1. Replacement Fuel For The Vienna Austria TRIGA Research Reactor
This presentation is about the efforts that were required to furnish the Austrian research reactor with lightly irradiated TRIGA nuclear fuel.
The fuel came from the storage facility at the Idaho Nuclear Technology and Engineering Center (INTEC) located at the Idaho National Laboratory (INL)
Mr. Dale Luke and Alan Robb
Domestic and Foreign Research Reactor Project / Idaho National Laboratory
TRTR September 2013

2. HOW DID WE GET HERE? Returns Program Atoms for Peace Program
INL/INTEC Designated as Receipt Site – TRIGA
Thousands of FRR/DRR TRIGA Elements Received
Many TRIGA Elements are Very Low Burnup
The Atoms For Peace Program was started as a result of a speech given by Pres. Eisenhower to the UN General Counsel in New York City Dec 8, The program was launched to supply equip/info to schools, hospitals, and research institutions within the US and throughout the world. Small research reactors were given to foreign nations in exchange for their promise to forego development of nuclear weapons and were to be used only for peaceful research and study.
Per the Record of Decision, issued on May 1995 and the EIS, DOE/EIS-0218F, dated February 1996, all U.S.-origin aluminum plate spent nuclear research reactor fuel will be managed at the Savannah River Site and all other spent nuclear research reactor fuel (mostly TRIGA) will be managed at the INL at INTEC.
Since 1998 INTEC, at the INL, has received thousands of elements from domestic and foreign research reactors around the world:
Domestic: Cornell Univ., University of Illinois, SUNY at Buffalo, Texas A&M, Univ., Univ. of Wisconsin, Oregon State Univ., Washington State Univ., NRAD at the INL, and Reed College
Foreign: Korea, Germany, Italy, Slovenia, Romania, England, Japan, Indonesia, Mexico, and Austria.
Many TRIGA elements are very low burnup and have much useful life left in them.
INTEC Facilities / INL

3. (Participating with the INL)
Foreign Research Reactor Locations with TRIGA Spent Nuclear Fuel
(Participating with the INL)
This map provides a quick overview of locations of foreign TRIGA research reactors
[Seoul & Taejon, South Korea; Bellingham, England; Heidelberg & Hannover, Germany; and Rikkyo & Musashi, Japan have been shut down and all fuel elements shipped to INTEC]

4. MAKING THE WORLD A SAFER PLACE
GTRI (Global Threat Reduction Initiative)
Eliminate Sources of Bomb Material from Research Reactors
March 2012 – Austria was Only Remaining Research Reactor World-wide with HEU TRIGA
International Agreements Committed to Remove HEU from Austria As Soon as Feasible
The “Off- Site Fuels Policy,” (later identified as the Global Threat Reduction Initiative (GTRI), made the provision to return all high enriched uranium (HEU) to the U.S. so it could not be used in the production of nuclear weapons. In 1986 the US included the return of all low enriched uranium (LEU) as well.
In March 2012, all TRIGA research reactors, with the exception of Austria, had converted from using HEU to LEU.
International agreements committed to remove HEU from Austria as soon as feasible.
TU Wien Mark II TRIGA Research Reactor

5. TU WIEN TRIGA MARK II RESEARCH REACTOR
Critical Since March 7, 1962
Only Operating Reactor in Austria
Steady State Power of 250 kw
Pulsing Capability up to 250 mw
The Austrian reactor went critical on March 7, 1962 and has been in operation since that time.
It is the only operating reactor in the country. With the elements that were supplied to them the reactor will now be able to continue operation for many years.
The reactor has and is still being used for the following:
Development of safeguards instrumentation (Supported the Olympics in London through the IAEA)
Calibration of nuclear instrumentation
Training for IAEA junior inspectors (since IAEA professionals have been trained in the facility)
Support and testing for IAEA member states.
The research reactor is capable of 250 watts for steady state power and up to 250 megawatts of pulsing power.

6. IN WITH THE NEW(er); OUT WITH THE OLD THE IDEA
Possible Unavailability of TRIGA Fuel
Recent Univ. of Ariz. to Reed College Transfer of Fuel
At a previous TRTR conference it was announced that the TRIGA fuel fabrication line was going to be down and new elements may not be available for several years.
At about this same time, Reed College was in dire need of new fuel to enable them to continue operation. The Univ. of Arizona was shutting down and had a nearly a core’s worth of fairly low burnup stainless steel-clad TRIGA fuel that could be utilized for years to come. Reed College coordinated the transfer of the fuel from Arizona to their location and then planned the return of their spent (mostly aluminum-clad) fuel to INTEC in Idaho.
The swap was a success and the reactor at Reed has been in continuing operation and will continue to operate for many years to come.
[USGS successfully received used fuel from the Veterans Administration facility in Omaha as well]
Picture of a Standard “Streamlined” TRIGA Element

