RSICC DATA PACKAGE DLC-230
1. NAME AND TITLE OF DATA LIBRARY
ALEPH-LIB-JEFF3.1: ACE Format Neutron Cross Section Library based on JEFF3.1.
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS
MAKXSF: Preparer of Cross Sections from LANL MCNP package
3. CONTRIBUTORS
SCK-CEN, Mol, Belgium, through the OECD Nuclear Energy Agency Data Bank, Issy-Les Molineaux, France.
4. HISTORICAL BACKGROUND AND INFORMATION
The ALEPH-LIB-JEFF3.1 library was generated with the NJOY-99.112 nuclear data processing system. In addition to up112, some updates are required for correct processing of JEFF-3.1 with NJOY99.112. These updates are listed in the included report. RSICC received this library through the NEADB where it is distributed as NEA-1745/ZZ-ALEPH-LIB-JEFF3.1. In the Data Bank collection, the temperature-specific data are distributed as separate versions. RSICC made no changes to the data but distributes all the data in one package.
5. APPLICATION OF THE DATA
This continuous energy neutron library can be used with the MCNP(X) or ALEPH codes. ALEPH is the Monte Carlo burnup code under development at SCK• CEN in collaboration with Ghent university. ALEPH-LIB-JEFF3.1 has undergone strict QA procedures. The library (at 300 K) was validated on a suite of criticality benchmarks and on a series of pulsed sphere benchmarks. The report provides thorough documentation on the NJOY processing path, the library verification process and the input instructions for the ALEPH-DLG (Data Library Generator) code system, which was used to automate the NJOY processing. The package contains graphs displaying the processed data for each reaction type.
6. SOURCE AND SCOPE OF DATA
ALEPH-LIB-JEFF3.1 is comprised of 380 materials and 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 six temperatures depending on application needs: 300, 600, 900, 1200, 1500 and 1800 degrees Kelvin. Unresolved resonance probability tables (ptable) were processed whenever evaluations contained such data. No thermal scattering evaluations are included.
NUCLIDES (380): 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-254, 99-Es-255, 100-Fm-255
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM
The MAKXSF code which prepares MCNP cross-section libraries is distributed with the MCNP5/ MCNPX (CCC-0730) and MCNP-4C2 (CCC-0701) code packages.
8. DATA FORMAT AND COMPUTER
RSICC ID is D00230MNYCP00. The data are in ASCII mode that can be read on many computers.
9. TYPICAL RUNNING TIME
Run times vary depending on a number of factors.
10. REFERENCES
a. Documentation available with library
W. Haeck, B. Verboomen, “A Validated MCNP(X) Cross Section Library based on JEFF 3.1,” SCK-CEN-BLG-1034 Rev. 0 (October 2006).
b. Other useful documentation
R. E. MacFarlane, .up112 - NJOY version 99.112., Los Alamos National Laboratory (2005). [NJOY99.0 is distributed in a separate package - PSR-0480].
W. Haeck and B. Verboomen, “ALEPH 1.1.2 - A Monte Carlo Burn Up Code”, SCKCEN BLG 1003 Rev. 0, Studiecentrum voor Kernenergie - Centre d’Etude de l’Energie Nucléaire, Belgium (2006).
11. CONTENTS OF LIBRARY
The ASCII data libraries, xsdir files, graphs and electronic document are transmitted on one DVD in WinZIP files. Uncompressed ASCII files are about 1.2 GB for each temperature.
12. DATE OF ABSTRACT
November 2007.
KEYWORDS: MCNP FORMAT; NEUTRON CROSS SECTIONS