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| Program name | Package id | Status | Status date |
|---|---|---|---|
| ZZ-AMPXJEFF3.1.1UPM | NEA-1927/01 | Arrived | 16-SEP-2022 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-1927/01 | Linux-based PC,PC Windows |
This package includes a continuous energy neutron cross-section data library based on the JEFF-3.1.1 evaluated nuclear data file for the Monte Carlo codes distributed within SCALE Code System (AMPX format).
NEUTRON ENERGY RANGE: 1.0e-5 eV – 20.0 MeV
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-58, 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-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-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-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-148M, 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-076, 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-242G, 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
TEMPERATURES: 293 K, 565 K, 600 K, 900 K, 1200 K, 1500 K, 2000 K, and 2400 K
THERMAL SCATTERING (6):
H 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
H bound in ZrH, 293.6 K, 400 K, 500 K, 600.0 K, 700 K, 800 K, 1000 K, 1200 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, 643.9 K
Be bound in Be metal, 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
H bound in CH2, 293.6 K, 350 K
ORIGIN: JEFF-3.1.1 [4]
NEUTRON WEIGHTING SPECTRUM: not required
This library has been generated using AMPX-6 nuclear data processing code [2] and specifically the version distributed under SCALE-6.3.0 beta 11 version [1].
All the inputs created and applied for the processing of the JEFF-3.1.1 cross-section data library are also provided by this package.
Testing and benchmarking activities for the JEFF-3.1.1 CE cross-section library are documented through selected bibliography. In the testing phase, a criticality validation suite of 120 cases is used from the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP) (available for request at https://www.oecd-nea.org/tools/abstract/detail/nea-1486/). This suite covers a variety of fuel, moderators, reflectors, spectra, and geometries. In this package, all the KENO inputs for this criticality suite are also provided for testing and benchmarking purposes. It is worth mentioning that the majority of these KENO inputs are directly available in th ICSBEP Handbook database.
This analysis addresses the comparison between SCALE and MCNP, which uses cross-section data processed with NJOY [7]. A very good agreement is found between both calculation routes but important remarks should be highlighted:
The CE library is not recommended for those cases that include Be-9 or TSL Be metal since AMPX does not properly deal with that isotope. This is the main restriction on the use of this package.
Three Thermal Scattering Libraries are not included in the library due to lack of identification by SCALE: H bound in CaH2, Ca bound in CaH2, and Mg in Mg metal.
The CE library has been extensively applied to reactor physics analyses as presented in the selected bibliography. This includes different systems:
IRPhEP KRITZ-LWR-RESR-004: testing of AMPX broadening capabilities through the comparison against 37 criticality measurements at room and elevated temperatures [8].
Superphénix start-up tests: verification and validation of the library compared to other codes/libraries and experimental results for criticality, reaction rates, and reactivity coefficients [7].
SEFOR Core II: evaluation of Doppler coefficient [9].
The cross-section data library and the associated covariance matrices are expected to be directly used as input for a large variety of codes included within SCALE6.2 Code System, available at https://www.oecd-nea.org/tools/abstract/detail/ccc-0834/.
KENO-V and KENO-VI Monte Carlo codes can load the continuous-energy cross-section data through the “JEFF311-AMPX-CE.xml” file. That includes all the sequences that incorporate KENO as a module (e.g., TSUNAMI-3D for sensitivity analyses or TRITON for depletion calculations).
Main references for SCALE Code System and AMPX processing code:
1/ W. A. Wieselquist, R. A. Lefebvre, M. A. Jessee, Editors: SCALE Code System, ORNL/TM-2005/39, Version 6.2.4 (April 2020).
2/ D. Wiarda, M. E. Dunn, N. M. Greene, M. L. Williams, C. Celik, L. M. Petrie: AMPX-6: A Modular Code System for Processing ENDF/B, ORNL/TM-2016/43 (April 2016).
3/ D. Wiarda, C. Celik, M. L. Williams, A. Holcomb, Introduction to AMPX, 2017 SCALE Users’ Group Workshop, Oak Ridge National Laboratory (September 2017).
The latest version of JEFF nuclear data library (JEFF-3.3) was released under the following reference:
4/ A. Santamarina, D. Bernard, P. Blaise, M. Coste, et al., The JEFF-3.1.1 nuclear data library. JEFF Report 22, Validation results from JEF-2.2 to JEFF-3.1.1, NEA No. 6190, OECD Nuclear Energy Agency, France (2006).
Antonio JIMÉNEZ-CARRASCOSA, Oscar CABELLOS and Nuria GARCÍA-HERRANZ
Departamento de Ingeniería Energética
Escuela Técnica Superior de Ingenieros Industriales
Universidad Politécnica de Madrid
C/José Gutiérrez Abascal, 2
28006 Madrid
Spain
Carlos J. DÍEZ
Consejo de Seguridad Nuclear
C/Pedro Justo Dorado Dellmans, 11
28040 Madrid
Spain
Keywords: JEFF-3.1, Monte Carlo method, continuous energy, cross sections, decay, fission yields, multigroup.
