compton suppressed gamma spectroscopy of spent fuel
TRANSCRIPT
Compton Suppressed Gamma Spectroscopy of
Spent Fuel InventoriesAbdullah Weiss
NCNR, Reactor Operations and Engineering Group
Background A little about me:
Texas A&M University-Kingsville (Junior Fall 2016)
Mechanical Engineering major, and Nuclear Engineering minor
Project Origins:
Idaho National Laboratory (ATR)
Penn State University
Motivation of Project:
To successfully determine the burnup of highly enriched uranium (HEU)
fuel in the Neutron Beam Split-core Reactor (NBSR) at the NCNR.
Benchmark the power and burnup of the NBSR.
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INL Study (2013)
A Feasibility and Optimization Study to
Determine Cooling Time and Burnup of
Advanced Test Reactor Fuels Using a
Nondestructive Technique by Jorge
Navarro
Determined burnup and cooling time of
fuel using isotopic ฮณ ray peak area, and
peak area ratios.
Relationship was found between burnup
and isotopes including 137Cs, and the
ratios of other isotopes correlated with
the cooling time (such as 144Ce/ 137Cs).
Isotope ratios were correlated to cancel
out the geometry of the measurement.
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Penn State Study (2014)
Study of Compton Suppression for Use in Spent Nuclear Fuel Assay by Sarah
Bender
A fuel sample from the Penn State Breazeale Reactor was measured using
Compton Suppression.
Used concrete collimator built into the fuel pool to study aged LEU fuel.
Eight additional photopeaks were unmasked, allowing for identification of
more isotopes in the fuel sample.
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Penn State Study (2014)
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Compton Suppression
Compton Scattering
How do we apply Compton Suppression?
ฮณ
ฮณโ
e-
โฮป =โ
๐๐๐(1 โ cos ๐)
๐ฝ
I am Arthur H.
Compton, and
I won the
Nobel Prize in
Physics
๐ฝ ฮณ
ฮณโ
Detector
Another Detector
Detectors Run in Anti-Coincidence
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NBSR FuelThe Reactor:
D2O Coolant, moderator, and reflector
30 fuel elements with 38.5 day fuel cycles
~20 MW Thermal Power
The Fuel:
93% U3O8 + Al
17 fuel plates per region
2 regions per fuel element
Burnup:
If 10% of an initial isotope underwent fission, the burnup is 10%.
In general: ๐๐โ๐
๐๐๐ก๐๐๐ ๐๐๐๐๐=
๐๐๐ค๐๐ร๐๐๐๐ ๐๐๐๐๐ก
๐ผ๐๐๐ก๐๐๐ ๐๐๐ ๐ ๐๐ ๐น๐ข๐๐
Fuel
Plates
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Burnup:
If 10% of an initial isotope underwent
fission, the burnup is 10%.
In general: ๐ด๐พโ๐
๐ด๐๐๐๐๐ ๐ป๐๐๐๐=
๐ท๐๐๐๐ร๐ป๐๐๐ ๐บ๐๐๐๐
๐ฐ๐๐๐๐๐๐ ๐ด๐๐๐ ๐๐ ๐ญ๐๐๐
We wanted to measure spectra from different spent fuel elements using a HPGe
detector and a BGO detector.
We had to channel a ฮณ beam from the fuel elements to the detectors.
The detectors had to be setup in a way that accommodates Compton suppression.
It had to be safe: health physics, crane lift, and ฮณ beam control.
Not a single thing besides the collimator and its peripherals was to touch the water.
Had to be easy to assemble and disassemble for multiple uses for different ฮณ beam
sizes.
Mechanical issues to be addressed: structure, buoyancy, material selection,
manufacturing
Cost Effectiveness
Detectors Setup and Calibration
EVERYTHING MUST WORK!!!!
Results?
Challenges
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14 15 16 17 18 19 20 21 22
Vertical Distance (ft)
Dose vs Distance From Source to Detector
1048 1049 1050 1051
Radiation Safety
1048
y = a1b1 x
Rยฒ = 0.9976
1049
y = a2b2 x
Rยฒ = 0.9729
1050
y = a3b3 x
Rยฒ = 0.9992
1051
y = a4b4 x
Rยฒ = 0.9986
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Questions:
1. How far down should we initially measure?
Necessities:
1. Attenuation Coefficients (ยต)
2. Average Attenuation Coefficient (ยตavg)
3. Average Tenth Value Layer (TVL)
???? ft
Collimator
Fuel Element
H2O
in the pool
Measured by Timothy Barvitskie
Radiation Safety
Attenuation Coefficient (ยต):
๐ท = ๐ท0๐โ๐๐ฅ ๐ =
โ๐๐(๐ท๐ท0)
๐ฅ
Tenth Value Layer (TVL):
๐๐๐ฟ =๐๐(10)
๐
Calculated Results:
ยต (1/ft) TVL (ft)
1048 1.8697 1.23
1049 1.6869 1.36
1050 1.8735 1.23
1051 1.8437 1.25
AVG 1.81845 1.27
1.27 ft๐ท
๐ท
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THIS IS IMPORTANT!!
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Where do we put the detectors?
Apparatus Requirements:
Easy to assemble/disassemble
Mobile
Stable
Other places that were considered:
On the side of the pool
In the pool (under the lid) HPGe
BGO
Catwalk
The Pool
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LN2
Where do we put the detectors?
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Where do we put the detectors?
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Where do we put the detectors?
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The Apparatus
8020 Aluminum
Polyethylene
Steel
6061 Aluminum
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The Collimator
6โ(x4)
1โ OD โ 0.93โ ID
Connected via Tube Locking
Fittings
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Structural Analysis
wHPGe
wBGO
wCol
ฦฉ๐ค = 115 ๐๐
ฦฉ๐ < ๐๐๐ ๐๐
There is a risk of dropping
detectors in the pool.
Treat system as a structural beam,
and find the center of mass for
the platform.
Center of mass was within the
safety zone.
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C.M.
Buoyancy Analysis
In order for the collimator to work properly, it must sink in.
Original thought:
2โOD 1.65โID tubes for collimator
Health Physics Concerns make Collimator smaller (1โOD, 0.93โID)
๐น๐ต,๐๐๐๐๐๐๐ = ๐๐ป2๐ ร ๐ ร ๐๐๐,๐๐๐ฅ โ ๐ค๐ถ๐๐ โ 5 ๐๐
5 lb deficit
But since itโs held in place, would it REALLY bend too much?
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Detector Calibration
Done using GENIE-2000
Energy Calibration using Co-60 and Eu-154 Sources
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Initial Results
Collimator was bending in the water.
Background spectrum was not very
different from fuel spectrum.
Needed a solution
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Channel
Counts
Initial Results
Background Spectrum (24 hour count)
Fuel Spectrum (1 hour count)
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Initial ResultsBackground Spectrum
Fuel Spectrum
๐ต๐ข๐๐๐ข๐ ๐๐๐ ๐๐ ๐๐๐ข๐๐ ๐ข๐ ๐๐๐โ134Cs
โ137Cs
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137Cs
662 keV
t1/2=30 y 134Cs
795 keV
t1/2=2.0 y
110Ag
657 keV
t1/2=249 d
Peaks were refitted in Hypermet-PC
โ134Csโ137Cs
ratio was calculated with the refitted peaks
Pictures Courtesy of Danyal Turkoglu
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Peak Fitting
Isotope Buildup
over fuel life
(MCNP)
0 E+0
2 E-3
4 E-3
6 E-3
8 E-3
1 2 3 4 5 6 7 8
Rel
ativ
e C
on
cen
trat
ion
Cycle #
Cs-137 Isotope vs Fuel Passm15 m16 m17 m18 m25 m26 m27 m28
0 E+0
2 E-4
4 E-4
6 E-4
8 E-4
1 2 3 4 5 6 7 8
Rel
ativ
e C
on
cen
trat
ion
Cycle #
Cs-134 Isotope vs Fuel Passm15 m16 m17 m18 m25 m26 m27 m28
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235U
Other Isotopes
Fission
Experiment efficiency (MCNP)
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134Cs
137Cs
Burnup of fuel (MCNP depletion study)
0
1000
2000
3000
4000
5000
6000
7000
8000
0 0.01 0.02 0.03 0.04 0.05 0.06 0.07 0.08 0.09 0.1
BU
RN
UP (
MW
-DAYS)
RATIO (134Cs/137Cs)
Burnup vs Cs Ratio
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BURNUP!!
โ134Cs
โ137Cs=๐134๐137
ร๐ถ๐ 134๐ถ๐ 137
รฮป137๐ผ662ฮป134๐ผ795
ร๐ฮป134 ๐ก๐๐๐๐
๐ฮป137 ๐ก๐๐๐๐
Experiment Efficiency Count Rate Specific ฮณ emission rate Cooling Time
Fuel Element Isotope Ratio Burnup (MW-day) Power* (MW)
S1025 (July 2015) 0.0751 5329 19.8
S1036 (Jan 2016) 0.0705 5100 18.9
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*38.5 d cycles assumed (7-cycle fuel)
Calculated error due to background corrected gamma peaks area is +/-0.04 MW
Burnup Results
0
1000
2000
3000
4000
5000
6000
7000
8000
0 0.01 0.02 0.03 0.04 0.05 0.06 0.07 0.08 0.09 0.1
BU
RN
UP
(M
W-D
AYS
)
RATIO (134Cs/137Cs)
Burnup vs Ratio
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Conclusion
Assembled the entire experiment and proved that it works
Addressed health physics concerns and completed safety evaluation
Observed several isotopes from fuel, and was able to determine burnup
This is the first time this is ever been done
Future Work
Make a collimator that works better
Improve stability of apparatus
Longer count times (overnight)
Measuring additional elements
Evolve this experiment into a gamma spectroscopy scanning apparatus
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Acknowledgements
Thomas Newton
Dan Hughes
Daniel Flynn
James Moody
Thomas Johnston
Samuel MacDavid
William Clow
Julie Borchers
Paul Brand
Attila Halacsy
Robert William
Gregory Heller
David Brown
Doug Johnson
Don Lopez
Joe Dura
And all the SURF directors and the SURF Program
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AcknowledgementsA special thank you to these individuals:
Daniel Mattes
Timothy Barvitskie
Danyal Turkoglu
Ryan Fangmeyer
HEโS A SURF STUDENT TOO!!
Taught me almost everything I know about detectors
Heโs a Mechanical Engineer.
It automatically makes him awesome
Guided me through ยต and
TVL calculations (and helped
out with Genieโฆand helped
out with other details of the
project)
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Acknowledgments
My Mentor:
Bryan Eyers
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Q/A?