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Herranz LE, Sánchez F, Gupta S. Validation Matrix for Pool Scrubbing Models. NUCL TECHNOL 2022. [DOI: 10.1080/00295450.2022.2122679] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/07/2022]
Affiliation(s)
- L. E. Herranz
- CIEMAT, Research Unit on Nuclear Safety, Madrid, Spain
| | - F. Sánchez
- CIEMAT, Research Unit on Nuclear Safety, Madrid, Spain
| | - S. Gupta
- Becker Technologies, Frankfurt, Germany
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Aguado C, Feria F, Herranz LE. Major sensitivities in FRAPCON-xt modeling of high burn-up fuel rods during dry storage to design and irradiation variables. KERNTECHNIK 2021. [DOI: 10.3139/124.200069] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
Abstract
Abstract
Thermo-mechanical performance of fuel rods is a key aspect for assessing the spent fuel safety during dry storage. There is a need of assessing fuel rod behaviour codes for dry storage stage and uncertainty quantification can be a useful tool for this assessment. As a first step of these studies, sensitivity analyses can help to understand the effects and to identify the relevant parameters for the predictions. The present work studies the effect of the scenario on sensitivity analyses focused on the cladding stress at the beginning of dry storage. To make this comparison 10 design parameter’s tolerances and 7 model biases have been studied for 2 different fuel rods in terms of design and irradiation. Cladding diameter tolerance and fuel gas release and thermal conductivity model biases are the more influencing parameters independently of the scenario chosen. Overall, moderate differences between scenarios have been obtained. Results obtained in this work are specifically related to the modelling of the code FRAPCON-xt.
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Feria F, Penalva J, Aguado C, Herranz LE. CIEMAT response to challenges on fuel safety research during dry storage. KERNTECHNIK 2018. [DOI: 10.3139/124.110945] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
Abstract
AbstractThe 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.
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Affiliation(s)
- F. Feria
- 1CIEMAT, Avda Complutense 40, Madrid, Spain
| | - J. Penalva
- 1CIEMAT, Avda Complutense 40, Madrid, Spain
| | - C. Aguado
- 1CIEMAT, Avda Complutense 40, Madrid, Spain
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Pellegrini M, Dolganov K, Herranz LE, Bonneville H, Luxat D, Sonnenkalb M, Ishikawa J, Song JH, Gauntt RO, Moguel LF, Payot F, Nishi Y. Benchmark Study of the Accident at the Fukushima Daiichi NPS: Best-Estimate Case Comparison. NUCL TECHNOL 2017. [DOI: 10.13182/nt16-63] [Citation(s) in RCA: 35] [Impact Index Per Article: 5.0] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
| | - K. Dolganov
- Nuclear Safety Institute of the Russian Academy of Sciences (IBRAE), Moscow, Russia
| | - L. E. Herranz
- Centro de Investigaciones Energéticas MedioAmbientales y Tecnológicas (CIEMAT), Madrid, Spain
| | - H. Bonneville
- Institut de Radioprotection et de Sùreté Nucléaire (IRSN), Fontenay-aux-Roses, France
| | - D. Luxat
- Institut de Radioprotection et de Sùreté Nucléaire (IRSN), Fontenay-aux-Roses, France
| | - M. Sonnenkalb
- Gesellschaft für Anlagen- und Reaktorsicherheit (GRS), Cologne, Germany
| | - J. Ishikawa
- Japan Atomic Energy Agency (JAEA), Tokyo, Japan
| | - J. H. Song
- Korea Atomic Energy Research Institute (KAERI), Daejeon, Korea
| | - R. O. Gauntt
- Sandia National Laboratories (SNL), Albuquerque, New Mexico
| | | | - F. Payot
- Korea Atomic Energy Research Institute (KAERI), Daejeon, Korea
| | - Y. Nishi
- Central Research Institute of Electric Power Industry (CRIEPI), Tokyo, Japan
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