Many-Group Cross-Section Adjustment Techniques for Boiling Water Reactor Adaptive Simulation-Reference-Cited by-同舟云学术

Many-Group Cross-Section Adjustment Techniques for Boiling Water Reactor Adaptive Simulation

Published:2011-09 Issue:1 Volume:169 Page:40-55
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Jessee M. A.¹,Turinsky P. J.¹,Abdel-Khalik H. S.¹

Affiliation:

1. North Carolina State University, Department of Nuclear Engineering Campus Box 7909, Raleigh, North Carolina 27695-7909

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE09-67

Reference13 articles.

1. “SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluations,” ORNL/TM-2005/39, Version 5.1, Vols. I–III (Nov. 2006); available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-732.

2. FORMOSA-B: A Boiling Water Reactor In-Core Fuel Management Optimization Package

3. Y. RONEN, Uncertainty Analysis, CRC Press Inc., Boca Raton, Florida (1988).

4. Efficient Subspace Methods-Based Algorithms for Performing Sensitivity, Uncertainty, and Adaptive Simulation of Large-Scale Computational Models

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