MINISTRY OF EDUCATION, RESEARCH AND INOVATION, ROMANIA
Experimental Tritium Removal Facility
an example/support for national
/international colaboration”
-Institute for Cryogenics and
Isotopes Separation-Rm Valcea
GHEORGHE IONITA
NucInfoday, May 15-th, 2013- Bucharest
Cernavoda Nuclear Power Plant
LIQUID EFFLUENTS EMISSIONS (1996-2009)
Tritium Liquid Emissions CNE Cernavoda - Unit 1
3.25E+11
2.45E+11
2.60E+11
kBq
1.95E+11
1.95E+11
1.54E+11
1.54E+11
1.14E+11
1.30E+11
6.50E+10
1.14E+11
8.47E+10
5.21E+10
4.35E+10
1.93E+10
6.18E+10
1.16E+10
7.88E+08
7.56E+10
0.00E+00
1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009
TRITIUM LIQUID EMISSIONS FOR UNIT 2(2007-2009)
Tritium Liquid Emissions
Unit 2 2007 - 2009
5.44E+09
4.68E+09
4.76E+09
4.08E+09
kBq
3.40E+09
2.72E+09
1.83E+09
2.04E+09
1.36E+09
6.80E+08
5.27E+08
0.00E+00
2007
2008
ye ar
2009
Tritium concentration in precipitation(arithmetic and
weighted mean) at ICSI Rm-Valcea(1999-2009)
Premises
• Permanent increase of the tritium level in heavy water (
steady state-65-80Ci/l) from CERNAVODA NPP, due to neutron
activation;
•Operation dificulties in safety conditions;
•High cost for replace and storage tritiated heavy water;
• Environment contamination risk;
• Neccessity to protect the operational staff of NPP;
• Tritium it’s a valuable material of real interest for ITER and
other applications;
• An effective and efficient technology for heavy water
detritiation and afferent Tritium Removal Facility it’s
requested
Heavy Water Detritiation Technologies
Company
Technology
Current Status
ILL Grenoble, Franta
VPCE+CD
Decommissioned
Ontario Hydro,
Darlington, Canada
AECL, Canada
In operation >20
years
CECE + CD
FZK, Germania
ICSI, Romania
Demonstration
(shut down)
In operationlaboratory
experiments)
LPCE + CD
Wolsung, Korea
Pre-operational
In Operation
Fugen, Japonia
LPCE
Decommissioned
Candu Owner Group
DE + CD
Conceptual Project
HEAVY WATER DETRITIATION TECHNOLOGY
( Liquid Phase Catalytic Exchange Cryogenic Distillation- LPCE – CD )
A) tritium transfer from water - by isotopic catalytic exchange
B) tritium concentration
- by cryogenic distillation
C) tritium safe storage
- (as metallic hidride)
Experimental Pilot Plant for Deuterium and
Tritium Separation
Start of the Project – 1992 – the first stage as semiindustrial scale plant for hydrogen isotope separation;
Finalisation of the Project – 1997 – commissioning with
hydrogen, deuterium isotopes;
In the year 2000, after reaching the normal operation and
proved the technology it begun the next stage – implementig
of the necessarry request to modify into nuclear facility;
In 2004-2010 – cold experiments by deuterium simulation
and implementing the modifications to be licensed by
Romanian Regulatory Body CNCAN (National Commission
for Nuclear Activities Control);
In 2009 we got the first barrel with 200 kg of 3,31e-8 Bq/kg
tritiated water ( excepted limit for regulations by CNCAN)
Initial Design Targets
• 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
ICIT – Tritium Removal Facility
ICSI – TRF’ Curent Status
• Shut-down for up-grading and lincensing as nuclear
facility
• Technical project:
–
–
–
–
–
CD system increasing refrigeration power (class 3 and 6 equipment)
LPCE column replaced with new catalyst/package design (class 3
equipment)
Purification system redesign
Tritium storage redesign (use uranium and titanium getter beds)
Utilities modification based on new requirements
Elaboration of decommissioning plan of TRF
• Detailed design:
–
