RSICC DATA PACKAGE DLC-228
1. NAME AND TITLE OF DATA LIBRARY
MCJEFF3.1NEA: Neutron Cross Section Library Based on JEFF3.1 for Use with MCNP.
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS
MAKXSF: Preparer of Cross Sections from LANL MCNP package
3. CONTRIBUTOR
OECD Nuclear Energy Agency Data Bank, Issy-Les Molineaux, France.
4. HISTORICAL BACKGROUND AND INFORMATION
MCJEF3.1NEA is a pointwise library for doing radiation transport and criticality calculations with the MCNP Monte Carlo transport code. The library was processed into ACE format with the NJOY-99.90 nuclear data processing system for the NEA Data Bank in France. RSICC received these data from the NEADB where they are distributed with identifier NEA-1768 ZZ-MCJEFF3.1NEA. In the DB collection each temperature is distributed as a separate package (versions 01 through 11). RSICC made no changes but distributes all temperatures in one package.
5. APPLICATION OF THE DATA
This continuous energy cross-section data library in ACE format is for shielding and criticality applications done with MCNP. In addition to the description of the NJOY processing procedure used to create the library, the included report NEA/NSC/DOC(2006)18 contains results from the benchmarking activity aimed at testing the quality of the data for criticality and shielding applications. The library at 300K has been verified: visually (no discontinuities, correct processing in all range) and with comparisons with other libraries available for the same purposes (ENDF/B-VI.8, JEF2.2, JENDL3.3, …) A set of experiments using MCNP4c are used in order to validate the processed library.
6. SOURCE AND SCOPE OF DATA
MCJEFF3.1NEA is derived from the JEFF-3.1 evaluated nuclear data library. It is a multi-temperature ACE-format neutron library for a wide range of ten temperatures depending on application needs: 300, 400, 500, 600, 700, 800, 900, 1000, 1200 and 1800 degrees Kelvin. The library is comprised of 381 materials and some thermal scattering evaluations. In addition to up90, some updates are required for correct processing of JEFF-3.1 with NJOY99.90 and are provided as a separate set of patch files. The NJOY99.90 inputs used for processing each nuclide are provided.
The processed data also contain production and gas production data whenever such data are contained in JEFF-3.1. Kinematic KERMA factors and total damage energy production data were processed. The nuclides processed include all those of the General Purpose Library and Thermal Scattering Library, including important light nuclei, structural materials, fission products, control rod materials and burnable poisons, all major and minor actinides.
NUCLIDES (381): 1-H-1, 1-H-2, 1-H-3, 2-He-3, 2-He-4, 3-Li-6, 3-Li-7, 4-Be-9, 5-B-10, 5-B-11,
