GENERAL PRESENTATION OF ICIT RM. VILCEA MAIN ACTIVITIES: o Isotopes separation at industrial pilot plants level; o Gases separation process, purification technologies and high-efficiency recuperative systems; o Cryogenic installation and technologies for separation, purification and gases liquefaction (argon, helium, hydrogen, carbon dioxide, nitrogen, oxygen); o Technologies for heavy water separation, technical analysis and tritium analysis; o Hydrogen and hydrogen fuel cells; o Business and technology incubator for research transfer; o Turbo molecular pumps, vacuum accessories, membrane for compressors, cryogenic pumps; o Heavy water etalons, depleted water; o Risk studies for chemical and petrochemical plants. NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010

GENERAL PRESENTATION OF ICIT RM. VILCEA RESEARCH ACTIVITIES NUCLEAR TRITIUMHEAVY WATER NON- NUCLEAR HYDROGEN AND FUEL CELLS ENVIRONMENT &LIFE SCIENCE NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010

ICIT Rm Valcea general strategy for R&D between is focused on the following objectives: o Romanian and European nuclear program (NPP, TRITIUM, HEAVY WATER) o Hydrogen and hydrogen fuel cells o Researches in the materials field o Environment and quality of life o Business and technology incubator for research transfer o Development of the infrastructure and services for technological transfer and innovation o Development of young researcher teams GENERAL STRATEGY NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010

PILOT PLANT FOR DEUTERIUM AND TRITIUM SEPARATION TRITIUM SEPARATION SYSTEM AT ICIT RM.VALCEA NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010

NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES o Helium liquefier - LINDE L5; o Hydrogen liquefier - PPH 100 (model A20 ); o Nitrogen liquefier - PPG; o Toughness testing stand with polystyrene foam as thermal insulator at 20K – 300K; o Experimental stand for tensile strength determination at 20K-700K; o Tritium permeability experimental stand; o Cryostats for tensile tests (round and plate samples); o Thermal treatment furnace; o Experimental stand for tritium endurance tests. CRYOGENIC LABORATORY TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010

NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES tritium maximum activity in heavy water: 30 Ci/kg maximum tritium inventory: 300,000 Ci quantity of heavy water annually processed : 2000 kg minimum deuterium concentration in feed water: 99.8 % water feed rate: 8 kg/h tritium inventory in CD: 200,000 Ci design service life: 30 years DESIGN DATES Tritium Removal and Storage Theoretical Models and Simulation of Isotopic Separation Process Experimental Facilities PILOT PLANT Theoretical Study of Catalytic Exchange Software for Simulation of processes: -Isotopic Exchange - Cryogenic Distillation Tritium StorageTritium Extraction TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010

NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES DETRITIATION TECHNOLOGY Chosen detritiation technology: LPCE – CD (Liquid Phase Catalytic Exchange – Cryogenic Distillation) Underlying technology: A) tritium transfer from water - by isotopic catalytic exchange B) tritium concentration - by cryogenic distillation C) tritium safe storage- (as metallic hidrides) TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010

NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES result of ICIT experience in detritiation systems: CTRF – Cernavoda Tritium Removal Facility Reducing of tritium activity from moderator and maintaining at 10 Ci/kg level Objective: tritium concentration 10 Ci/kg at maturity in time interval 3-4 years Feeding with heavy water with isotopic content between 5 and 99,8% D2O The final isotopic content in heavy water after detritiation - 99,95% Implement in existent building space LPCELPCE ELECTROLYZER RECOMBINATOR CD MODERATOR D2D2 DT DTO D2OD2O Storage O 2 -From electrolyze -Supplementary O2O2 D+T TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010

ICIT PILOT PLANT Catalytic isotopic exchange tritiated heavy water - deuterium, followed by cryogenic distillation P IEC CD Tritiated Feed Water Tritium Depleted Water D 2 Tritium Analysis System MONITORING AND SAFETY SYSTEMS Links between experimental modules for Tritium and Deuterium Separation Pilot Plant Tritium Storage System HR CD 1 Boiler O 2 Purifier Electrolyser H 2 O, HTO H 2, HTLPCE Column Heater Condenser Boiler H2OH2O O2O2 CD2 H2H2 HR – Helium refrigerator CD1, CD2 – Cryogenic distillation Potential combination of WDS and ISS at ITER WDS / ITER: LPCE ELECTROLYSES (PERMEATION) CRYOGENIC DISTILLATION WDS / ICIT LPCE PURIFICATION CRYOGENIC DISTILLATION Research activities/facilities for Fusion Technologies at ICIT Rm.Valcea NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010