Overall revision
–
–
–
–
Licensing requirements review (hazard category 3)
Design requirements review
Safety systems list review
FSAR review based on new project (new safety analysis required)
• Licensing:
Upgrading – Cryogenic Distillation
•
The upgrading-extending process comprise technological
design, equipment acquisition and installation
•
Equipment proposed to be procured:
Helium refrigeration unit – 1000 W at 20 K –
compressor, helium tank, helium cold-box,
helium transfer line;
Tritium storage system;
Cold-box for the cryogenic distillation
module;
Experimental cascade system for the
cryogenic distillation;
Control and measurement system for the
cryogenic distillation module;
CATALYSTS
• Preparation, characterization and testing of catalysts for:
1- hydrogen- water isotopic exchange in liquid phase( LPCE);
2- hydrogen-oxygen recombination ( stoechiometric mixtures);
3- removal of volatile organic compounds(formaldehyde, BTX;
alchools;etc) from water;
4- catalysts for fuell cell
5 - conversion of greenhouse gases in friendly environmental
compounds;
6 - recycling of solid waste;
7 - conversion of biomass in products with energetic value;
•
Charactherization: metal content; surface area; size particle; metal
area; total volume and pore distribution ;mechanical strength;
• Hydrophobic catalaysts for 1-4 applications (Pt/C/PTFE; Pt/SDB;
Pt/C/PTFE-ZnO; Pt/C/PTFE-TiO2) – tablets and rings with metal
content-0.4-2%; surface area 16-120 m2/g; metal area 120 m2/g;
mechanical strength-1.7-6.6 k gf/pellet
CATALYSTS
Packings for water distillation
Packings of 100 mm diameter
PACKING OF 800MM DIAMETER
Implementation of Detritiation Facility at
Cernavoda NPP
Cernavoda TRF Facilities(CTRF)
• Project started in 2008. Technical project,
detailed design and licensing
• Subject: tritium removal facility for U1/U2
• CTRF scope:
– Detritiation of heavy water moderator produced by
operation of U1
– Operating of CTRF on line for U1&U2
– Decommissioning support for U1&U2
• Future TRF – U3&U4
CTRF Technical Specification (initial)
• CTRF will start at 54 Ci/kg (estimated)
• To reduce the tritium content to 10 Ci/kg in 2
years (heavy water moderator)
• Feed: 40 Kg/h
• Detritiation factor 100
• Upgrading possibility for heavy water - from
minimum 99.7% to 99.95%
• To be used by U1 and U2
• Design for 40 years lifetime
• Long term storage space for tritium
Cernavoda CTRF-2 Considerations
- Lifetime of TRF – 40 years
•
Actual planned CTRF design can not support
U3&U4:
– U3&U4 – private investment, but CNE Cernavoda
has operating responsibilities
– detritiation for U3&U4 start operating; 20 years
later than U1;
– Location of CTRF – no pipe route for heavy water
transport and high distance
– Operating of CTRF also for U3&U4 can affect the
target for U1/U2 (no capacity available)
Conclusion – U3&U4 need new TRF
Schedule for ICSI & CNE TRF
ICSI
TRF
CNE TRF
Year
2011
Design (technical
project)
Design (detailed design)
Procurement
Construction
Licensing
Commissioning
Operating
2012
2013
2014
2015
2016
2017
2018
• COMPARISON BETWEEN ICIT-TRF
AND CERNAVODA -CTRF
Main data comparison
ICSI TRF
CERNAVODA TRF
Flow (kg/h)
7
40
Detritiation factor
3
100
Front-end
LPCE (1 column, Ø100x6 m)
LPCE (3 columns, Ø400x17m
each)
Back-end
CD (hydrogen, 140W*)
CD (helium, 12000W)
6 g tritium, no vault
5 kg tritium, secured vault
OPEX
ICSI, ITER (experimental
facilities)
ICSI, ITER (experimental
facilities)
WTRF, DTRF (industrial)
Status
Commissioning (stopped*)
Design phase
Storage capacity
