11. AMPX-6: A Modular Code System for Processing ENDF/B Evaluations
AMPX is a modular system of computer programs used for nuclear analysis with a primary emphasis on tasks associated with the production and use of multigroup (MG) and continuous energy (CE) cross sections. AMPX accepts basic cross section data from ENDF/B libraries. AMPX can be used to generate a variety of MG libraries that can be used with modern transport codes to perform nuclear analyses. CE or point cross section libraries can be produced for use in Monte Carlo codes and other applications. In addition, AMPX has an internal MG format that can be read by various AMPX modules and codes outside the system. For example, the Standardized Computer Analyses for Licensing Evaluations (SCALE) system has the capability to read AMPX formatted cross section libraries. This manual provides procedures for producing CE and MG neutron cross section libraries.
- 11.1. Introduction
- 11.2. Overview
- 11.3. Processing ENDF Data
- 11.4. Using ExSite
- 11.5. Data Structures
- 11.6. Notes on Some of the Modules
- 11.7. Miscellaneous Useful Information
- 11.8. Input File Generation
- 11.9. Installation
- 11.10. Fido Input
- 11.11. Appendix A: AMPX Instructions
- 11.11.1. AJAX: Module to Merge, Collect, Assemble, Reorder, Join, Copy, Selected Nuclides from AMPX Interfaces
- 11.11.2. ALPO: Module for Producing ANISN Libraries from AMPX Working Libraries
- 11.11.3. BROADEN: Module to Doppler Broaden TAB1 Functions
- 11.11.4. CADILLAC: Combine All Data Identifiers Listed in Logical AMPX Coverx Format
- 11.11.5. CAMELS: Module to Compare AMPX Master or Working Libraries
- 11.11.6. CEEXTRACT: Extract Data out of a CE Library
- 11.11.7. CHARMIN: Module to Convert TAB1 Libraries from Single to Double Precision, to Text, or from Any of these Formats to any of the Others
- 11.11.8. CLAROL: A Module to Replace Cross Sections on an AMPX Master Interface
- 11.11.9. COGNAC: Conversion Operations for Group-Dependent Nuclides in AMPX COVERX Format
- 11.11.10. COMBINE: Add, Subtract, Multiply, or Divide TAB1 Files
- 11.11.11. COMPRESS: Module to Compress Functions Written in TAB1 Format
- 11.11.12. COVCOMP: Compare Two COVERX Files or Add COVERX Files According to a Given Percentage
- 11.11.13. COVCONV: Program to Convert File 32 Resonance Data into File 33 Format
- 11.11.14. COVERR: Program to Convert COVERX Files to ERRORR Covariance Files
- 11.11.15. FABULOUS_URR: Module to Produce Bondarenko Factor Tables
- 11.11.16. FABULOUS: Module to Produce Bondarenko Factor Tables
- 11.11.17. FILTER: Select Specific Data from a Master of Working Library
- 11.11.18. FUNCCALC: Calculate Arbitrary Function
- 11.11.19. IRFFACHOMO: Module to Produce Homogenous F-Factors
- 11.11.20. IRFFACTOR: Module to Calculate Intermediate Resonance F-Factors Based on Hetero Cells
- 11.11.21. JAMAICAN: Module to Thin Point-Wise 2D Data
- 11.11.22. JERGENS: Module to Generate Weight Functions and to Combine ENDF/B TAB1 Records
- 11.11.23. KINKOS: Kinematic Conversion System
- 11.11.24. KINZEST: Module to Manage Kinematic Libraries
- 11.11.25. LAMBDA: Module to Produce Lambda Factors
- 11.11.26. LAVA: AMPX Module to Make an AMPX Working Library from an ANISN Library
- 11.11.27. LINEAR: Module to Linearize Functions Written in TAB1 Format
- 11.11.28. LIPTON: Convert ASCII ENDF/B File That Contains File 3, 9, and 10 to Binary
- 11.11.29. MAKPEN: Module to Generate Cross Section Data in a PENDF Format
- 11.11.30. MALOCS: Module to Collapse AMPX Master Cross Section Libraries
- 11.11.31. MALT: Make ANISN Library Transformation
- 11.11.32. MG_to_KIN: Convert Total MG Scattering Matrix to CE
- 11.11.33. PALEALE: Improved Module for Printing Data from AMPX Libraries
- 11.11.34. EXTRACT: Module to Read an NJOY PENDF and Create a TAB1 File
- 11.11.35. PICKEZE: Module to Pick Functions from a TAB1 File
