NEA-1768 ZZ-MCJEFF3.1NEA.

ZZ-MCJEFF3.1NEA.

Continuous energy neutron cross-section data library for the Monte Carlo program MCNP based on the JEFF-3.1 evaluated nuclear data library (ACE format).

FORMAT: ACE

NUMBER OF GROUPS: Continuous energy

NUCLIDES (381): 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-253, 99-Es-254, 99-Es-255, 100-Fm-255

Isotopes in isomeric state (library at 300K): 27-Co-58M, 47-Ag-110M, 48-Cd-115M, 52-Te-127M, 52-Te-129M, 61-Pm-148M, 95-Am-242M, 95-Am-244M

TEMPERATURES: 300 K, 400 K, 500 K, 600 K, 700 K, 800 K, 900 K, 1000 K, 1200 K and 1800 K (the package is separated as separate entity for each temperature to facilitate handling)

THERMAL SCATTERING

• Hydrogen bound in polyethylene, 293.6 K, 350 K

• Hydrogen bound in water, 293.6 K, 323.6 K, 373.6 K,  423.6 K, 473.6 K, 523.6 K, 573.6 K, 623.6 K, 647.2 K, 800 K, 1000 K

• Hydrogen bound in ZrH, 293.6 K, 400 K, 500 K, 600 K, 700 K, 800 K 1000 K, 1200 K

• Graphite, 293.6 K, 400 K, 500 K, 600 K, 700 K, 800 K 1000 K, 1200 K, 1600 K, 2000 K, 3000 K

• D bound in D2O, 293.6 K, 323.6 K, 373.6 K,  423.6 K, 473.6 K, 523.6 K, 573.6 K, 643.6 K,

• Be(metal), 293.6 K, 400 K, 500 K, 600 K, 700 K, 800 K 1000 K, 1200 K

• Be in BeO, 293.6 K, 400 K, 500 K, 600 K, 700 K, 800 K 1000 K, 1200 K

ORIGIN: JEFF3.1

WEIGHTING SPECTRUM:

This library was generated with the NJOY-99.90 nuclear data processing system plus some specific updates required for correct processing. The library has undergone strict QA procedures. All inputs used for processing JEFF3.1 with NJOY99.90 and the documented derived version are provided. The validations made, using benchmark experiments for criticality (ICSBEP) and shielding (SINBAD) are documented in the report.

• PRPR: Fortran 77 pre-processor source.

• MAKXSF: Prepares the MCNP Cross-Section Libraries.
  These programs are distributed with the Monte Carlo code package MCNP-4C2 (CCC-0701), PREPRO2002 Endf-6 files preprocessing codes (IAEA1379).

• NJOY99 Data Processing System of Evaluated Nuclear Data Files ENDF Format (PSR-0480).

Requesters for MCJEFF3.1NEAttttK libraries (tttt is the temperature) should request also the THER data for thermal neutron applications.

• Trkov, A., ACELST code, December 2002.

• D. Lopez Aldama and A. Trkov, A test library for Accelerator Driven Systems, ADS-Lib/V1.0 , IAEA, 2005.

• M.S. Abdelrahman, N. Abdurrahman, Cross Section Libraries for Studies of Plutonium Disposition in Light Water Reactors. ANRCP-1999-28, October 1999.

• W. Haeck, B. Verboomen, ALEPH-DLG 1.1.0 Creating Cross Section Libraries for MCNP(X). SCK, CEN-BLG-1002 Rev. 0. February, 2006.

• J. Perrot, O. Meplan, ENDF2ACE User Guide, http://lpsc.in2p3.fr/MURE/pdf/ENDF2ACE_User_Guide.pdf

• S. C. FRANKLE, Experience with ENDF60 and QA of a Continuous-Energy Library, XTM:SCF-96-363, Los Alamos National Laboratory, USA (1996)

• J. Blair Briggs (ed.), International Handbook of Evaluated Criticality Safety Benchmark Experiments, NEA/NSC/DOC(95)03/I, Nuclear Energy Agency, Paris (September 2005 Edition)

• S.C. van der Marck, Shielding benchmark calculations with MCNP-4C3 using JEFF-3.1 data, NRG-Petten, October 2005, JEFDOC-1106.

• S.C. van der Marck, Criticality safety benchmark calculations with MCNP-4C3 using JEFF-3.1 data, NRG-Petten, October 2005, JEFDOC-1107.

• NEA/OECD; The JEFF-3.1 project: Complete content of the JEFF-3.1 evaluated nuclear data library, June 2, 2005, NEA#06071 (on CDROM)

• Robert C. Little, Robert E. MacFarlane, ENDF/B-VI Neutron Library for MCNP with Probabity Tables, LANL, LA-UR-98-5718, Dec. 1998

• Russell D. Mosteller, Comparison of ENDF/B-VI and Initial ENDF/B-VII Results for the MCNP Criticality Validation Suite, LA-UR-05-8430, 2005.

• R. C. LITTLE, R. E. MacFARLANE, .ENDF/B-VI Neutron Library for MCNP with Probability Tables., LA-UR-98-5718, Los Alamos National Laboratory, USA (1998)

• M. C. WHITE, J. M. CAMPBELL, S. C. FRANKLE, R. C. LITTLE, Processing of Nuclear Data for Applications., LA-UR-02-1235, Los Alamos National Laboratory, USA (2002)

• J. M. CAMPBELL, S. C. FRANKLE, R. C. LITTLE, .ENDF66: A Continuous-Energy Neutron Data Library Based on ENDF/B-VI Release 6., LA-UR-03-0954, Los Alamos National Laboratory, USA (2003)

• J. D. Court, R.C. Brockhoff, and J.S. Hendricks Lawrence Livermore Pulsed Sphere Benchmark Analysis of MCNP ENDF/B-VI, LA-12885 (1994)

• Briesmeister, J. F., MCNP - A General Monte Carlo N-Particle Transport Code, Version 4C, Los Alamos National Laboratory, LA-13709-M, 2000

• M. Mattes and J. Keinert, Thermal Neutron Scattering Data for the Moderator materials H2O, D2O and ZrHx in ENDF-6 Format and as ACE library for MCNP(X) Codes, INDC(NDS)-0470, April 2005

• MacFarlane, R.E., Muir, D.M., NJOY-99.0: Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B data, Los Alamos National Laboratory, PSR-480, 2000.

• R. E. MacFARLANE, .up90 - NJOY version 99.90., Los Alamos National Laboratory, USA (2003)

• R. E. MacFARLANE, .up112 - NJOY version 99.112., Los Alamos National Laboratory, USA (2005)

• Cullen, D.E., PREPRO 2004: 2004 ENDF/B Pre-processing codes, IAEA-NDS-39, Rev. 12, November 22, 2004.

• Sinbad data base, NEA (2005).

• Trkov, A., UpdXSDIR code, December 2002.

• F.A. Alpan, M.E. Dunn, Yummy: The Yucca Mountain MCNP-Library, ORNL/TM-2204/124, June 2004.

This work was carried out for the OECD/NEA Data Bank
12, boulevard des Iles
92130 Issy-les-Moulineaux
France
by Oscar Cabellos