7. “IN WITH THE NEW(er); OUT WITH THE OLD” THE IDEA (cont.)
TRTR Informal Discussions of INTEC Source for TRIGA
“Idea” Picked up by DOE-NNSA & Proposed to Austria
CWI Database Revealed ‘Prime’ TRIGA Elements Available
To other colleges at TRTR, CWI personnel identified INTEC as a source of used TRIGA fuel elements with low burnup that could potentially be re-used. These elements were shipped to Idaho from research reactors that have discontinued operations.
The idea of “harvesting” fuel from the fuel storage facility in Idaho was picked up by DOE-NNSA and discussed in meetings with Austria as an option to replace their HEU fuel elements.
Austria liked the idea a lot and decided to ask for enough elements to replace almost a core’s worth of much greater burnup, mostly Al-clad TRIGA elements.
Using information from fuel storage data, CWI personnel identified low burnup fuel elements that could be candidates for future use in TRIGA research reactors. Some of these elements were “prime” streamlined SS-clad TRIGA elements with very low burnup. (Yes, Austria truly got the ‘pick of the litter’).
Storage Array at IFSF in Idaho

8. “THAR’S GOLD (FUEL) IN THEM THAR HILLS OF IDAHO”
DOE / CWI / Austrian Ministry Met in Dec. 2011
Proposal & Cost Estimate Developed with Seed Money
In December of 2011 Austria sent over a delegation of personnel from the reactor facility and the Austrian ministry to meet with DOE and CWI to discuss the possibility of a “harvesting” lightly irradiated TRIGA fuel and sending their higher burnup fuel to Idaho. The delegation was given a tour of the storage facility and the discussions led into what capability the storage facility had and the feasibility of doing such work.
CWI personnel, with seed money and directions from DOE, developed a detailed cost estimate and project plan.
The major pieces of work that were estimated included the following:
Procedures development, dry run, and final approval;
Required shippers data prep and issue;
Safety basis changes: cask lists, fuel lists, and CSE;
Fuel examinations - both in Austria and at the INL by the Austrians;
Cask and fuel handling operations: basket/cask loading cask leak test, fuel basket unloading and storage;
Fuel handling tools and equipment;
Equipment dry-run testing and training;
Assessment of readiness to begin operations; and
Overall project management and oversight.
Austrian Delegation to Idaho

9. “GIT ‘ER DONE”
DOE / Austrian Ministry / TU Wien Agreed to Make Exchange (Austria Paid)
77 ‘Prime’ Lightly Irradiated TRIGA Elements to Austria
91 ‘Well Used’ TRIGA Elements to Idaho
Used the Same NAC-LWT Cask to Ship Elements - Both Directions
DOE and Austria agreed to the terms (Austria paid for the elements, the work to harvest them, and the transport) and the work started to make the exchange. The cost savings over procuring new elements was significant.
Austria reviewed the fuel element data and identified 88 ‘prime’ elements that they were interested in from the inventory (of which 77 were selected for shipment).
Austria identified 91 of their ‘well used’ elements that were to be returned to the U.S. These included the remaining HEU TRIGA elements that were returned to the U.S. for storage.
The NAC-LWT cask was chosen to ship the lightly used elements to Austria. The cask was unloaded and used to return the used elements to the U.S.
[A preliminary meeting was held in Austria with CWI personnel to discuss the workings of the fuel exchange and to begin the preparations of required documentation, which proved to be extremely useful to work out potential problems and to:
-evaluate facility equipment and fuel storage configuration needs;
-discuss and determine the logistics of the fuel exams and loading (big “Ah Ha” moment: Austria realized they needed to determine where to store elements until their elements were loaded to ship to Idaho, crit safety issue, etc.)
-determine extent of documentation needed (RSD, etc.) and begin preps
-determine work schedules, training and entry into work areas at Austria and Idaho
NAC-LWT Cask

10. “CHECK IT OUT!” Fuel Exams Performed in Austria & Idaho
June Exam in Vienna, Austria
September Exam in at INTEC
Fuel examination equipment was packaged and sent ahead of CWI personnel to Austria in preparation for the fuel exam at the research reactor facility.
CWI personnel traveled to Austria in June 2012 to perform a detailed visual examination.
In September Austrian reactor personnel traveled to the U.S. to participate in the fuel examination and loading of the chosen elements in preparation for shipment to Austria.
Fuel Examination Equipment