- 11.11.36. PLATINUM: PKENO Library Assembler Tool in a Useable Module
- 11.11.37. POLIDENT: Module to Produce Point Data from Resonance Data
- 11.11.38. PRELL: Module to Produce and Manipulate an Energy Limits Library
- 11.11.39. PRILOSEC: Module to Produce ORIGEN Cross Section Libraries
- 11.11.40. PRUDE: AMPX Module to Create Cross Sections for the Unresolved Resonance Energy Region
- 11.11.41. PUFF_IV: Module to Generate MG Correlation Matrices
- 11.11.42. PURM: Module to Produce Probability Tables from Unresolved Resonance Data Using Monte Carlo
- 11.11.43. PURM_UP: Correct Probability Tables for File 3 Contributions
- 11.11.44. RADE: Module to Check AMPX Master Cross Sections Libraries
- 11.11.45. SIMONIZE
- 11.11.46. SMILER: AMPX Module to Convert NJOY GENDF Files to AMPX Master Libraries
- 11.11.47. SPLICER: Sets the Functions on a TAB1 File to Zero Between el and eh, or Chop to the Given Range, or Splice with Data
- 11.11.48. TAB1COMPARE: Module to Compare Functions on Two TAB1 Files
- 11.11.49. TABASCO: Module to Read Functions from an AMPX Master Library and Write Them to a TAB1 File as Histograms
- 11.11.50. TGEL: Module to Calculate Total Cross Sections for Functions Written in TAB1 Format
- 11.11.51. TOMATO: Module to Change Material Identifiers (MAT Numbers) on a TAB1 File
- 11.11.52. WORM: AMPX Module to Convert an AMPX Working Library to an AMPX Master Library
- 11.11.53. X10: Module to Produce MG Libraries from Three Tabular Files
- 11.11.54. Y12: Create Kinematic Data Files
- 11.11.55. ZEST: Module to Manage String Libraries
References
I. I. Bondarenko. Group constants for nuclear reactor calculations. Consultants Bureau, 1964.
J. J. Dongarra, Jeremy Du Croz, Sven Hammarling, and I. S. Duff. A set of level 3 basic linear algebra subprograms. ACM Transactions on Mathematical Software, 16(1):1–17, March 1990. URL: https://doi.org/10.1145/77626.79170 (visited on 2022-10-03), doi:10.1145/77626.79170.
M. E. Dunn and L. C. Leal. Calculating probability tables for the unresolved-resonance region using Monte Carlo methods. Nuclear science and engineering, 148(1):30–42, 2004. Publisher: Taylor & Francis.
M.E. Dunn and N.M. Greene. POLIDENT: A Module for Generating Continuous-Energy Cross Sections from ENDF Resonance Data. Technical Report ORNL/TM-2000/35, NUREG/CR-6694, 769280, Oak Ridge National Laboratory, December 2000. URL: http://www.osti.gov/servlets/purl/769280-YIZz7R/webviewable/ (visited on 2022-10-03), doi:10.2172/769280.
Freeman J. Dyson and Madan Lal Mehta. Statistical Theory of the Energy Levels of Complex Systems. IV. Journal of Mathematical Physics, 4(5):701–712, May 1963. Publisher: American Institute of Physics. URL: https://aip.scitation.org/doi/abs/10.1063/1.1704008 (visited on 2022-10-03), doi:10.1063/1.1704008.
N. M. Greene, J. L. Lucius, L. M. Petrie, W. E. Ford, III, J. E. White, and R. Q. Wright. AMPX: a modular code system for generating coupled multigroup neutron-gamma libraries from ENDF/B. Technical Report ORNL/TM-3706, 7342486, Oak Ridge National Laboratory, March 1976. URL: http://www.osti.gov/servlets/purl/7342486/, doi:10.2172/7342486.
Gordon Edward Hansen and William H. Roach. Six and sixteen group cross sections for fast and intermediate critical assemblies. LAMS-2534, Los Alamos Scientific Laboratory of the University of California, 1963.
H. Henryson, B. J. Toppel, and C. G. Stenberg. MC 2-2: a code to calculate fast neutron spectra and multigroup cross sections. Technical Report, Argonne National Laboratory, 1976.
M. Herman. ENDF-6 Formats Manual: Data Formats and Procedures for the Evaluated Nuclear Data File ENDF/B-VI and ENDF/B-VII. Technical Report BNL–90365-2009, 981813, Brookhaven National Laboratory, June 2009. URL: http://www.osti.gov/servlets/purl/981813-Y9Gooc/ (visited on 2022-10-03), doi:10.2172/981813.
