Monte Carlo Perturbation Analysis of Fuel Temperature Variations in the MCNP Model of the Annular Core Research Reactor-Reference-Cited by-同舟云学术

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Monte Carlo Perturbation Analysis of Fuel Temperature Variations in the MCNP Model of the Annular Core Research Reactor

Published:2024-02-09 Issue:6 Volume:210 Page:1015-1026
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Moreno Melissa¹^ORCID,Redhouse Danielle²,Perfetti Christopher³

Affiliation:

1. Sandia National Laboratories, Applied Nuclear Technologies, Graduate R&D Intern, P.O. Box 5800, MS 1146, Albuquerque, New Mexico 87185

2. Sandia National Laboratories, Modeling and Metrology, R&D S&E Nuclear Engineer, P.O. Box 5800, MS 1146, Albuquerque, New Mexico 87185

3. University of New Mexico, Department of Nuclear Engineering, Albuquerque, New Mexico 87106

Publisher

Informa UK Limited

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295450.2023.2274168

Reference10 articles.

1. M. MOTAMED “A Crash Course on Uncertainty Quantification ” Uppsala Universitet/The University of New Mexico (Fall 2018); https://math.unm.edu/~motamed/UQ2018/intro.pdf.

2. J. G. WILLIAMS, D. W. VEHAR, and P. GRIFFIN, “Covariance Matrices for Calculated Neutron Spectra and Measured Dosimeter Responses,” .

3. J. R. TAYLOR, An Introduction to Error Analysis, University Science Books (1997).

4. SCALE Code System

5. MATLAB: The Language of Technical Computing. Desktop Tools and Development Environment, 7th ed. Math Works, Inc. (2005).

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