**RSICC CODE PACKAGE PSR-578**

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**1. NAME AND TITLE**

CALENDF-2010: Pointwise, Multigroup Neutron Cross-Sections and Probability Tables from ENDF/B Evaluations.

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** RESTRICTIONS**

Requesters from NEA Data Bank member countries are advised to order CALENDF from the NEA Data Bank. Non‐commercial users from other OECD member countries (specifically Canada and the United States) may order CALENDF from RSICC. Users from non‐OECD member countries and all commercial requesters are advised to contact the NEA Data Bank.

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**2. CONTRIBUTORS**

Culham Centre For Fusion Energy, CCFE, Culhan Science Centre, Abingdon, Oxfordshire, OX14 3DB United Kingdom, CEA, DEN/DER/SPRC, 13108 Saint Paul lez Durance Cedex, France, and CEA, DEN/DM2S/SERMA, 91191 Gif Sur Yvette Cedex, France, through the Nuclear Energy Agency Data Bank, Issy-les-Moulineaux, France.

**3. CODING LANGUAGE AND
COMPUTER**

Fortran 90 and 95; IBM PC Linux and Windows (P00578PCX8600).

**4. NATURE OF PROBLEM
SOLVED**

The CALENDF Nuclear Data Processing System is used to convert the evaluation defining the cross-section in ENDF format (i.e. the pointwise cross-sections and/or the resonance parameters, both resolved and unresolved) into forms useful for applications. Those forms used to describe neutron cross-section fluctuations correspond to "cross-section probability tables", based on Gauss quadratures and effective cross-sections. CALENDF also provides capabilities for group collapsing, for merging of several nuclei and for temperature interpolation; these calculations are based on data probability table description.

CALENDF-2010 represents a Fortran-95 update of the 2002, 2005 code distribution
with emphasis on programming quality and standard, physics and usage
improvements. CALENDF consists of a set of modules, each performing a
well-defined processing task. Each of these modules is essentially a separate
computer program linked together by input and output files and some common
constants. Devised to process multigroup cross-sections it relies on GAUSS
quadratures mathematical principle and strength. The following processes can be
handled by the code:

- moment probability tables and effective cross-sections
calculation

- probability table condensation

- probability table mix for several isotopes

- probability table interpolation

- effective cross section calculation based on probability table
calculations

- probability table calculations from effective cross-sections

- effective cross-section comparison

- complete energy pointwise cross-section processing

- thickness dependant averaged transmission sample calculation.

**5. METHOD OF SOLUTION**

Due to the diversity of the calculations, several physical modeling and numerical techniques or algorithms are used, including:

- the use of stratified sampling for random resonance parameter generation (in the unresolved resonance range)

- the use of improved Multi-Niveau Breit and Wigner (MNBW # MLBW) approximation when it is valid

- the use Reich-Moore (RM) method, when the MLBW approximation is not valid

- the calculation of probability tables which are, in fact, Gauss quadrature tables

- the use of Padé approximants and Gauss quadratures for various computations

- the cubic interpolation.

**6. RESTRICTIONS OR
LIMITATIONS**

- No limitation on the size of the pointwise or multigroup energy mesh.

- All the defaulted dimensions or options can be modified by the users.

**7. TYPICAL RUNNING TIME**

For calculations starting from evaluations, the computing time depends greatly on the evaluation, on the required accuracy and on the group mesh chosen. All 29 test cases ran in about 10 minutes on a single 2.4 Ghz Intel processor.

**8. COMPUTER HARDWARE
REQUIREMENTS**

CALENDF-2010 runs on Personal Computers and IBM RS/6000, Sun and Mac OSX. Around 300 MB of disk space and a few Mb of computer memory at run time.

**9. COMPUTER SOFTWARE
REQUIREMENTS**

Fortran compiler FFLAGS for normal, full debugging and fast execution are provided for each compiler and platforms. Older Fortran compiler releases, on all platforms, are generally not supported.

CALENDF-2010
was tested at the CCFE on the following platforms:

- Oracle Solaris 5.11 & Oracle Studio 12 Fortran 77/95
Compilers

- Mac Pro OsX 10.7.2, Ubuntu-10, Fedora-15, Cygwin & gfortran
4.5

- Mac Pro OsX 10.7.2, & g95 0.92

- Mac Pro OsX 10.7.2 & Intel Compiler XE 12.1

- Window 7 & Intel Compiler XE 12.1

- Window XP & Lahey/Futjitsu Fortran 95 Release 5.7

**10. REFERENCES**

J-Ch. Sublet, P Ribon, M Coste-Delclaux, “CALENDF-2010 : User Manual,” Rapport CEA-R-6277, ISSN 0429-3460 (2011).

J-Ch. Sublet, R. M. Blomquist, S. Goluoglu, R. E. MacFarlane, “ Unresolved Resonance Range Cross Section, Probability Tables and Self Shielding,” Rapport CEA-R-6227, ISSN 0429-3460 (2009).

R. E. MacFarlane, R. M. Blomquist, D. E. Cullen, E. lent, J-Ch. Sublet, “A Code Comparison Study for the Big Ten Assembly,” Report LA-UR-08-4668 (2008).

J-Ch. Sublet, C. Dean, D. Plisson-Rieunier, “ECCOLIB-JEFF-3.1 Libraries,” Rapport CEA-R-6100, ISSN 0429-3460 (2006).

C. Jouanne, J-Ch. Sublet, “TRIPOLI-4.4 JEFF-3.1 Based Libraries,” Rapport CEA-R-6125, ISSN 0429-3460 (2006).

J-Ch. Sublet, P. Ribon, “Current Status of CALENDF-2005,” Wonder (2006).

**11. CONTENTS OF CODE
PACKAGE**

Included are the referenced documents listed above and a CD which includes source codes, executables, Makefiles, and test cases. This version is distributed as a WinZIP file.

**12. DATE OF ABSTRACT**

October 2012.

**KEYWORDS:** ENDF/B-VI;
ENDF FORMAT; MULTIGROUP CROSS SECTION PROCESSING; NEUTRON CROSS SECTION
PROCESSING; R-MATRIX THEORY; RESONANCES