CIEMAT response to challenges on fuel safety research during dry storage
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Abstract
The research on safety of dry stored nuclear fuel poses a number of challenges related to understand and predict its performance under the anticipated conditions. The ultimate goal is the development of analytical capabilities for predicting the integrity of the fuel rod. In this regard, the research carried out by the Unit of Nuclear Safety Research of CIEMAT is enabling the use of predictive tools and analysis methodologies whereby safety conditions can be assessed. To do so, the experience gained in fuel rod thermal-mechanics in reactor is used as a basis; particularly, the fuel performance code FRAPCON is being extended to the dry storage technology, called FRAPCON-xt. This paper shows the work carried out so far, including some applications on aspects related to cladding embrittlement due to hydrides as one of the main concerns.
Kurzfassung
Die Forschung zur Sicherheit von trocken gelagerten Kernbrennstoffen stellt eine Reihe von Herausforderungen im Zusammenhang mit dem Verständnis und der Vorhersage ihrer Leistung unter den erwarteten Bedingungen dar. Das Ziel ist die Entwicklung von analytischen Möglichkeiten zur Vorhersage der Integrität des Brennstabes. In diesem Zusammenhang ermöglichen die Arbeiten der CIEMAT-Gruppe „Nukleare Sicherheitsforschung“ den Einsatz von vorhersagenden Instrumenten und Analysemethoden, mit denen die Sicherheitsbedingungen bewertet werden können. Dabei werden die Erfahrungen aus der Brennstab-Thermomechanik innerhalb von Reaktoren zugrunde gelegt, insbesondere wird der Brennstoffleistungscode FRAPCON auf die Trockenspeichertechnologie FRAPCON-xt erweitert. Dieses Papier zeigt die bisher geleisteten Arbeiten, einschließlich einiger Anwendungen zu Aspekten der Versprödung von Brennstoffhüllen durch Hydride.
References
1 USNRC: 10 CFR Part 72, 2000Search in Google Scholar
2 Hanson, B.; Alsaed, H.; Stockman, C.; Enos, D.; Meyer, R.; Sorenson, K.: Gap analysis to support extended storage of used nuclear fuel. PNNL-20509, 2012Search in Google Scholar
3 USNRC: Spent Fuel Project Office Interim Staff Guidance No. 11 (ISG-11, rev 3), 2003Search in Google Scholar
4 USNRC: Spent Fuel Project Office Interim Staff Guidance No. 22 (ISG-22), 2006Search in Google Scholar
5 Nissen, K. L.: Mechanical properties of used fuel rod cladding relevant to dry storage licensing. Annual Meeting of the Spanish Nuclear Society, 2017Search in Google Scholar
6 NEA: Review of Uncertainty Methods for Computational Fluid Dynamics Application to Nuclear Reactor Thermal Hydraulics. NEA/CSNI/R(2016)4, 2016Search in Google Scholar
7 NEA: Premium: A Benchmark on the Quantification of the Uncertainty of the Physical Models in System Thermal-hydraulic Codes: Methodologies and Data Review. NEA/CSNI/R(2016)9, 2016.Search in Google Scholar
8 Geelhood, K. J., Luscher, W. G., Raynaud, P. A., Porter, I. E: FRAPCON-4.0: A Computer Code for the Calculation of Steady-State, Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup. PNNL-19418, Vol.1 Rev. 2., 2015.Search in Google Scholar
9 Herranz, L. E., Feria, F: Extension of the FRAPCON-3.3 creep model to dry storage conditions. Progress in Nuclear Energy, 52 (2010), pp. 634–63910.1016/j.pnucene.2010.04.003Search in Google Scholar
10 Feria, F.; Herranz, L. E.: Creep assessment of Zry-4 cladded high burnup fuel under dry storage, Progress in Nuclear Energy53 (2011) 395–40010.1016/j.pnucene.2011.01.012Search in Google Scholar
11 Feria, F.; Herranz, L. E.: On the way to enabling FRAPCON-3 to model spent fuel under dry storage conditions: The thermal evolution, Annals of Nuclear Energy85 (2015) 995–100210.1016/j.anucene.2015.07.017Search in Google Scholar
12 Feria, F.; Herranz, L. E.: Effect of the oxidation front penetration on in-clad hydrogen migration, Journal of Nuclear Materials500 (2018) 349–36010.1016/j.jnucmat.2018.01.011Search in Google Scholar
13 Herranz, L. E.; Feria, F.: Spent fuel rod splitting due to UO2 oxidation during dry storage: assessment of the database, Progress in Nuclear Energy51 (2009) 201–20610.1016/j.pnucene.2008.09.006Search in Google Scholar
14 Ito, K.; Kamimura, K.; Tsukuda, Y.: Evaluation of irradiation effect on spent fuel cladding creep properties. Proceedings of the 2004 International Meeting on LWR Fuel Performance, 19–22Search in Google Scholar
15 Bouffioux, P.: Transportation and interim dry storage of PWR's spent fuel. EDF report, HT25-C2005-192/PBF, 2005Search in Google Scholar
16 Herranz, L. E.; Penalva, J.; Feria, F.: CFD analysis of a cask for spent fuel dry storage: Model fundamentals and sensitivity studies, Annals of Nuclear Energy76 (2015) 54–6210.1016/j.anucene.2014.09.032Search in Google Scholar
17 AlvarezR.; Beyea, J.; Janberg, K.; Kang, J.; Lyman, E.; Macfarlane, A.; Thompson, G.; Von Hippel, F. N.: Reducing the Hazards from Stored Spent Power-Reactor Fuel in the United States, Science and Global Security11 (2003) 1–5110.1080/08929880309006Search in Google Scholar
