NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES
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.
TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010

NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES
NUCLEAR NON-NUCLEAR
TRITIUM HEAVY WATER
TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT
HYDROGEN
AND
FUEL CELLS
ENVIRONMENT
&LIFE SCIENCE
Workshop Diaspora 2010

NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES
ICIT Rm Valcea general strategy for R&D between 2006-2013 is focused on the following objectives: o o o o o o o
Romanian and European nuclear program (NPP, TRITIUM, HEAVY WATER)
Hydrogen and hydrogen fuel cells
Researches in the materials field
Environment and quality of life
Business and technology incubator for research transfer
Development of the infrastructure and services for technological transfer and innovation
Development of young researcher teams
TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010

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

NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES
• tritium maximum activity in heavy water:
• maximum tritium inventory:
• quantity of heavy water annually processed :
• minimum deuterium concentration in feed water:
• water feed rate:
• tritium inventory in CD:
• design service life:
30 Ci/kg
300,000 Ci
2000 kg
99.8 %
8 kg/h
200,000 Ci
30 years
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 REMOVAL FACILITY-CRYOGENIC PILOT PLANT
Tritium Storage Tritium Extraction
Workshop Diaspora 2010

NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES
Chosen detritiation technology: LPCE – CD (Liquid Phase Catalytic Exchange
– Cryogenic Distillation)
Underlying technology:
A) tritium transfer from water
B) tritium concentration
C) tritium safe storage -
by isotopic catalytic exchange
by cryogenic distillation
(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
MODERATOR
D
2
O
RECOMBINATOR
D
2
DTO C
E
L
P
DT
CD
O
2
From electrolyze
Supplementary
D+T
Storage
O
2
ELECTROLYZER
 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
TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010

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

NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES
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. 042862 (FU 06);
10. RESEARCH TRAINING NETWORK ”TRITIUM TECHNOLOGIES FOR THE FUSION FUEL CYCLE TRI-TOFFY “
11. C4T/09/90/PMT - PRI0001338
– “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.
TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010

NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES
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
KIT ICIT ENEA CEA
F4E
Industry
PARTIES
STEERING COMMITTEE
PARTY LEADER
MANAGEMENT BODY
COLLABORATION MANAGER
WORK PACKAGE LEADERS
PARTIES REPRESENTATIVES
MANAGEMENT SUPPORTING TEAM
IO
Others
TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010

NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES
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
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 ( gaschromatograph - mass spectrometer system)
 mass spectrometry analyses, IR spectrometry analyses and dens meter analyses applied to various products control
TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010

NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES
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.
TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010

NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES
 Breakdown by age (total 217):
 53 employees < 35 years
 69 employees 36-45 years
 82 employees 46-55 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 specialists
49%
MD Attendants
2%
Doctors
19%
PhD Attendants
30%
TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010

NATIONAL R&D INSTITUTE FOR CRYOGENICS AND ISOTOPES TECHNOLOGIES
“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
TRITIUM REMOVAL FACILITY-CRYOGENIC PILOT PLANT Workshop Diaspora 2010