* Project change to 1000W (2010-2012)
Design comparison
ICSI TRF
Main systems (LPCE, CD)
Cernavoda TRF
Same technology
ADS
100 mc/h
2000 mc/h
TRS
No
Yes
LCS
Feed & product
purification
Same
No
Feed the plant by barrel
Yes, specific
equipment. Feed by
pipes
DMS
Yes (equipment to be
installed)
Yes
HVAC
2 exchanges/h
10 exchanges/h,
hydrogen ventilation
1 x 100 KVA
2 x 250 KVA
Class III Diesel Generator
Lessons learn for CTRF-2
• Location – in U3/U4 project TRF location should be
included
• Safety analysis for U3/U4 should take in consideration
TRF events
• Utilities – based on actual CTRF project, utilities
requirements for TRF should be included
• Operating – CTRF-2 design systems should be changed:
building with more space and different layout, all systems
inside CTRF-2 building (ex. HWFS, HWPS), underground
pipes for heavy water transfer
• Applicable code and standards
CTRF-2 discussions
• Companies involved in U3&U4 project are
aware about TRF
• Discussions related to new TRF started as
initial investigation
• Energonuclear and AMEC investigate TRF
approach. TRF construction for U3&U4 will
be recommended.
CONSORTIUM WORK RELATED TO ITER
LINK TO ITER-EURATOM PROGRAM(I)
ITER - WDS
For ITER, the WDS is one of the key systems to control the tritium
content in the effluent streams, to recover as much tritium as possible
and consequently to minimize the impact to the environment.
The most suitable process for water detritiation is the CECE process, a
combination of electrolysis and catalytic exchange of hydrogen isotopes in a
Liquid Phase Catalytic Exchange (LPCE) column.
The separation duty of the CECE process for fusion reactors is very high (tritium
concentration in the released H2 from the WDS for ITER shall be < 700
Bqm-3 air at a typical activity of tritium in the feed water of 370 GBqm-3).
ITER - ISS
The Isotope Separation System (ISS) envisaged to be used in ITER
consists of a cascade of four cryogenic distillation columns with the
aim to process a gas stream from the Vacuum Vessel via the
Tokamak Exhaust Processing (TEP) system and a second one from
the Water Detritiation System mixed with the return stream from the
Neutral Beam Injectors. The ISS has to supply five streams with
various tritium, deuterium and hydrogen composition. The top
product of a CD column from ITER-ISS (CD1 column) has to be
almost tritium free to be discharged into the environment, which is
one of the main concerns from the licensing point of view
Final remarks
Experimental Pilot for Deuterium and Tritium Separation (TRF) it’s a national
interest facility with the aim:
- to check by simulation and in real conditions, the heavy water detritiation
technology;
- to suport research activities concerning the certain processes and behavior
of materials at cryogenic temperatures/conditions;
- to suport research activities linked to WDS and ISS facility within ITER –
Fusion Project;
• Based on experimental results obtained in real conditions, ICIT-TRF will offers
significant results for designining and implementing an Industrial CTRF at U1 and
U2 from Cernavoda NPP and will contribute to decreasing the tritium releases in
the environment;
•
•
•
Based on lessons learn, ICIT make recommendation for future TRF
implementation to U3&U4;
TRF and future CTRF is mainly a result of national cooperation
More international cooperation / exchange experience and technical assistance
it’s still neccessary
Main support from IAEA
• Review of the curent status and future
activities concerning operating of TRF and its
