Most of the dry storage cask systems that are used to contain nuclear fuel are austenitic stainless steel canisters. Past experience suggests that stainless steel is susceptible to stress corrosion cracking (SCC) in the presence of chloride salts. A crack growth rate (CGR) model has been developed and applied to evaluate the crack depth in stainless steel canisters over the timeframe of the storage at independent spent fuel storage installations. This study focuses on stainless steel canisters for dry storage systems in the two nuclear power plants in Taiwan. The crack depth was first evaluated using the CGR model, site climate data, and canister surface temperature. The critical crack size and depth were then determined from the structural tolerance assessment of the canister shells. It was found that the variations in the thermal and hydraulic properties of dry storage canisters produce large variations in the SCC initiation time but do not affect the surface temperature in the range of 55–60 °C. The CGR at the SCC initiation is high and the growth of flaws is significant. The surface temperature and CGR decrease with time. The total crack depth therefore may not vary greatly as a function of SCC initiation time. Overall, dry storage canisters show high structural tolerance to crack size and depth.

Issue Section:
Special Section Papers
Keywords:
Plant Systems, Risk informed applications for nuclear engineering, Systems reliability, Thermal hydraulics, Construction, Structures, Components, Systems performance

References

1.
EPRI
,
2013
, “
Failure Modes and Effects Analysis (FMEA) of Welded Stainless Steel Canisters for Dry Cask Storage Systems
,” Electric Power Research Institute, Palo Alto, CA, Report No.
3002000815
.https://www.epri.com/#/pages/product/000000003002000815/
2.
EPRI
,
2013
, “
Flaw Growth and Flaw Tolerance Assessment for Dry Cask Storage Canisters
,” Electric Power Research Institute, Palo Alto, CA, Report No.
3002002785
https://www.epri.com/#/pages/product/000000003002002785/.
3.
ASME
,
2013
, “
ASME Boiler and Pressure Vessel Code Section XI
,” American Society of Mechanical Engineers, New York.
4.
Shirai
,
K.
,
Tani
,
J.
, and
Saegua
,
T.
,
2011
, “
Study on Interim Storage of Spent Nuclear Fuel by Concrete Cask for Practical Use—Feasibility Study on Prevention of Chloride Induced Stress Corrosion Cracking for Type 304 L Stainless Steel Canister
,” Central Research Institute of Electric Power Industry, Tokyo, Japan, Technical Report No. N10035 (in Japanese).
5.
Tani
,
J.
,
2009
, “
Initiation and Propagation of Stress Corrosion Cracking of Stainless Steel for Concrete Cask Storage of Spent Nuclear Fuel
,”
Corrosion
,
65
(
3
), pp.
187
–
194
.
Google Scholar
Crossref
Search ADS
 