6-C-0, 7-N-14, 7-N-15, 8-O-16, 8-O-17, 9-F-19, 11-Na-22, 11-Na-23, 12-Mg-24, 12-Mg-25, 12-Mg-26, 13-Al-27, 14-Si-28, 14-Si-29, 14-Si-30, 15-P-31, 16-S-32, 16-S-33, 16-S-34, 16-S-36, 17-Cl-35, 17-Cl-37, 18-Ar-36, 18-Ar-38, 18-Ar-40, 19-K-39, 19-K-40, 19-K-41, 20-Ca-40, 20-Ca-42, 20-Ca-43, 20-Ca-44, 20-Ca-46, 20-Ca-48, 21-Sc-45, 22-Ti-46, 22-Ti-47, 22-Ti-48, 22-Ti-49, 22-Ti-50, 23-V-0, 24-Cr-50, 24-Cr-52, 24-Cr-53, 24-Cr-54, 25-Mn-55, 26-Fe-54, 26-Fe-56, 26-Fe-57, 26-Fe-58, 27-Co-58, 27-Co-58m, 27-Co-59, 28-Ni-58, 28-Ni-59, 28-Ni-60, 28-Ni-61, 28-Ni-62, 28-Ni-64, 29-Cu-63, 29-Cu-65, 30-Zn-0, 31-Ga-0, 32-Ge-70, 32-Ge-72, 32-Ge-73, 32-Ge-74, 32-Ge-76, 33-As-75, 34-Se-74, 34-Se-76, 34-Se-77, 34-Se-78, 34-Se-79, 34-Se-80, 34-Se-82, 35-Br-79, 35-Br-81, 36-Kr-78, 36-Kr-80, 36-Kr-82, 36-Kr-83, 36-Kr-84, 36-Kr-85, 36-Kr-86, 37-Rb-85, 37-Rb-86, 37-Rb-87, 38-Sr-84, 38-Sr-86, 38-Sr-87, 38-Sr-88, 38-Sr-89, 38-Sr-90, 39-Y-89, 39-Y-90, 39-Y-91, 40-Zr-90, 40-Zr-91, 40-Zr-92, 40-Zr-93, 40-Zr-94, 40-Zr-95, 40-Zr-96, 41-Nb-93, 41-Nb-94, 41-Nb-95, 42-Mo-92, 42-Mo-94, 42-Mo-95, 42-Mo-96, 42-Mo-97, 42-Mo-98, 42-Mo-99, 42-Mo-100, 43-Tc-99, 44-Ru-96, 44-Ru-98, 44-Ru-99, 44-Ru-100, 44-Ru-101, 44-Ru-102, 44-Ru-103, 44-Ru-104, 44-Ru-105, 44-Ru-106, 45-Rh-103, 45-Rh-105, 46-Pd-102, 46-Pd-104, 46-Pd-105, 46-Pd-106, 46-Pd-107, 46-Pd-108, 46-Pd-110, 47-Ag-107, 47-Ag-109, 47-Ag-110, 47-Ag-111, 48-Cd-106, 48-Cd-108, 48-Cd-110, 48-Cd-111, 48-Cd-112, 48-Cd-113, 48-Cd-114, 48-Cd-115, 48-Cd-116, 49-In-113, 49-In-115, 50-Sn-112, 50-Sn-114, 50-Sn-115, 50-Sn-116, 50-Sn-117, 50-Sn-118, 50-Sn-119, 50-Sn-120, 50-Sn-122, 50-Sn-123, 50-Sn-124, 50-Sn-125, 50-Sn-126, 51-Sb-121, 51-Sb-123, 51-Sb-124, 51-Sb-125, 51-Sb-126, 52-Te-120, 52-Te-122, 52-Te-123, 52-Te-124, 52-Te-125, 52-Te-126, 52-Te-127, 52-Te-128, 52-Te-129, 52-Te-130, 52-Te-132, 53-I-127, 53-I-129, 53-I-130, 53-I-131, 53-I-135, 54-Xe-124, 54-Xe-126, 54-Xe-128, 54-Xe-129, 54-Xe-130, 54-Xe-131, 54-Xe-132, 54-Xe-133, 54-Xe-134, 54-Xe-135, 54-Xe-136, 55-Cs-133, 55-Cs-134, 55-Cs-135, 55-Cs-136, 55-Cs-137, 56-Ba-130, 56-Ba-132, 56-Ba-134, 56-Ba-135, 56-Ba-136, 56-Ba-137, 56-Ba-138, 56-Ba-140, 57-La-138, 57-La-139, 57-La-140, 58-Ce-140, 58-Ce-141, 58-Ce-142, 58-Ce-143, 58-Ce-144, 59-Pr-141, 59-Pr-142, 59-Pr-143, 60-Nd-142, 60-Nd-143, 60-Nd-144, 60-Nd-145, 60-Nd-146, 60-Nd-147, 60-Nd-148, 60-Nd-150, 61-Pm-147, 61-Pm-148, 61-Pm-148, 61-Pm-149, 61-Pm-151, 62-Sm-144, 62-Sm-147, 62-Sm-148, 62-Sm-149, 62-Sm-150, 62-Sm-151, 62-Sm-152, 62-Sm-153, 62-Sm-154, 63-Eu-151, 63-Eu-152, 63-Eu-153, 63-Eu-154, 63-Eu-155, 63-Eu-156, 63-Eu-157, 64-Gd-152, 64-Gd-154, 64-Gd-155, 64-Gd-156, 64-Gd-157, 64-Gd-158, 64-Gd-160, 65-Tb-159, 65-Tb-160, 66-Dy-160, 66-Dy-161, 66-Dy-162, 66-Dy-163, 66-Dy-164, 67-Ho-165, 68-Er-162, 68-Er-164, 68-Er-166, 68-Er-167, 68-Er-168, 68-Er-170, 71-Lu-175, 71-Lu-176, 72-Hf-174, 72-Hf-176, 72-Hf-177, 72-Hf-178, 72-Hf-179, 72-Hf-180, 73-Ta-181, 73-Ta-182, 74-W-182, 74-W-183, 74-W-184, 74-W-186, 75-Re-185, 75-Re-187, 76-Os-0, 77-Ir-191, 77-Ir-193, 78-Pt-0, 79-Au-197, 80-Hg-196, 80-Hg-198, 80-Hg-199, 80-Hg-200, 80-Hg-201, 80-Hg-202, 80-Hg-204, 81-Tl-0, 82-Pb-204, 82-Pb-206, 82-Pb-207, 82-Pb-208, 