Issues Related to Long- term Dry Storage of Used Nuclear Fuel · Dry Cask Storage Characterization...

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EI• ELECTRIC POWER RESEARCH INSTITUTE Issues Related to Long- term Dry Storage of Used Nuclear Fuel Nuclear Waste Technical Review Board Meeting Las Vegas NV, 11 June 2009 John Kessler Manager, Used Fuel and HLW Management Program

Transcript of Issues Related to Long- term Dry Storage of Used Nuclear Fuel · Dry Cask Storage Characterization...

Page 1: Issues Related to Long- term Dry Storage of Used Nuclear Fuel · Dry Cask Storage Characterization (DCSC) Project Review" Four-year effort (1999-2002)" Impetus: end of the initial

EI• ELECTRIC POWERRESEARCH INSTITUTE

Issues Related to Long-term Dry Storage of UsedNuclear Fuel

Nuclear Waste Technical Review BoardMeetingLas Vegas NV, 11 June 2009

John KesslerManager, Used Fuel and HLWManagement Program

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Outline

" Dry cask storage system functions" Dry Cask Storage Characterization Project (DCSC)

review

* Potential long-term degradation mechanisms

* EPRI plans for future work

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Functions of a Dry Cask Storage System thatMust be Maintained

* NUREG-1536 (NRC, 1997) identifies the functionsimportant to safety that the dry cask systems mustmaintain:- thermal performance

- radiological protection

- confinement- sub-criticality- retrievability

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Dry Cask Storage Characterization (DCSC)Project Review

" Four-year effort (1999-2002)

" Impetus: end of the initial 20-year licenses (2006)

" Investigation of Castor V/21 cask at INL

- In dry storage for 15 years

- Represented the lead (spent) fuel in dry storage in the U.S.

" Co-funded by NRC-Research, EPRI, DOE-RW, DOE-EM

" Documented in EPRI reports:

- Interim report 1000157 (2000)

- Interim report 1003010 (2001)

- Final report 1002882 (2002)

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DCSC Project Tasks

" Reopen Castor V/21 at INL- Cask cavity gas analysis- External dose rate measurements- Visual inspection of assemblies and cask internals

- Remove rods from assembly in Castor at INL

" Rod testing at ANL- Profilometry at ANL-West

- Rod puncturing for fission gas release at ANL-West- Destructive exams of Zircaloy at ANL-East

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Castor V/21 on TransporterHeaded to ot Shop

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DCSC Profilometry: No Evidence of CreepDuring Storage

The nominal as-fabricated cladding outer diameter is 10.72 mm.

EE.

E

CUc,)

1 0.75

1 0.70

10.65

10.60

0 500 1000 1500 2000 2500 3000 3500 4000

Location (mm, from rod bottom)

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DCSC: Morphology of Hydrides MostlyCircumferential -----------

Mid plane 0.5m above mid planeElECTRIC POWER

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Main Conclusions from the Four-Year DCSCEffort

" No cask functional degradation observed

" Assemblies still look the same- No sticking; no significant bowing upon removal

- No visual signs of degradation (color, oxide, damage)

" No leaks during storage

" No significant additional fission gas release to rodinternals

" No significant hydride reorientation

, Zero to minuscule creep during storage" "Creep life" remains

• Result: basis for license extensions out to --60 years

" Most severe conditions are during first 20 years© eELECTRIC POWER

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Examples ofAddress

Issues the DSCS Program did not

" High burnup used fuel" Long-term concrete degradatione Effect of marine environments (examined in EPRI

1011820, September 2005)report

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Review of Potential Degradation MechanismsOutline (from EPRI report 1003416, December 2002)

III II - ,. .Mechanism Claddingj~%.~.

Initial ExtendedI • Initial ExtendedNormalOxidation N Nfgr Y NCreep, Y NDCCG N NH2 reorientation Y NDHC N NSCC maybeH2 embrittlement NH2 migration Y N%4_ __

Annealing Y NCrud Spallation maybe NOff-Normal __ _

Oxidation due to air Y Yingress UCreep Y DEAnnealing Y DEAccident-impactFracture DE DEOxidation DE DEImpact Breach DE DECrud spallation DE DEAccident-fire ____

Stress rupture YAnnealing Y YH2 reorientation YDHC = Delayed Hydrogen CrackingDCCG = Diffusion Controlled Cavitation GrowthFgr = fission gas releaseSCC = Stress Corrosion Cracking

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Temperature-related Dry Storage SystemDegradation Mechanisms

'7NEI

* Fuel cladding creep caused by increased claddingductility and increased stress- Due to higher temperatures causing higher pressures inside the

cladding

" Hydride reorientation in the spent

" Corrosion* Degradation of neutron shielding

* Concrete dry-out and cracking

fuel cladding

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Changes as the System gets Cooler

" Mostly good things

-Reduced metal creep rates

- Reduced corrosion rates

-Reduced gamma and neutron radiation

" Potential negatives (mostly related to cladding)

-Additional hydride precipitation

Decreased ductility

* Potentially more susceptible to breakageduring storage and transportation

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Reduced Degradation with Time does not MeanDegradation Stops

* Corrosion (in oxidizing environments)

" Helium buildup inside fuel rods

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Aging Management Options

* "Initial" activities- Additional analyses to extend progress of degradation

mechanisms- Enhanced monitoring and

" "Eventually"

- Canning- Repackaging

- Over-packaging

• When is "eventually"?

inspection

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Potential Sequence of Events for Extended DryStorage (from EPRI report TR-1 08757, 1998, assumes 100-yr storage)

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Potential Sequence of Events for Extended DryStorage After an Accident Event

no effect

Continue DryStorage

fuel damaged cask OK

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Potential EPRI Work on Very Long-term Used[7 Fuel Storage and Transportation Issues

" Workshop (Fall 2009)* "Paper" analyses

• Experimental (with others?)* Licensing issues* Operational issues

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Together...Shaping the Future of Electricity

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