6.
Shirai
,
K.
,
Tani
,
J.
,
Arai
,
T.
, and
Winston
,
P.
,
2008
, “
Research on Spent Fuel Storage and Transportation in CRIEPI—Part 2: Concrete Cask Storage
,” 16th Pacific Basin Nuclear Conference (16PBNC), Aomori, Japan, Oct. 13–18, Paper No.
P16P1215
.https://inis.iaea.org/search/search.aspx?orig_q=RN:41004440
7.
Hayashibara
,
H.
,
Mayuzumi
,
M.
,
Mizutani
,
Y.
, and
Tani
,
J.
,
2008
, “
Effects of Temperature and Humidity on Atmospheric Stress Corrosion Cracking of 304 Stainless Steel
,”
Corrosion
, New Orleans, LA, Mar. 16–20, pp. 4375–4383.https://www.onepetro.org/conference-paper/NACE-08492?sort=&start=0&q=Effects+of+Temperature+and+Humidity+on+Atmospheric+Stress+Corrosion+Cracking+of+AISI+304+Stainless+Steel&from_year=&peer_reviewed=&published_between=&fromSearchResults=true&to_year=&rows=10#
8.
Bechtel SAIC
,
2005
, “
Analysis of Dust Deliquescence for FEP Screening
,” Bechtel SAIC Company, LLC, McLean, VA, Technical Report No.
ANL-EBS-MD-000074, Rev. 01
.https://curie.ornl.gov/content/analysis-dust-deliquescence-fep-screening-1
9.
Chang
,
H. Y.
,
2013
, “
A Study on Stress Corrosion of Stainless Steel and Methodologies for Reducing the Susceptibility
,” FCMA, New Taipei City, Taiwan, Technical Report No. 102FCMA003 (in Chinese).
10.
Shih
,
C. K.
, and
Tseng
,
Y. S.
,
2014
, “
Thermal-Hydraulic Analysis of Design Lifetime Behaviors of Dry storage Systems
,” FCMA, New Taipei City, Taiwan, Technical Report No. 103FCMA001 (in Chinese).
11.
Shih
,
C. K.
,
2015
, “
Thermal-Hydraulic Analysis of Design Lifetime Behaviors of Drystorage Systems in the 2nd Nuclear Power Plant
,” FCMA, New Taipei City, Taiwan, Technical Report No. 104FCMA011 (in Chinese).
12.
Patko, A. L.,
2007
, “
Final Safety Analysis Report for the UMS® Universal Transport Cask, Rev. 6.C
,” NAC International Inc., Norcross, GA, Report No. ML041040369.
13.
Patko, A. L.,
2013
, “
Final Safety Analysis Report (FSAR) for the NAC MAGNASTOR® Cask System, Rev. 4
,” NAC International Inc., Norcross, GA, Report No. ML091000633.
14.
Liu
,
C. T.
, and
Huang
,
C. T.
,
2007
, “
Management of Spent Fuel Nuclear Dry Storage in Taiwan
,”
15th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 2007)
, Miami, FL, Oct. 21–26.
15.
EPRI
,
2014
, “
Calvert Cliff Stainless Steel Dry Storage Canister Inspection
,” Electric Power Research Institute, Palo Alto, CA, Report No.
1025209
.https://www.epri.com/#/pages/product/000000000001025209/
16.
Bryan, C.,
2013
, “
Data Report on Corrosion Testing of Stainless Steel SNF Storage Canisters
,” Technical Report Prepared for U.S. Department of Energy Used Fuel Disposition Campaign, Sandia National Laboratories (SNL), Livermore, CA, Technical Report No.
SAND2013-8314P
.https://www.energy.gov/sites/prod/files/2013/12/f5/CorrosionTestStainlessSteelSNFStorContainer.pdf
17.
Bryan, C.,
2014
, “
Results of Stainless Steel Canister Corrosion Studies and Environmental Sample Investigations
,” Technical Report Prepared for U.S. Department of Energy Used Fuel Disposition Program, SNL, Livermore, CA, Technical Report No.
SAND2014-20347O
.https://www.energy.gov/sites/prod/files/2015/05/f22/FCRDUFD2014000055CanisterCorrosionnStud.pdf
18.
Wataru
,
M.
,
Kato
,
H.
,
Kudo
,
S.
,
Oshima
,
N.
,
Wada
,
K.
, and
Takahashi
,
T.
,
2007
, “
Evaluation on the Atmospheric Sea Salt Concentration for Practical Use of the Dry Storage Facility Using the Concrete Cask
,” Central Research Institute of Electric Power Industry, Tokyo, Japan, Technical Report No. N06022 (in Japanese).
19.
Wataru
,
M.
, and
Saegura
,
T.
,
2010
, “
Evaluation of the Salt Deposition on the Canister Surface of Concrete Cask—Measurement Test of the Salt Deposition in the Laboratory and the Field
,” Central Research Institute of Electric Power Industry, Tokyo, Japan, Technical Report No. N09023 (in Japanese).
20.
Wataru
,
M.
, and
Takeda
,
H.
,
2015
, “
Evaluation of the Salt Deposition on the Canister Surface of Concrete Cask—Part 3: Long-Term Measurement of Salt Concentration in Air and Evaluation of the Salt Deposition
,” Central Research Institute of Electric Power Industry, Tokyo, Japan, Technical Report No. N14019 (in Japanese).
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