83-Bi-209, 88-Ra-223, 88-Ra-224, 88-Ra-225, 88-Ra-226, 89-Ac-225, 89-Ac-226, 89-Ac-227, 90-Th-227, 90-Th-228, 90-Th-229, 90-Th-230, 90-Th-232, 90-Th-233, 90-Th-234, 91-Pa-231, 91-Pa-232, 91-Pa-233, 92-U-232, 92-U-233, 92-U-234, 92-U-235, 92-U-236, 92-U-237, 92-U-238, 93-Np-235, 93-Np-236, 93-Np-237, 93-Np-238, 93-Np-239, 94-Pu-236, 94-Pu-237, 94-Pu-238, 94-Pu-239, 94-Pu-240, 94-Pu-241, 94-Pu-242, 94-Pu-243, 94-Pu-244, 94-Pu-246, 95-Am-241, 95-Am-242, 95-Am-242m, 95-Am-243, 95-Am-244, 95-Am-244m, 96-Cm-240, 96-Cm-241, 96-Cm-242, 96-Cm-243, 96-Cm-244, 96-Cm-245, 96-Cm-246, 96-Cm-247, 96-Cm-248, 96-Cm-249, 96-Cm-250, 97-Bk-247, 97-Bk-249, 97-Bk-250, 98-Cf-249, 98-Cf-250, 98-Cf-251, 98-Cf-252, 98-Cf-254, 99-Es-253, 99-Es-254, 99-Es-255, 100-Fm-255
Isotopes in isomeric state (library at 300K): 27-Co-58M, 47-Ag-110M, 48-Cd-115M, 52-Te-127M, 52-Te-129M, 61-Pm-148M, 95-Am-242M, 95-Am-244M
TEMPERATURES: 300 K, 400 K, 500 K, 600 K, 700 K, 800 K, 900 K, 1000 K, 1200 K and 1800 K (the package is separated as separate entity for each temperature to facilitate handling)
THERMAL SCATTERING
- Hydrogen bound in polyethylene, 293.6 K, 350 K
- Hydrogen bound in water, 293.6 K, 323.6 K, 373.6 K, 423.6 K, 473.6 K, 523.6 K, 573.6 K, 623.6 K, 647.2 K, 800 K, 1000 K
- Hydrogen bound in ZrH, 293.6 K, 400 K, 500 K, 600 K, 700 K, 800 K 1000 K, 1200 K
- Graphite, 293.6 K, 400 K, 500 K, 600 K, 700 K, 800 K 1000 K, 1200 K, 1600 K, 2000 K, 3000 K
- D bound in D2O, 293.6 K, 323.6 K, 373.6 K, 423.6 K, 473.6 K, 523.6 K, 573.6 K, 643.6 K,
- Be(metal), 293.6 K, 400 K, 500 K, 600 K, 700 K, 800 K 1000 K, 1200 K
- Be in BeO, 293.6 K, 400 K, 500 K, 600 K, 700 K, 800 K 1000 K, 1200 K
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM
The MAKXSF code which prepares MCNP cross-section libraries is distributed with the MCNP5/ MCNPX (CCC-730) and MCNP-4C2 (CCC-0701) code packages.
8. DATA FORMAT AND COMPUTER
RSICC ID is D00228MNYCP00. Different temperatures (300, 400, 500, 600, 700, 800, 900, 1000, 1200, 1800 Kelvin) are distributed in separate zip files.
The data for each temperature are provided in 3 forms:
1. the ascii file for the specified temperature for all nuclides
2. the binary file for the specified temperature for all nuclides
3. a directory containing the separate ascii file for each nuclide
In addition, the xsdir file is provided for both ascii and binary files.
9. TYPICAL RUNNING TIME
Run times vary depending on a number of factors.
10. REFERENCE
O. Cabellos, “Processing of the JEFF-3.1 Cross Section Library into a Continuous Energy Monte Carlo Radiation Transport and Criticality Data Library,” OECD NEADB, NEA/NSC/DOC(2006)18 (May 2006).
11. CONTENTS OF LIBRARY
The data libraries and electronic document are transmitted on three DVDs in WinZIP files which include data libraries and xsdir files. Uncompressed ASCII files are about 1.2 GB for each temperature.
12. DATE OF ABSTRACT
March 2007.
KEYWORDS: MCNP FORMAT; NEUTRON CROSS SECTIONS