ICIT – EURATOM/EFDA PROJECTS 1. SEPARATION TECHNOLOGIES FOR HYDROGEN ISOTOPES SYSTEM FOR TRITIUM EXTRACTION FROM TRITIATED HEAVY WATER. (TWO-TRIT/REM) 2. OPTIMISATION OF THE PACKAGE/CATALYST RATIO FOR THE SIMULTANEOUS TRANSFER OF TRITIUM AND DEUTERIUM IN A WATER DETRITIATION FACILITY. (JW0-FT-2.1) 3. ENDURANCE TEST FOR THE CATALYST- PACKAGE MIXTURE PROPOSED FOR WATER DETRITIATION SYSTEM AT JET USING SCK-CEN MIXTURE. (JW4-FT-2.20) 4. TRITIUM PERMEABILITY IN DIFFERENT MATERIALS AS A FUNCTION OF PARTIAL PRESSURE, TEMPERATURE AND CONCENTRATION.(NUC–INT–UT 4); 5. MECHANICAL DESIGN PACKAGE. DEVELOPMENT OF ITER PRM AND STANDARD PARTS CATALOGUES IN CATIA V5 FOR TRITIUM-CONTAINING SYSTEM AND COMPONENTS. (TW5-TTFD-TPI-51); 6. UPDATE OF ITER ISS-WDS PROCESS DESIGNTW6-TTFD-TPI-55; 7. UPGRADE OF GAMMA-RAY CAMERAS - NEUTRON ATTENUATORS.(KN3-G/ KN3-VC-NA / NUC-INT-F7); 8. ENDURANCE TESTS OF WDS COMPONENTS.(TW6-TTFD-TR64); 9. RESEARCH TRAINING NETWORK - „PREPARING THE ITER FUEL CYCLE“- CONTRACT NO (FU 06); 10. RESEARCH TRAINING NETWORK ”TRITIUM TECHNOLOGIES FOR THE FUSION FUEL CYCLE TRI-TOFFY “ 11. C4T/09/90/PMT - PRI – “DEVELOPMENT OF METHOD FOR HIGHLY TRITIATED WATER HANDLING IN ITER TRITIUM PLANT. PHASE 1”; 12. F4E-2010-GRT- 045 (PNS-VTP) FINALIZATION OF THE SYSTEM CAPACITY, ENHANCEMENTS STUDIES AND DETAILED DESIGN OF WDS COMPONENTS INCLUDING HAZOP STUDIES. NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010

MEMBERS OF THE CONSORTIUM Tri-Pla-CA Karlsruhe Institue of Technology, KIT; Commissariate d’Énergie Atomique, CEA Ente per le Nuove Tecnologie, l’Energia e l’Ambiente ENEA Ministry of Education and Research/Association EURATOM-MEdC/National Research and Development Institute for Cryogenic and Isotopes Technologies - ICIT Rm Valcea CONSORTIUM STRUCTURE F4E Others IO Industry MANAGEMENT SUPPORTING TEAM MANAGEMENT BODY PARTY LEADER COLLABORATION MANAGER WORK PACKAGE LEADERS PARTIES REPRESENTATIVES PARTIES REPRESENTATIVES KIT CEAENEA ICIT PARTIES STEERING COMMITTEE NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010

HYDROGEN AND FUEL CELLS The ICIT research is concentrated basically on the next directions: Hydrogen production by natural gas steam reformation Hydrogen purification by high and low shift reaction Hydrogen purification using dense and porous metallic membranes Proton Exchange Membrane Fuel Cells (PEMFCs) and PEM electrolyzers development New type of membranes, catalysts and gas diffusion layers synthesis and testing Fuel cells and electrolyzers improvement using Computational Fluid Dynamics (CFD) Proton Exchange Membrane Fuel Cells (PEMFCs) and PEM electrolyzers stacks development NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES ENVIRONMENT AND LIFE QUALITY ICIT Rm. Valcea supplies also public services, especially in the fields of environmental protection and food quality control, such as:  environmental monitoring and industrial products detection (using gas – chromatography and mass spectrometry)  physical-chemical analyses of liquid and solid samples (drinking water, industrial water, sparkling water, waste water from various processes, soil samples)  food quality control, alcoholic and non - alcoholic beverages analyses using GCMS systems ( gas- chromatograph - mass spectrometer system)  mass spectrometry analyses, IR spectrometry analyses and dens meter analyses applied to various products control BUSINESS AND TECHNOLOGICAL INCUBATOR TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010

PRODUCTS AND SERVICES Products: Pure and highly pure gases: (argon, hydrogen, nitrogen, oxygen, helium, methane, carbon dioxide); Welding gases; Gas mixtures for welding in controlled environment; Gas mixtures used for fire extinguishers; Pure gases used for analyses, calibration and checking of analysis instrumentation; Pure gases and gas mixtures used in the food industry; Special gas mixtures used in the calibration of internal combustion and continuous emission engines; Liquefied gases (nitrogen, hydrogen, argon); Deuterium depleted water Services: Expertise, technical assistance, technical solution and special equipments for heavy water production plants; Tightness tests on equipments and plants; Advanced vacuum for the equipments and assembly of plants; Isotopic and physical-chemical analyses; Technological transfer for innovating technologies and products; Software and IT optimizing for isotopic separation processes from the heavy water separation plants. NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010

STRUCTURE AND STAFF BREAKDOWN Breakdown by age (total 217):  53 employees < 35 years  69 employees years  82 employees years  13 employees >56 years Breakdown by qualification:  Nuclear Scientists/Engineers: 27  Non-Nuclear Scientists/Engineers: 64  Technical Staff: 96  Administration and Service: 30 PERSONNEL WITH HIGHER EDUCATION PhD Attendants 30% specialists 49% MD Attendants 2% Doctors 19% NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010

“Research & Development Activities as Support for Commissioning and Decommissioning and Operation of Tritium Removal Facilities (TRF)” Quality management plans and computer codes for procedures decommissioning of a TRF plant; Minimization of volume and radio toxicity of radioactive waste through: o Detritiation methods and techniques of materials ( metals; oils; catalyst, etc) from a TRF plant; o Treatment and conditioning of waste containing tritium and C-14; o Methods of tritium transport and storage o Investigation of materials properties from TRF plants; o Techniques to measure the tritium content (in and post operation of the TRF plants) as well as the design of equipment necessary for these analysis Research directions TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010 NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES