regulatory nuclear material control of stuk – nda methods ... · • homogenic isotropic...
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Regulatory nuclear material control of STUK –
NDA methods of Spent Nuclear Fuel in Finland
prior Geological Disposal
Tapani Honkamaa, Topi Tupasela, Mikael Moring
TECHNICAL MEETING ON SPENT FUEL CHARACTERIZATION FOR MANAGEMENT OF SPENT FUEL IN THE BACK END OF THE FUEL CYCLE
IAEA HEADQUARTERS VIENNA 12 – 14 NOVEMBER 2019
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Contents
• Goal of NM verification for both safeguards and security
• Finnish National safeguards concept
• NDA Methods
• What data is needed for verification and analysis?
• Data management issues
12 Nov 2019
Tapani Honkamaa
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Goal of NM verification
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Safeguards challenge of geological disposal
• Goal of geological disposal is to store the spent
fuel environmentally safely and non-accessibly,
forever.
• 1 canister ~ 1-2 IAEA Significant Quantity (3000-
5000 canisters in case of Finland)
• >50 SQ stored every year, 50 % partial defect
of that =…!
• All parties involved must have clear and
unambiguous common understanding about
what has been disposed of.
• It is imperative not to encapsulate and dispose
any items which may in later stages generate
open questions.
Tapani Honkamaa
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Image, Posiva Oy
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Security challenge
• Similar to safeguards challenge, but even smaller defects matter
– A single missing pin is highly relevant
• NM Security and Safeguards have many common goals and means
– The difference is mainly a question of methods used and against what you
protect
• STUK has set the goal that pin level defect should be possible to detect
Tapani Honkamaa
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Characterization vs Verification
• Verification in this presentation means Safeguards
verification conducted by an inspectorate (=IAEA, EC,
STUK)
– Typically NDA measurement
• Goal of verification is to verify the correctness and
completeness of declaration.
• Declaration is provided to the inspectorate by the nuclear
facility
• Nuclear facility can obtain the data for declaration in
multiple ways, which sometimes may be called
characterization
– Own measurement (primarily NDA, DA)
– Modeling (most typical)
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Characterization
Declaration
Verification
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Verification vs characterization
• Usually:
precision of characterization (~5%) >> precision of verification (~50%)
• It would be very cost effective to use the same method for
both verification and characterization BUT:
– Roles must be kept clear
– Independency of the inspectorate verification shall be taken
care of
Typically the methods used for verification have not provided
much value in characterestics due to their poor precision.
Tapani Honkamaa
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Finnish national safeguards concept
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Project GOSSER
• STUK has internal project called GOSSER
(=Geological Disposal Safeguards and
Security R&D)
• GOSSER develops methods needed for
spent fuel disposal project
• GOSSER has two subprojects
– Development of NDA
– Development of surveillance, environmental
monitoring and geological tools needed
Tapani Honkamaa
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Proposed NDA tool by GOSSER: PNAR+PGET integrated
verifier
• PGET =Passive Gamma Emission Tomography
• PNAR = Passive Neutron Albedo Reactivity
• Proposed tool for national verification concept
• Verification time 5 min/assembly
• Fuel assembly is lowered to the verifier from the
top
• Stands at the bottom of the pool, underwater
instrument.
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PGET
PNAR
Tapani Honkamaa
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PGET – hardware and operating principle will
be presented by IAEA SG
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PGET development
Tapani Honkamaa
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1980
1990
1999
2003
2004
2009
2012
2014
2017
2018
2019
2020-
Idea proposed
Th
e first
tests
1999: Proof
of concept
IAEA decision to
support
construction
The first full test proto
development
Te
sts
in IS
PR
A
Te
sts
in L
oviis
a
Development for spent fuel
disposal
Te
sts
in B
WR
, P
WR
, V
VE
R
IAE
A a
pp
roval
Com
me
rcia
liza
tio
n
Th
e first
co
mm
erc
ial
PG
ETs d
eliv
ere
d
HA
RD
WO
RK
TR
L
Year
12
34
56
78
9
TRL = Technology Readiness Level
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PGET performance
• The performance of PGET method is
not yet fully unleashed.
– Analysis is still developing
– New hardware is coming
• An idea has been proposed, if the
methodis capable of quantitative burn
up estimation at the pin level
– This is not needed in safeguards.
• The latest campaign data suggests that
the current system is capable of
detecting sub pin level burn up profile.
12 Nov 2019
Tapani Honkamaa]
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PNAR – hardware and operating principle
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PNAR = Passive Neutron Albedo Reactivity
• Neutron albedo = reflection of slowed neutrons
from moderator (pool water)
• PNAR studies reactivity by modifying neutron
albedo
• 2 measurements
– Maximal neutron albedo
– Suppressed neutron albedo (Cd)
• Ratio of these measurements = PNAR Ratio
– Proportional to neutron multiplication of albedo
neutrons
– PNAR Ratio is correlated with M, keff, inf
• Neutron multiplication is only an attribute of
fissile material
Tapani Honkamaa
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Spent
nuclear fuel
SF neutrons and
1st order multiplication
Neutron
albedo
Neutrons from fission
induced by reflected
neutrons
Fast
neutron
detector
Water/Polyethylene
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PNAR device
• Underwater measurement
• 4 identical measurement pods
with polyethen cover
• 1 γ and 1 He-3 neutron-
detector per pod
– He-3 lined with Cd and
shielded with Pb
• Preamp shielded
• Cadmium sheet moves as
close the fuel as possible
Tapani Honkamaa
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10 mm
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Modular design of the PNAR instrument around the
cadmium liner
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Operating principle
• Cadmium sheet is pulled between neutron
detectors (He-3) and the fuel
• Cadmium absorbs thermalized neutrons.
Tapani Honkamaa
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MCNP simulations
• Design was designed by simulations
before manufacturing
• Homogenic isotropic distribution
assumed in the fuel
• Response:
– PNAR Ratio is propotional to the
fissile material content. (Initial
enrichment, burn-up)
– Dynamic range is important, it tells
how reliably the fissile material
content can be verified.
• Minimization of errors is crucial
Tapani Honkamaa
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Dynamic
range
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PNAR performance (based on July 2019 campaign)
• A typical assembly has a PNAR
Ratio of 1.044 while MCNP
model predicted ~1.12 (??)
• STD of PNAR Ratio
determination is ±0.0013 (!!)
• Non-multiplying assembly is
expected to have PNAR ratio
~0.98 (MCNP estimation using
“nonu-card”; this can not be
measured directly)
• Thus; detection sensitivity of
the instrument is ~40 sigma!!!
Tapani Honkamaa
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Combined PNAR and PGET results
Tapani Honkamaa
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• Areas of lower burnup can be identified
from PGET reconstructions
• In theory
low BU rod = more U-235 and Pu-239
= higher PNAR Ratio
• In reality enrichment profiling, reactor
history etc. has and effect
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IAEA’s ASTOR expert group recommendations
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ASTOR NDA Focus Group Recommended PGET PNAR
Capable of pin level detection Yes No
Capable of verifying that the declared assembly is consistent with measured signatures
? Yes
Capable of measuring assembly neutron multiplication No Yes
Capable of measuring all fuel assemblies at the measurement location and in the medium of interest (fresh water, borated water, air)
Yes Yes (specific design is required for every FA type)
Robust, low maintenance and have a low false alarm rate ? Yes
Difficult to trick with pin substitution System Attribute
Measure the weight of the assembly Load Cell Attribute
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Pictures from PGET+PNAR campaign from
Olkiluoto, July 2019
Pictures: TVO
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PNAR+PGET campaign setup, Olkiluoto 22-26 Jul 2019
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Olkiluoto KPA store, July 2019
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PNAR Detector controller units poolside
Tapani Honkamaa
14 Nov 2019
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Reviewing the PGET results
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What data is needed for verification and
analysis?
Pictures: TVO
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Data useful for safeguards purposesBatch number
Amount of NM
Design: Fuel geometry, Number of rods
Design: partial length rod positions
Design: water rods and their positions
Averaged burn-up of an assembly.
Initial Enrichment
Burn up profiles, axial and pin by pin
Detailed info about enrichment of different pins
and enrichment profiles
Design: Pin-by pin info about burnable poisons
Total weight in air/water
Design: Number and location of spacers
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Design: Description of the handle and other
supporting structure
Rod cassettes geometry information
Burn up history: Cooling time
Burn-up history (BU/cycle, off reactor cycles )
High fidelity burn-up history (weekly BU history)
Operator calculated isotopics and Isotopics
distribution
Heat generation
Positions in the reactor, location history
Fuel maintenance: Pin replacements and removals,
rebatching
Fuel maintenance operations not affecting NM:
openings, dechanneling, etc.
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Reasonings why data is needed for safeguards
• Some are stipulated by the agreements, they are mandatory
– Amount of NM, batch number, Initial enrichment and burn-up at the assembly level
• Some data is needed for analysis.
– Fuel history, detailed enrichment profiles
• Some data may be useful for result interpretation helping to resolve any inconsistencies
– High fidelity burn-up history
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Data management issues
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Storing the data – how and for how long?
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State of the art data storage ~100 years ago
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At least as long as the repository is active > 100 y
For every fuel element, at least
• Fuel number
• NM Mass
• Fuel history
Safeguards verification data (NDA) shall also be kept but but at which level?
This is subject to investigation.
Future generations should be able to perform (if not all, at least the most important)
analyses, if they want
• The long timelines and requirements for trustworthiness of data place high demands on
the upkeep of the system.
• After the repository is closed and backfilled, the responsibility is transferred to the state
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