Henry C. Honeck. THERMOS. A Thermalization Transport Theory Code for Reactor Lattice Calculations. Technical Report, Brookhaven National Laboratory, Upton, NY, 1961.
Richard N. Hwang. A rigorous pole representation of multilevel cross sections and its practical applications. Nuclear Science and Engineering, 96(3):192–209, 1987. Publisher: Taylor & Francis.
Matthew Anderson Jessee, William A. Wieselquist, Thomas M. Evans, Steven P. Hamilton, Joshua J. Jarrell, Kang Seog Kim, Jordan P. Lefebvre, Robert A. Lefebvre, Ugur Mertyurek, and Adam B. Thompson. Polaris: a new two-dimensional lattice physics analysis capability for the SCALE code system. Technical Report, Oak Ridge National Laboratory, Oak Ridge, TN (USA), 2014.
G. D. Joanou and J. S. Dudek. GAM-II. AB \$ sub 3\$ CODE FOR THE CALCULATION OF FAST-NEUTRON SPECTRA AND ASSOCIATED MULTIGROUP CONSTANTS. Technical Report, General Atomic Div., General Dynamics Corp., San Diego, Calif., 1963.
C. Kalbach and F. M. Mann. Phenomenology of continuum angular distributions. I. Systematics and parametrization. Physical Review C, 23(1):112, 1981. Publisher: APS.
O. Klein and Y. Nishina. Über die Streuung von Strahlung durch freie Elektronen nach der neuen relativistischen Quantendynamik von Dirac. Zeitschrift für Physik, 52(11):853–868, November 1929. URL: https://doi.org/10.1007/BF01366453 (visited on 2022-10-03), doi:10.1007/BF01366453.
Brendan Kochunas, Benjamin Collins, Dan Jabaay, Thomas J. Downar, and William R. Martin. Overview of development and design of MPACT: Michigan parallel characteristics transport code. Technical Report, American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL …, 2013.
Nancy M Larson. Updated User's Guide for Sammy: Multilevel R-Matrix Fits to Neutron Data Using Bayes' Equations. Technical Report ORNL/TM-9179/R8, 941054, Oak Ridge National Laboratory, October 2008. URL: http://www.osti.gov/servlets/purl/941054-BqQIHy/ (visited on 2022-10-03), doi:10.2172/941054.
R. E. MacFarlane and A. C. Kahler. Methods for processing ENDF/B-VII with NJOY. Nuclear Data Sheets, 111(12):2739–2890, 2010. Publisher: Elsevier.
C. M. Mattoon, B. R. Beck, N. R. Patel, N. C. Summers, G. W. Hedstrom, and D. A. Brown. Generalized Nuclear Data: A new structure (with supporting infrastructure) for handling nuclear data. Nuclear Data Sheets, 113(12):3145–3171, 2012. Publisher: Elsevier.
ORNL. SCALE: A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design". Technical Report ORNL/TM-2005/39, Version 6.1, Oak Ridge National Laboratory, Oak Ridge, TN, 6 2011.
W. H. Press, W. T. Vetterling, S. A. Teukolsky, and B. P. Flannery. Numerical recipes in Fortran 77: The art of scientific computing. Cambridge University Press, second edition edition, 1992.
Rudi JJ Stamm'ler and Máximo Julio Abbate. Methods of steady-state reactor physics in nuclear design. Volume 111. Academic Press London, 1983.
N. M. Steen, G. D. Byrne, and E. M. Gelbard. Gaussian quadratures for the integrals $\int _0^\infty e^-x^2 f(x) \, dx$ and $\int _0^b e^-x^2 f(x) \, dx$. Mathematics of Computation, 23(107):661–671, 1969. URL: https://www.ams.org/mcom/1969-23-107/S0025-5718-1969-0247744-3/ (visited on 2022-10-03), doi:10.1090/S0025-5718-1969-0247744-3.
Alvin Martin Weinberg and Eugene Paul Wigner. The physical theory of neutron chain reactors. University of Chicago Press, 1958.
Dorothea Wiarda, Goran Arbanas, L. Leal, and Michael E. Dunn. Recent advances with the AMPX covariance processing capabilities in PUFF-IV. Nuclear Data Sheets, 109(12):2791–2795, 2008. Publisher: Elsevier.
Mark L. Williams. Resonance self-shielding methodologies in SCALE 6. Nuclear Technology, 174(2):149–168, May 2011. URL: https://doi.org/10.13182/NT09-104, doi:10.13182/NT09-104.
Mark L. Williams and Kang Seog Kim. The embedded self-shielding method. In PHYSOR 2012. 2012.