Automatic Rapid Process for the Generation of Problem-Dependent SAS2H/ORIGEN-S Cross-Section Libraries

Author:

Leal Luiz C.1,Hermann Otto W.1,Bowman Stephen M.1,Parks Cecil V.1

Affiliation:

1. Oak Ridge National Laboratory Computational Physics and Engineering Division, Building 6011 Mail Stop 6370, P.O. Box 2008, Oak Ridge, Tennessee 37831-6370

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference7 articles.

1. “Characteristics of Spent Fuel, High-Level Waste, and Other Radioactive Wastes Which May Require Long-Term Isolation,” DOE-RW-0184, U.S. Department of Energy.

2. O. W. HERMANN and R. M. WESTFALL, “ORIGEN-S: SCALE System Module to Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buildup and Decay, and Associated Radiation Source Terms,” Vol. II, Sec. F7 of “SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation,” NUREG/CR-0200, Rev. 5 (ORNL/NUREG/CSD-2R5) (Mar. 1997). Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-545.

3. O. W. HERMANN, S. M. BOWMAN, M. C. BRADY, and C. V. PARKS, “Validation of the SCALE System for PWR Spent Fuel Isotopic Composition Analysis,” ORNL/TM-12667, Oak Ridge National Laboratory (Mar. 1995).

4. O. W. HERMANN and M. D. DEHART, “Validation of SCALE (SAS2H) Isotopic Predictions for BWR Spent Fuel,” ORNL/TM-13315, Oak Ridge National Laboratory (1998).

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