POINT2011: ENDF/B-VII.1 Beta4 Temperature Dependent Cross Section Library.
None included. Uses interactive HTML links.
Lawrence Livermore National Laboratory, Livermore, CA, and the International Atomic Energy Agency, IAEA, Vienna, Austria.
The latest ENDF/B-VII.1 beta4 data library was recently and is now freely available through the National Nuclear Data Center (NNDC), Brookhaven National Laboratory. This release completely supersedes all preceding releases of ENDF/B. The ENDF/B-VII.1 data library was processed into the form of temperature dependent cross sections and is being distributed as POINT2011. Details on this and previous versions of this library can be found in the included documentation.
The beta4 release is very similar to the beta3 release, with the same 418 evaluations. The author has only found time to compare the energy dependent, room temperature, total cross section; the following evaluations differ by 0.1% or more in the total.
WARNING: Be aware that other cross sections may differ, but do not result in significant differences in the total.
As distributed, the ENDF/B-VII.1 data includes cross sections represented in the form of a combination of resonance parameters and/or tabulated energy dependent cross sections, nominally at 0 Kelvin temperature.
For use in applications the ENDF/B-VII.1 library has been processed into the form of temperature dependent cross sections at eight neutron reactor like temperatures, between 0 and 2100 Kelvin, in steps of 300 Kelvin (the exception being 293.6 Kelvin, for exact room temperature at 20 Celsius). It has also been processed to five astrophysics like temperatures—1, 10, and 100 eV; and 1 and 10 keV. For reference purposes, 300 Kelvin is approximately 1/40 eV, so that 1 eV is approximately 12,000 Kelvin. At each temperature the cross sections are tabulated and linearly interpolable in energy.
As distributed, the original evaluated data includes cross sections represented in the form of a combination of resonance parameters and/or tabulated energy dependent cross sections, nominally at 0 Kelvin. For use in applications, this data has been processed using the 2010 version of the ENDF/B Pre-processing codes (PREPRO 2010) to produce temperature dependent, linearly interpolable in energy, tabulated cross sections, in the ENDF-6 format.
The steps required and codes used to produce room temperature, linearly interpolable tabulated cross sections, in the ENDF-6 format, are described below (the name of each code is given in parenthesis; for details of each code see reference).
Here are the steps and PREPRO 2010 codes used to process the data, in the order in which the codes were used.
1) Linearly interpolable, tabulated cross sections (LINEAR)
2) Including the resonance contribution (RECENT)
3) Doppler broaden all cross sections to temperature (SIGMA1)
4) Check data, define redundant cross sections by summation (FIXUP)
5) Update evaluation dictionary in MF/MT=1/451 (DICTIN)
For the “cold” (0 Kelvin) data steps 1), 2) 4), and 5) were used (no Doppler broadening). For the data at other temperatures, after steps 1) and 2), the data was Doppler broadened to each temperature using step 3), and the results were then made consistent with the ENDF/B formats and conventions using steps 4) and 5) to produce the final distributed data.
The result is linearly interpolable in energy, tabulated, temperature dependent cross sections, in the ENDF-6 format ready to be used in applications.
Note - this processing only involved the energy dependent neutron cross sections. All other data in the evaluations (e.g., angular and energy distributions) was not affected by this processing, and is identical in all versions of the final results (i.e., it is the same in all of the directories, ORIGINAL, as well as K0 through K2100, and 1ev through 10kev, on the DVDs).
1-H - 1, 1-H - 2, 1-H - 3, 2-He- 3, 2-He- 4, 3-Li- 6, 3-Li- 7, 4-Be- 7, 4-Be- 9, 5-B - 10, 5-B - 11, 6-C -Nat, 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 -Nat, 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- 58M, 28-Ni- 60, 28-Ni- 61, 28-Ni- 62, 28-Ni- 64, 29-Cu- 63, 29-Cu- 65, 30-Zn-Nat, 31-Ga- 69, 31-Ga- 71, 32-Ge- 70, 32-Ge- 72, 32-Ge- 73, 32-Ge- 74, 32-Ge- 76, 33-As- 74, 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-110M, 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-115M, 48-Cd-116, 49-In-113, 49-In-115, 50-Sn-112, 50-Sn-113, 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-127M, 52-Te-128, 52-Te-129M, 52-Te-130, 52-Te-132, 53-I -127, 53-I -129, 53-I -130, 53-I -131, 53-I -135, 54-Xe-123, 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-133, 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-136, 58-Ce-138, 58-Ce-139, 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-148M, 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-153, 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-156, 66-Dy-158, 66-Dy-160, 66-Dy-161, 66-Dy-162, 66-Dy-163, 66-Dy-164, 67-Ho-165, 67-Ho-166M, 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, 77-Ir-191, 77-Ir-193, 79-Au-197, 80-Hg-196, 80-Hg-198, 80-Hg-199, 80-Hg-200, 80-Hg-201, 80-Hg-202, 80-Hg-204, 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, 92-U -239, 92-U -240, 92-U -241, 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-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-249, 97-Bk-250, 98-Cf-249, 98-Cf-250, 98-Cf-251, 98-Cf-252, 98-Cf-253, 98-Cf-254, 99-Es-253, 99-Es-254, 99-Es-255, 100-Fm-255
No data retrieval program is included in the package. The PREPRO codes may be used to plot the POINT2011 data. Mozilla Firefox can be used to access the data through the html index. Internet Explorer might require forward slashes in path names of the html index file to be changed to back slashes.
The ENDF Utility Codes for handling ENDF/B data may be used to access this data. The latest versions are available at NNDC http://www.nndc.bnl.gov/nndcscr/endf/endf-util/index.html.
In this library each evaluation is stored as a separate file. The entire library is in the computer independent ENDF-6 character format, which allows the data to be easily transported between computers. The entire library requires approximately 15.5 gigabyte of storage. (D00247MNYCP01).
Not applicable.
a. Documentation available with library:
D. E. Cullen, POINT 2011, A Temperature Dependent Cross Section Library, LLNL-TR-479947 Rev2 (September 30, 2011).
b. Other useful documentation:
D. E. Cullen, “POINT 2009, A Temperature Dependent ENDF/B-VII.0 Cross Section Library,” (June 6, 2009).
D.E. Cullen, “PREPRO 2007: 2007 ENDF/B Pre-processing Codes,” IAEA-NDS-39, Rev. 13 (March 17, 2007).
D. E. Cullen, “TART2005 - A Coupled Neutron-Photon 3-D, Combinatorial Geometry, Time Dependent Monte Carlo Transport Code,” UCRL-SM-218009 (Nov.22, 2005).
The ASCII data files are approximately 16 gigabytes in size when extracted and are distributed on DVD in a Tar/GZ file. The document cited in Section 10.a is also included.
July 2011, October 2011.
KEYWORDS: BASED ON ENDF/B-VII.1; EVALUATED NEUTRON CROSS SECTIONS