11. “WHAT YA GOT?” 91 Elements Examined 9 Elements had Breached Cladding
1 Element had No Cladding
These Elements Were Canned
A total of 91 TRIGA elements were examined at Austria. Ten elements had damaged cladding and were required to be placed in sealed failed fuel cans for shipment and storage.
Nine of the elements were classified as failed fuel (failed fuel is any element that exhibits the following: greater than hairline cracks, pinholes, or “suspect“ and are required to be placed in a sealed failed fuel can for transport and storage). One element had no cladding at all (was bagged with ID number for purposes of material and configuration control).
As noted in the photo above this is one of the actual elements that was examined at the reactor facility and was subsequently identified as needing to be placed in a sealed failed fuel can prior to cask loading. (You can see completely through the other side of this “hole”).
Al-Clad TRIGA Element w/ Breached Cladding
Element w/ No Cladding

12. “IT’S DARK IN HERE!” SFFC
During loading of the NAC-LWT baskets, the element that had no cladding was transferred to a sealed failed fuel can in preparation for loading into the cask. After the fuel was placed in the can the lid was put on, torqued and leak tested for integrity. The can was then transferred to the pool where it was lowered into the awaiting NAC basket.
Note element pieces in the can.
A total of 6 sealed failed fuel cans were used.
NAC Sealed Failed Fuel Can (SFFC) with Fuel Pieces

13. “WAY TO GO, IDAHO!” 79 Elements Examined
2 Elements Rejected for Anomalies
Sent: 75 Elements From Musashi, Japan;
2 Elements From Cornell Univ.
Three Austrian research reactor personnel traveled to Idaho to perform fuel inspections and witness the loading of baskets.
From a pool of 88 pre-selected TRIGA elements, 79 elements were inspected by placing each element into a specially made examination stand that was placed in the fuel handling cave. The stand had a scale to allow any anomalies to be documented as to where they were and a bracket for holding an AMP-200 radiation monitor to determine radiation levels of the elements.
The three delegates from Austria, through remote cameras/monitors, evaluated the elements for acceptance or rejection. Two of the elements were rejected by them because of indications of damage to the cladding.
75 of the elements were previously used at the Musashi, Japan research reactor and 2 elements were previously used at the Cornell University research reactor. Therefore, 77 elements were selected and sent to Austria from Idaho.
Overall, the process went fairly smoothly, though we did have some problems resulting from aging in-cell equipment and working out a few minor bugs associated with new processes and equipment.
Both Austria and Idaho were very pleased with how things worked out so well. In the future the process should be even smoother and less costly now that the process and procedures have been developed.
Examination Stand
Austrians Examining Elements

14. INTACT SS TRIGA ELEMENTS AVAILABLE FOR HARVEST FROM IFSF AT INTEC
“WHERE’S THE MEAT?”
INTACT SS TRIGA ELEMENTS AVAILABLE FOR HARVEST FROM IFSF AT INTEC
Intact SS TRIGA Elements
Burnup (%)
0 - 5
5 - 10
> 50
SS - Std (8.5/20) 42
112
194 67 73 52 96 9 3 8
Cum
154
348
415
488
540
636
645
648
656
SS - Streamlined (8.5/20) 28 17 2 45 53 55
SS - Total (8.5/20) 70
129
202 69
199
401
470
543
595
691
700
703
711
SS - Conversion (8.5/20) 29 37
141
178
207
209
This table is a summary of the data we have compiled about intact stainless steel-clad TRIGA fuel elements stored at INTEC. More detailed information is available for each element, though we are certainly dependent on the information that was provided by the research reactor that sent this fuel to Idaho.
There are two styles of SS-clad “regular” TRIGA elements. One is the “standard” element and the other is the “streamlined” element. Either style can typically be used in regular TRIGA research reactors. They are shown in the blue boxes in the table.
The other “type” of TRIGA SS-clad elements are the “conversion” (conversion of older MTR-type research reactors, like Texas A&M, Univ. of Wisconsin, and Washington State) or “cluster” elements that are bundled into assemblies of up to four elements. These elements are shown in the green boxes in the table.

15. “FOR WHAT IT’S WORTH” Your Input is Needed on Acceptable Burnup
Also, Is Time Out of Reactor Important?
We have tried to ascertain what the acceptable burnup level is to be able to effectively re-use the TRIGA fuel. Mr. James Sterbentz at the INL, who has extensively modeled TRIGA fuel, gave us a preliminary value. He said that fuel with even up to 20% or higher burnup could probably be effectively re-used, providing significant life expectancy to make it worthwhile for consideration of re-use (dependent on cost of recovery, of course).
Weneed your input, however, to exploit your expertise in relation to TRIGA fuel performance at higher burnup levels. Also, needed is information on whether time out of reactor significantly impacts the performance of the fuel.
Idaho stores the TRIGA fuel in dry storage and so little if any degradation of the fuel cladding is expected.
Thank you for your attention and participation.
Any questions or comments?