High-fidelity depletion capabilities of the scale code system using triton

Transactions of the American Nuclear Society

Volumn 97, Issue , 2007, Pages 598-600

  DeHart, Mark D ^a  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 55349133370     PISSN: 0003018X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (10)

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2. M. D. DeHART, "Advancements in Generalized Geometry Discrete Ordinates Transport for Lattice Physics Calculations," Proc. PHYSOR-2006, Vancouver, British Columbia, Canada, Sept. 10-14 (2006).
3. M. D. DeHART and A. P. ULSES. "Lattice Physics Capabilities of the SCALE Code System Using TRITON," Proc. PHYSOR-2006, Vancouver, British Columbia, Canada, Sept. 10-14 (2006).
4. SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, ORNL/TM-2005/39, Version 5, Vols. I-III, April 2005. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-725.
5. B. D. MURPHY, ORIGEN-ARP Cross-Section Libraries for Magnox, Advanced Gas-Cooled, and WER Reactor Designs, ORNL/TM-2003/263, UT-Battelle, LLC, Oak Ridge National Laboratory (February 2004).
6. S. M. BOWMAN and D. F. GILL, "Validation of SCALE/TRITON 2-D and 3-D Models for LWR Fuel," Proc. PHYSOR-2006, Vancouver, British Columbia, Canada, Sept. 10-14 (2006).
7. K. T. CLARNO et al., "Code-to-Code Benchmark of Coolant Void Reactivity (CVR) in the ACR-700 reactor," Presented at 2005 ANS Winter Meeting, "Talk About Nuclear Differently: A Good Story Untold," Washington, D.C., Nov. 13-17, 2005. Trans. Am. Nucl. Soc., 93, 977-980 (2005).
8. G. ILAS, I. C. GAULD, "Analysis of Decay Heat Measurements for BWR Fuel Assemblies," presented at Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, Reno, Nevada, June 4-8, 2006. Trans. Am. Nucl. Soc., 94, 385-387 (2006).
9. M. D. DeHART and A. P. ULSES, "Lattice Physics Capabilities of the SCALE Code System Using TRITON," Proc. of PHYSOR-2006, Vancouver, British Columbia, Canada, Sept. 10-14 (2006).
10. A. YAMAMOTO et al., "Benchmark Problem Suite for Reactor Physics Study of LWR Next Generation Fuels," J. Nucl. Sci. Technol. 39 (8), 900-912 (2002).