IAEA1421 ZZ-POINT-2007.
ZZ POINT-2007, linearly interpolable ENDF/B-VII.0 data for 14 temperatures
NAME OR DESIGNATION, COMPUTER, DESCRIPTION OR FUNCTION, METHODS, RESTRICTIONS, RELATED OR AUXILIARY PROGRAMS, STATUS, REFERENCES, REQUIREMENTS, LANGUAGE, OPERATING SYSTEM, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| ZZ-POINT-2007 | IAEA1421/01 | Arrived | 31-MAY-2007 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| IAEA1421/01 | Many Computers |
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3. DESCRIPTION OR FUNCTION
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 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
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4. METHODS
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)
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)
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5. RESTRICTIONS
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.
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.
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10. REFERENCES
[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; http://www-nds.iaea.or.at/ndspub/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
[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; http://www-nds.iaea.or.at/ndspub/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
IAEA1421/01, included references:
- D.E. Cullen:POINT 2007, A Temperature Dependent ENDF/B-VII.0 Data, Cross Section Library
UCRL-TR-228089 (February 14, 2007)
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IAEA1421/01
UCRL-TR-228089 document in MSWord and PDF formatsORIGINAL - The original ENDF/B data before processing
K0 - 0 Kelvin cross sections
K300 - 300 Kelvin cross sections
K600 - 600 Kelvin cross sections
K900 - 900 Kelvin cross sections
K1200 - 1200 Kelvin cross sections
K1500 - 1500 Kelvin cross sections
K1800 - 1800 Kelvin cross sections
K2100 - 2100 Kelvin cross sections
1eV - 1 eV cross sections
10eV - 10 eV cross sections
100eV - 100 eV cross sections
1keV - 1 keV cross sections
10keV - 10 keV cross sections
pt2007.htm Index
Keywords: ENDF/B, cross sections, evaluated data.