Resonance self-shielding methodologies in SCALE 6

Nuclear Technology

Volumn 174, Issue 2, 2011, Pages 149-168

  Williams, Mark L ^a  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

Continuous energy discrete ordinates; SCALE; Self shielding

Indexed keywords

RESONANCE;

DETERMINISTIC CALCULATIONS; DISCRETE ORDINATES; EVALUATED NUCLEAR DATA FILE; NEUTRON TRANSPORT CALCULATIONS; SCALE; SELF-SHIELDING; TRANSPORT CALCULATION; VERIFICATION-AND-VALIDATION;

SHIELDING;

EID: 79959247554     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT09-104     Document Type: Article

References (27)

1. "SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation," ORNLTM/2005/39, Version 6, Vols. I, II, and III (2009);
2. see also CCC-750, Radiation Safety Information Computational Center at Oak Ridge National Laboratory.
3. M. E. DUNN and N. M. GREENE, "AMPX-2000: A CrossSection Processing System for Generating Nuclear Data for Criticality Safety Applications," Trans. Am. Nucl. Soc., 86,118 (2002).
4. A. F. HENRY, Nuclear Reactor Analysis, MIT Press, Cambridge, Massachusetts (1982).
5. Group Constants for Nuclear Reactor Calculations, I. I. BONDARENKO, Ed., Consultants Bureau, New York (1964).
6. S. GOLUOGLU and M. L. WILLIAMS, "Modeling Doubly Heterogeneous Systems in SCALE," Trans. Am. Nucl. Soc., 93, 767 (2005).
7. M. D. DeHART, I. C. GAULD, and M. L. WILLIAMS, "High-Fidelity Lattice Physics Capabilities of the SCALE Code System Using TRITON," Proc. Joint Int. Topi. Mtg. Mathematics & Computation and Supercomputing in Nuclear Applications (M&C + SNA2007), April 15-19, 2007.
8. T. M. EVANS, A. S. STAFFORD, R. N. SLAYBAUGH, and K. T. CLARNO, "Denovo: A New Three-Dimensional Parallel Discrete Ordinates Code in SCALE," Nucl. Technol., 171, 171 (2010).
9. G. I. BELL and S. GLASSTONE, Nuclear Reactor Theory, Van Nostrand, Princeton, New Jersey (1970).
10. M. L. WILLIAMS and M. ASGARI, "Computation of Continuous-Energy Neutron Spectra with Discrete Ordinates Transport Theory," Nucl. Sci. Eng., 121, 173 (1995).
11. W. ROTHENSTEIN, "Collision Probabilities and Resonance Integrals for Lattices," Nucl. Sci. Eng., 7, 162 (1960).
12. K. M. CASE, F. DE HOFFMANN, and G. PLACZEK, Introduction to the Theory of Neutron Diffusion, Los Alamos Scientific Laboratory (1953).
13. J. R. KNIGHT, "SUPERDAN: Computer Programs for Calculating the Dancoff Factor of Spheres, Cylinders, and Slabs," ORNL/CSD/TM-37, Union Carbide Corporation (Nuclear Division), Oak Ridge National Laboratory (1978).
14. L. W. NORDHEIM, "The Theory of Resonance Absorption," Proc. Symp. Applied Mathematics, Vol. XI, p. 58, G. BIRKHOFF and E. P. WIGNER, Eds., American Mathematical Society (1961).
15. M. B. CHADWICK et al., "ENDF/B-VII.0 Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology," Nucl. Data Sheets, 107, 12, 2931 (2006).
16. M. L. WILLIAMS, "Submoment Expansion of NeutronScattering Sources," Nucl. Sci. Eng., 134, 218 (2000).
17. "Handbook of Mathematical Functions," Appl. Math. Ser., 55, M. ABRAMOWITZ and I. A. STEGUN, Eds., National Bureau of Standards (1964).
18. H. C. HONECK and D. R. FINCH, "FLANGE-II, A Code to Process Thermal Neutron Data from an ENDF/B Tape," DP-1278 (ENDF-152), Du Pont De Nemours Company, Savannah River Laboratory (1971).
19. "ENDF/B-6 Formats Manual: Data Formats and Procedures for the Evaluated Nuclear Data Files ENDF/B-VI and ENDF/B-VII," BNL-NCS-44945-05-Rev, Document ENDF102, M. HERMAN, Ed., Brookhaven National Laboratory (2005).
20. R. J. DOYAS and S. T. PERKINS, "Interpolation of Tabular Secondary Neutron and Photon Energy Distributions," Nucl. Sci. Eng., 50, 390 (1973).
21. G. S. ROBINSON, "Notes on the AAEC Version of XLACSII," Australian Atomic Energy Commission (1981).
22. K. T. CLARNO et al., "Code-to-Code Benchmark of Coolant Void Reactivity (CVR) in the ACR-700 Reactor," Trans. Am. Nucl. Soc., 92, 525 (2005).
23. "MCNP-A General Monte Carlo Code N-Particle Transport Code, Version 4C," LA-13709-M, J. F. BRIESMEISTER, Ed., Los Alamos National Laboratory (2000).
24. S. C. VAN DER MARCK, "Benchmarking ENDF/BVII.0," Nucl. Data Sheets, 107, 12, 3061(2006).
25. "International Handbook of Evaluated Criticality Safety Benchmark Experiments," NEA/NSC/DOC(95) 03/1, Nuclear Energy Agency (Sep. 2008).
26. M. L WILLIAMS and G. ILAS, "ENDF/B-VII Nuclear Data Libraries for SCALE 6," Proc. Advances in Nuclear Fuel Management IV (ANFM 2009), Hilton Head Island, South Carolina, April 12-15, 2009.
27. D. ILAS and J. C. GEHIN, "HTTR Fuel Block Simulations with Scale," Proc. Advances in Reactor Physics to Power the Nuclear Renaissance (PHYSOR 2010), Pittsburgh, Pennsylvania, May 9-14, 2010.