IAEA1421 ZZ-POINT-2007.

ZZ-POINT-2007

The ENDF/B data library, ENDF/B-VII.0 was processed into the form of temperature dependent cross sections.

The original evaluated data include 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, these ENDF/B-VII.0 data were processed into the form of temperature dependent cross sections at eight temperatures: 0, 300, 600, 900, 1200, 1500, 1800 and 2100 Kelvin. It has also been processed to six astrophysics like temperatures: 0.1, 1, 10, 100 eV, 1 and 10 keV.

At each temperature the cross sections are tabulated and linearly interpolable in energy with a tolerance of 0.1 %. POINT 2007 contains all of the evaluations in the ENDF/B-VII general purpose library, which contains 78 new evaluations + 315 old ones : total 393 nuclides. It also includes 16 new elemental evaluations replaced by isotopic evaluations + 19 old ones. No special purpose ENDF/B-VII libraries, such as fission products, thermal scattering, photon interaction data are included. These evaluations include all cross sections over the energy range 10e-5 eV to at least 20 MeV.

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 PREPRO 2007 code system was used to process the ENDF/B data. Listed below are the steps, including the PREPRO2007 codes, which were used to process the data in the order in which the codes were run.

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)

Due to recent changes in ENDF-6 Formats and Procedures only the latest version of the ENDF/B Pre-processing codes, namely PREPRO 2007, can be used to accurately process all current ENDF/B-VII evaluations. The use of any earlier versions of these codes may occasion inaccurate results.

No data retrieval program is included in the package. The PREPRO 2007 package may be used to plot the POINT 2007 data.

• [R1] 'POINT 2004: A Temperature Dependent ENDF/B-VI, Release 8 Cross Section Library', Lawrence Livermore National Laboratory, UCRL-TR-202284, April 2004.

• [R2] Data Formats and Procedures for the Evaluated Nuclear Data File ENDF-6, BNL-NCS-44945, Rev. 11/95, edited by V. McLane, et al. National Nuclear Data Center, Brookhaven National Lab. http://www.nndc.bnl.gov/nndcscr/documents/endf/endf102/

• [R3] 'PREPRO 2004: The 2004 ENDF/B Pre-Processing Codes,' by D.E. Cullen, Nuclear Data Section, International Atomic Energy Agency, Vienna, Austria, IAEA-NDS-39, Rev. 12, Nov. 22, 2004; https://www-nds.iaea.org/public/endf/prepro/

• [R4] 'Atlas of Nuclear Resonances', by S.F. Mughabghab, National Nuclear Data Center, Brookhaven National Laboratory, published by Elsevier, March 2006.

• [R5] 'Exact Doppler Broadening of Tabulated Cross Sections,' by D.E. Cullen and C.R. Weisbin, Nuclear Science and Engineering 60, p. 199 (1975)

• [R6] 'THERMAL: A Routine Designed to Calculate Neutron Thermal Scattering,' by D.E. Cullen, Lawrence Livermore National Laboratory, UCRL-ID-120560-Rev-1, Sept. 1995.

• [R7] 'Verification of High Temperature Free Atom Thermal Scattering in MERCURY Compared to TART', by D.E. Cullen, Scott McKinley and Christian Hagmann, Lawrence Livermore National Laboratory, UCRL-TR-226340, August 1, 2006.

• [R8] 'TART2005: A Coupled Neutron-Photon 3-D, Time Dependent, Combinatorial Geometry Monte Carlo Transport Code,' by D.E. Cullen, Lawrence Livermore National Laboratory, UCRL-SM-218009, Nov. 22, 2005.

• P. Oblozinsky, M. Herman et al.:
  ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology
  Nuclear Data Sheets 107 (2006) 2931-3060

• S. C. van der Marck:
  Benchmarking ENDF/B-VII.0
  Nuclear Data Sheets 107 (2006) 3061-3118
  Special Issue on Evaluated Nuclear Data File ENDF/B-VII.0

This library is organised in folders for each temperature. The entire library is in the computer independent ENDF/B-6 character format, which allows the data to be easily transported between computers.

Dermott E. Cullen
University of California
Lawrence Livermore National Laboratory
P.O. Box 808/L-159
Livermore, CA 94550
U.S.A.