implementation at CernavodaNPP-workshops2; expert mission-1; SV-3;
• Equipment Procurement
• Training of Human Resources:
– Developing of methods for determination of tritium
(stored and mobile) and deuterium inventory related to
TRF;-fellowship
– HAZOP Study for TRF operation- EM 1; SV-2
– Elaboration of Decommissioning Plan for TRF and U1-U2
reactor including CTRF and Radioactive Waste
Management;- Training course
ROM 02/009’ PLANNED ACTIVITIES in 2012
• 1. Experience Exchange- Scientific Visit at Wolsong TRF and
KAERI( Koreea) for 3 researchers
•
Proposed data- April 2012;
•
Budget 3x 4333 = 12 999 Euro
• Aditional request- extension the delegation at 6 ( researchers
and engineers):
– For 3 persons the fees will be covered within Project;
– For 3 persons the fees will be covered by ICIT Rm-Valcea;
– Apropriate agreement with Wolshong TRF it will neccessary in advance
ROM 02/009’ PLANNED ACTIVITIES
• 2. Acquisition/procurement of:
• Gas tritium standards - for the calibration
of the tritium process monitors and tritium
in air monitors within TRF;
– Charactheristics in Anexe 1;
– Potential Supplier: Overhoff Technology
Corporation ;
• Specific Software (ISOGRAPH Package
products) for complete risk analysis and
hazard analysis; see Anexe 2
ISOGRAPH Package Software(anexe 2)
• NSWC Module = (Mechanical) Failure Rates Prediction = 2,660.00Eu
• Fault Tree+ Module = Fault and Event Tree diagram + Markov
analysis =8,400.00Eu
• RBD module = Reliability Block Diagram (Network) Analysis =
5,320.00Eu
• FMECA module = Failure Mode, Effects and Criticality Analysis =
5,320.00Eu
• MTTR module = Mean Time To Repair (Maintainability) =
1,260.00Eu
• Allocation module = Method of apportioning a system target
reliability amongst sub-systems and components = 1,260.00Eu
• HAZOP module = Hazard and Operability Study = 2,520.00Eu
• LOPA (Layers of Protection Analysis)-2,140 Eu
• Risck analysis modules for electrical systems – 2,435 Eu
• and the following libraries:
• NPRD = Non-electronic parts = 672.00Eu
• IAEA = library for mechanical component failure data = 560.00Eu
• Total Estimated Price= 35 000 Eu
ROM 02/009’ PLANNED ACTIVITIES in 2012
• 3. Training Course-( 1 person) on “Elaboration
of deccomissioning plan of TRF and safety
management of specific radioactive waste” ;
•
•
•
•
Duration: 4-6 weeks
Planned date- Q2- Q3
Budget- 10 000 Euro
Aspects : Initial planned TC "Management of
Radioactive Waste in Accordance with IAEA Safety
Standards and International Best Practice" –
organised by Clausthal University of Technology
( Germany) will take place in 2013;
• Proposal: to find other similar course in 2012
or to replace it with workshop 1, planned in
2013 ( budget 15 000 Euro)
PROIECTE EURATOM-EFDA
•
1. Tehnologii de separare a izotopilor de hidrogen in sistemele de detritierea a apei grele
(TWO-TRIT/REM)
•
2. Optimizare raport umplutura/catalizator pentru transferul simultan al deuteriului si
tritiului in sistemele de detritiere (JW0-FT-2.1)
•
3. Test de anduranta a amestecului de umplutura/catalizator propus pentru sistemul de
detritiere de la JET (JW – FT – 2.20)
•
4. Permeatia tritiului in materiale (NUC – INT – UT 4)
•
5. Proiectare a instalatiilor de procesare a tritiului pentru JET si ITER; (TW2-TI-TR39),
(TW5-TTFD-TPI-51) zi (TW6-TTFD-TPI-55)
•
6. Research Training Network - „Preparing the ITER Fuel Cycle“
•
7. JET Gamma-Ray Cameras Upgrade Neutron Attenuator (GRC_KN3_NA)
•
8. Teste de anduranta ale componentelor sistemelor de detritiere a apei