Multidimensional Deterministic Nuclear Data Sensitivity and Uncertainty Code System: Method and Application
Author:
Affiliation:
1. Jožef Stefan Institute, Jamova 39, 1111 Ljubljana, Slovenia
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE00-43
Reference31 articles.
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3. R. E. ALCOUFFE, R. S. BAKER, F. W. BRINKLEY, D. R. MARR, R. D. O’DELL, and W. F. WALTERS, “DANT-SYS 3.0—A Diffusion-Accelerated, Neutral-Particle Transport Code System,” LA-12969-M, Los Alamos National Laboratory (June 1995).
4. A cross-section sensitivity and uncertainty analysis of fusion reactor blankets with SAD/SED effect
5. D. E. BARTINE, F. R. MYNATT, and E. M. OBLOW, “SWANLAKE, A Computer Code Utilizing ANISN Radiation Transport Calculations for Cross Section Sensitivity Analysis,” ORNL-TM-3809, Oak Ridge National Laboratory (May 1973).
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