HAPL's Potential Tritium Issues
Kirk L. Shanahan (ed.)Defense Programs Technology Section
Savannah River National LaboratoryAiken, SC
HAPL Review, Oct. 30-31, 2007
300 500 700 900
T (K)
dP/d
t (ar
b. u
.)
4th
5th
WSRC-STI-2007-00604
Background
Charter - To identify tritium issues potentially affecting a HAPL IFE reactor facility– not limited in scope or to a particular reactor design
Contributors – James Klein, Kit Heung, Elliot Clark,
Kirk Shanahan – SRNL
Kevin Sessions – SRS Tritium Facility
Format – whitepaper - began Oct. 2006, comments from PPPL and LANL, issued Jan. 29, 2007
HAPL's Potential Tritium Issues vs. ITER’s
HAPL facility will be very similar to ITER
Functions defined in ITER should be found in HAPL
Tokamak
VacuumTokamak Exhaust
Processing
Isotope Separation
System
Storage and Delivery
Fueling
Atmosphere Detritiation
Water Detritiation
Automated Control System
Analytical System
Q2
WaterMethaneInerts
Q2
WaterMethaneInerts
Q2
Trace-tritium gases (water, methane, inerts
D, TD, TDTH
Air/Gases
EffluentH2OHTO
T
Tritium Plant
,
Note: Q = H, D or T
Original Focus – Can we do it?
Early HAPL facility concerns focused on reactor core
Magnets
Upper Pole Blanket
Upper-mid Blanket
Lower-mid Blanket
Lower Pole Blanket
Ring Cusp Armored Dump
Point Cusps Armored Dump
6m
Courtesy G. Sviatoslavsky, University of WisconsinCourtesy C. Gentile, PPPL
Yes, we can – What next?
C. Gentile’s slide from 16th HAPL Workshop
Now that there is a reactor concept, time to consider T processing
HAPL's Potential Future
Fuel Recovery System
T in SolidsRecovery Sys.
Target Loading Facility
Tritium ExtractionSystem
Waste Handling Facility
* Analytical Services Embedded
*
*
*
*
*
But more functionality needed!
Regulatory Issues Immense!
Tritium Handling requires significant infrastructure as well• Accounting
― Inventory― Measurement QA
• Radiation Exposure Records― Personnel―Environmental
• Facility Documentation• Licensing and Regulatory Compliance• Waste Handling and Monitoring
Whitepaper’s Primary Conclusions
Major Point – need to start developing Conceptual Design of other needed facilities– Fuel Recovery System – recovers T from gas stream (already covered in
PPPL CD)– Tritium Loading Facility – loads the plastic shells and delivers to reactor
(LANL is working on part of this)– Tritium in Solids Recovery Facility – deals with tritium recovery from
particulates up to large parts – Tritiated Waste Handling Facility – Handles all non-recoverable tritium as
waste– Tritium Extraction System – remove T from breeder material
Several minor points made as well
Example of Details
Some specific detailed comments
– Possibility of T uptake in plastic shells?
– Specific choices for components in FRS CD may need more research (ITER is doing some of this now)
– Was worried about use of ferritic steel (but use is minimal to zero)
– Where do all the spallation products go?
– Further progress in defining the issues rests on the ability to specify stream compositions and time dependencies (flowcharts)
Some New Questions
Some specific questions
– T behavior in hot SiC?
– T recovery from FLiBe or PbLi?
– How do T issues change with higher temperatures and neutron damage?
Recommendations
Recommended Future HAPL Tritium Activities/Studies
– C-loading, particulates, etc., of FRS feed stream
– T uptake by plastics (Shells, ablation materials, other parts?)
– T uptake and impact on other materials of construction(SiC, PbLi, FLiBe, etc., and note that the process equipment will not be at high temp.)
– Radioactive material release estimates and ancillary waste issues