18 McMinn, J. S.; Darby, A.; Schofield, E. C.: The terminal solid solubility of hydrogen in zirconium alloys. in: 12th Int. Symp. Zr Nucl. Ind. Toronto, CA, 2000: pp. 173–19510.1520/STP14300SSearch in Google Scholar
19 Kammenzind, W. J.; Franklin, B.; Peters, D. G.; Duffin, H. R.: Hydrogen pickup and redistribution in alpha-annealed Zircaloy-4. in: 11th Int. Symp. Zircon. Nucl. Ind. ASTM STP1295., 1997: pp. 338–369Search in Google Scholar
20 Tupin, M.; Bisor, C.; Bossis, P.; Chêne, J.; Bechade, J. L.; Jomard, F.: Mechanism of corrosion of zirconium hydride and impact of precipitated hydrides on the Zircaloy-4 corrosion behavior. Corros, Sci.98 (2015) 478–49310.1016/j.corsci.2015.05.058Search in Google Scholar
21 Sahle, W.: PIE of CIP0-1 father rod: cladding oxide and hydride measurement in SEM, N(H)-02/027 rev.2 (2010)Search in Google Scholar
22 Stafford, D. S.: Multidimensional simulations of hydrides during fuel rod lifecycle. J. Nucl, Mater.466 (2015) 362–37210.1016/j.jnucmat.2015.06.037Search in Google Scholar
23 Veshchunov, M. S.; Shestak, V. E.; Ozrin, V. D.: A new model of hydrogen redistribution in Zr alloy claddings during waterside corrosion in a temperature gradient. J. Nucl, Mater.472 (2016) 65–7510.1016/j.jnucmat.2016.01.032Search in Google Scholar
24 Adams, B. M.; Ebeida, M. S.; Eldred, M. S.; Jakeman, J. D.; Swiler, L. P.; Stephens, J. A.; Vigil, D. M.; Wildey, T. M.; Bohnhoff, W. J.; Dalbey, K. R.; Eddy, J. P.; Hu, K. T.; Bauman, L. E.; Hough, P. D.: Dakota, A Multilevel Parallel Object-Oriented Framework for Design Optimization, Parameter Estimation, Uncertainty Quantification, and Sensitivity Analysis, Version 6.2. Reference Manual. SAND2014-5015. 201410.2172/1177048Search in Google Scholar
25 Feria, F.; Herranz, L. E.: Application of the BEPU methodology to assess fuel performance in dry storage, Annals of Nuclear Energy99 (2017) 240–24610.1016/j.anucene.2016.08.029Search in Google Scholar
26 Feria, F.; Aguado, C.; Herranz, L. E.: Comparison of uncertainty assessment methods applied to the thermo-mechanical characterization of fuel at the beginning of dry storage. ANS Best Estimate Plus Uncertainty International Conference, Lucca, May 13–19, 2018Search in Google Scholar
27 O'Donnell, G. M.; Scott, H. H.; Meyer, R. O.: Comparative Analysis of Fuel Designs. NUREG-1754 (2001)Search in Google Scholar
28 Une, K.; Ishimoto, S.; Etoh, Y.; Ito, K.; Ogata, K.; Baba, T.; Kamimura, K.; Kobayashi, Y.: The terminal solid solubility of hydrogen in irradiated Zircaloy-2 and microscopic modeling of hydride behavior. J. Nucl, Mater.389 (2009) 127–13610.1016/j.jnucmat.2009.01.017Search in Google Scholar
29 Courty, O. F.; Motta, A. T.; Piotrowski, C. J.; Almer, J. D.: Hydride precipitation kinetics in Zircaloy-4 studied using synchrotron X-ray diffraction. J. Nucl, Mater.46 (2015), pp. 180–18510.1016/j.jnucmat.2015.02.035Search in Google Scholar
30 Wensauer, A.; Distler, I.; Heins, L.: Probabilistic uncertainty analysis applied to fuel rod design, probabilistic safety assessment and management. PSAM 7-ESREL ’04, Volume 5, Springer (2004)10.1007/978-0-85729-410-4_447Search in Google Scholar
31 Lurie, D.; Abramson, L.; Vail, J.: Applying Statistics, NUREG-1475, Revision1 (2011)Search in Google Scholar
© 2018, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Editorial
- Safety of extended dry storage of spent nuclear fuel – GRS workshop 2018
- Technical Contributions/Fachbeiträge
- CIEMAT response to challenges on fuel safety research during dry storage
- Research activities at GRS on fuel rod behaviour during extended dry storage
- Open questions on the road to reliable predictions of cladding integrity
- Considerations on spent fuel behavior for transport after extended storage
- Investigations of the hydrogen diffusion and distribution in Zirconium by means of Neutron Imaging
- Effect of Zirconium Hydrides on the mechanical behavior of cladding
- Response of irradiated nuclear fuel rods to quasi-static and dynamic loads
- Investigations on potential methods for the long-term monitoring of the state of fuel elements in dry storage casks
Articles in the same Issue
- Contents/Inhalt
- Contents
- Editorial
- Safety of extended dry storage of spent nuclear fuel – GRS workshop 2018
- Technical Contributions/Fachbeiträge
- CIEMAT response to challenges on fuel safety research during dry storage
- Research activities at GRS on fuel rod behaviour during extended dry storage
- Open questions on the road to reliable predictions of cladding integrity
- Considerations on spent fuel behavior for transport after extended storage
- Investigations of the hydrogen diffusion and distribution in Zirconium by means of Neutron Imaging
- Effect of Zirconium Hydrides on the mechanical behavior of cladding
- Response of irradiated nuclear fuel rods to quasi-static and dynamic loads
- Investigations on potential methods for the long-term monitoring of the state of fuel elements in dry storage casks
