokamak Cooling Water Systems TCWS can be of major concern as contributor to the Occupational Radiological Exposure during normal operation and to the source term in case of accident. The PACTITER code, an adaptation of the PACTOLE code developed for Pressure Water Reactor, has been used for predicting the ACP activities in the various TCWS.

CORELE LOOP OUTLINE

Release Rate Measurement Radioactive ions released in the fluid Measurement of the activity A level for each radionuclide  spectrometry Irradiated tubes Purified fluid Ion-exchange resins Pure Water

Influence of temperature on global release rates At 150°C the release rates are : - 22 mg/dm²/month for a primary coolant velocity of 4.12 m/s - 36 mg/dm²/month for a primary coolant velocity of 1.02 m/s. Coherent with PACTITER simulation of 23 mg/dm²/month at 150°C and 1m/s.

Influence of temperature on global release rates At 100°C the release rates are : –Less than 2.8 mg/dm²/month for a fluid velocity of 1 m/s. –Below detection limit for 4m/s Coherent with the existence of a solid diffusion barrier which limits corrosion

CONCLUSION – TEST 2004 In ITER operating conditions, 316 SS release is limited : Principally by the thermally activated solid diffusion of oxygen in a surface barrier (possibly as chromite) which reduces the potential source of release by corrosion, The mass diffusion which depends solely on Reynolds number instead of the velocity at the interface fluid/solid Planned tests are in progress in order to : assess the existence of the energy of activation of the release rate (>180 kJ/mol ?) confirm the weak influence of velocity compared to the Reynolds number on the release rate. complete the validation of the code PACTITER by including the determination of Cu release rates (2006)

ITER TEST MATRIX

ITER CHEMICAL CONDITIONS