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Federico Puente Espel

Ph. D. Student

The Pennsylvania State University
334 Reber Building
University Park, PA 16802

Phone: (814) 321 3637
Email: fup104@psu.edu
Personal Web Page:
Last presentation:
Resume:Please click here to see the resume


Technical Interests:  Hybrid Monte Carlo-based Coupled Core Calculations, Cross-Section Generation Methodologies, Nuclear Depletion Analysis, Reactor Analysis and Fuel Management.

Current Work:

1.- Coupled Hybrid Monte Carlo Based Code System with Thermal-Hydraulic feedback from Cobra-TF

2.- Depletion Analysis with Monte Carlo Based Coupled Code.


Selected List of publications:

  1. F. Puente Espel, M. Avramova, K. Ivanov, S. Misu, “High Accuracy Modeling For Advanced Nuclear Reactor Core Designs Using Monte Carlo Based Coupled Calculations”,  Invited paper for M&C 2009, Saratoga Springs, New York, May 3-7, 2009.
  2. F. Puente Espel, S. Ghrayeb, K. Ivanov, S. Tarantola, “Application of Global Sensitivity Analysis Approach To Exercise I-1 Of The OECD LWR UAM Benchmark”, Invited paper for M&C 2009, Saratoga Springs, New York, May 3-7, 2009.
  3. S. Ghrayeb, K. Ivanov, S. Levine and F. Puente-Espel, Eric P. Loewen, “Improving Burnup Performance of Fast Sodium Cooled Reactor by Utilizing Thorium Based Fuels”,  Invited paper for M&C 2009, Saratoga Springs, New York, May 3-7, 2009.
  4. F. Puente Espel, C. Tippayakul, S. Misu, K. Ivanov,MCOR as a Reference Tool for Benchmarking Spectral Codes”, ANS Winter Meeting 2008, Reno, Nevada, USA.
  5. C. Tippayakul, M. Avramova, F. Puente Espel, K. Ivanov, “Investigations on Monte Carlo Based Coupled Core Calculations,” Proceedings of ICAPP 2007, Nice, France, May 13-18, 2007, Paper 7134.
  6. F. Puente Espel, E. Müller, H. Anglart, “Cell Data Generation for the SPERT III E-core”, Master of Science Thesis, Royal Institute of Technology (KTH), Stockholm, Sweden, Nov. 2004.

Other publications (Companies’ reports)

  1. F. Puente Espel, V. Organai, “Realization, verification and coordination of plant systems’ design base documents and design modifications program for Vandellos II and ASCO I & II NPPs”, Proprietary Report, Westinghouse Technology Services Spain, Tarragona, Spain, Jan. 2006.
  2. F. Puente Espel, E. Müller, “Comparison of POLCA7 and POLCA-T TIP predictions for KKL C19 stability test cases”, Proprietary Report, Westinghouse Electric Sweden AB, Västerås, Sweden, Jan. 2005.
  3. F. Puente Espel, E. Müller, “Investigation of Thermal-Hydraulic effects on reactor simulations performed by 3D core simulator POLCA7”, Proprietary Report, Westinghouse Electric Sweden AB, Västerås, Sweden, Dec. 2004.

 

 

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