|Program name||Package id||Status||Status date|
|Package ID||Orig. computer||Test computer|
|DLC-0247/01||Many Computers||PC Windows|
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 are being distributed as POINT2011. Details on this and previous versions of this library can be found in the included documentation.
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 temperature. For use in applications, this data has been processed using the 2010 version of the ENDF/B Pre-processing codes (PREPRO2010, NEA package id. IAEA1379/05) to produce temperature dependent, linearly interpolable in energy, tabulated cross sections, in the ENDF-6 format.
List of nuclides:
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
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.
Linearly interpolable, tabulated cross sections (LINEAR)
Including the resonance contribution (RECENT)
Doppler broaden all cross sections to temperature (SIGMA1)
Check data, define redundant cross sections by summation (FIXUP)
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).
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.
|Package ID||Status date||Status|
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).
Keywords: ENDF/B, cross sections, evaluated data.