ADS-LIB/V2.0: Test Library for Accelerator Driven Systems V.2.0.
Processing was carried out using NJOY-99.259 with the local updates at IAEA-NDS. The resulting processed files are available in ACE format for Monte Carlo transport calculations and in MATXS format for deterministic transport calculations.
Nuclear Data Section, International Atomic Energy Agency Vienna, Austria, through the Nuclear Energy Agency Data Bank, Issy-les-Moulineaux, France.
Participants at the IAEA Technical Meeting on “Application Libraries for ADS and Transmutation,” held in Vienna, December 15–17, 2004, recommended the generation of a limited scope test library for Monte Carlo as well as deterministic transport codes for use in the analysis of ADS INDC(NDS)-0469 . The generation of the ADS nuclear data library for testing was undertaken by IAEA-NDS INDC(NDS)-0474. The number of materials was extended from 30 to 156 in 2008 on the basis of the same processing procedures INDC(NDS)-0545.
Research groups exploring the utilization of Accelerator Driven Systems (ADS) for power generation and the transmutation of actinide and fission product waste require well-defined cross-section libraries suitable for their transport calculations. Thus, a test library has been further developed and re-assembled to meet this request and assist benchmarking studies linked to ADS experiments and design concepts. The ADS-2.0 library has been prepared from the ENDF/B-VII.0 library and the JENDL/AC actinoid and IAEA-NDS tungsten files, and processed in suitable forms for Monte Carlo and deterministic transport codes used in the analysis of ADS. The resulting data package can also be applied to criticality calculations for new reactor designs, particularly for high-temperature systems (core materials up to 1800K).
FORMAT: ENDF-6
NUMBER OF GROUPS: point-wise continuous-energy cross-section data in ACE format for MCNP calculations multi-group cross-sections based on the ORNL 421-group energy structure available in two formats MATXS and GENDF
NUCLIDES: H-1, H-2, He-3, He-4, Li-6, Li-7, Be-9, B-10, B-11, C-nat, N-14, N-15, O-16, F-19, Na-23, Mg-24, Mg-25, Mg-26, Al-27, Si-28, Si-29, Si-30, P-31, S-32, S-33, S-34, S-36, Cl-35, Cl-37, K-39, K-40, K-41, Ca-40, Ca-42, Ca-43, Ca-44, Ca-46, Ca-48, Ti-46, Ti-47, Ti-48, Ti-49, Ti-50, V-nat, Cr-50, Cr-52, Cr-53, Cr-54, Mn-55, Fe-54, Fe-56, Fe-57, Fe-58, Co-59, Ni-58, Ni-60, Ni-61, Ni-62, Ni-64, Cu-63, Cu-65, Zn-nat, Zr-90, Zr-91, Zr-92, Zr-94, Zr-96, Nb-93, Mo-92, Mo-94, Mo-95, Mo-96, Mo-97, Mo-98, Mo-100, Ag-107, Ag-109, Cd-106, Cd-108, Cd-110, Cd-111, Cd-112, Cd-113, Cd-114, Cd-116, In-113, In-115, Eu-151, Eu-153, Gd-152, Gd-154, Gd-155, Gd-156, Gd-157, Gd-158, Gd-160, Er-162, Er-164, Er-166, Er-167, Er-168, Er-170, Lu-175, Lu-176, Hf-174, Hf-176, Hf-177, Hf-178, Hf-179, Hf-180, Ta-181, W-180, W-182, W-183, W-184, W-186, Au-197, Hg-196, Hg-198, Hg-199, Hg-200, Hg-201, Hg-202, Hg-204, Pb-204, Pb-206, Pb-207, Pb-208, Bi-209, Th-232, Pa-231, Pa-233, U-232, U-233, U-234, U-235, U-236, U-237, U-238, Np-237, Np-239, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Am-241, Am-242, Am-242m, Am-243, Cm-242, Cm-243, Cm-244, Cm-245, Cm-246 and Cm-247
THERMAL SCATTERING: Thermal scattering data for hydrogen bound in light water, deuterium bound in heavy water, and graphite
TEMPERATURES:
for H-1 (H2O), H-2 (D2O): [293.6, 350, 400, 450, 500, 550, 600, 650K]
for C-nat (graphite): [296, 400, 500, 600, 700, 800, 1000, 1200, 1600, 2000K]
for actinides, Si-28, Si-29, Si-30, O-16: [293.6, 600, 900, 1200, 1500, 1800K]
and for the rest of materials: [293.6, 600, 900, 1200K]
ORIGIN: ENDF/B-VII.0, JENDL/AC, IAEA-NDS tungsten files
NEUTRON WEIGHTING SPECTRUM:
Standard PWR spectrum included in the GROUPR module of NJOY is modified in such a way that follows the 1/E shape from 4.0 Ev to 9.811 KeV and from 10 to 20 MeV.
BACKGROUND SCATTERING: Bondarenko sigma-0 approach
LEGENDRE ORDER: P-6 for transport correction to P-5.
Processing was carried out using NJOY-99.259 with the local updates at IAEA-NDS. The resulting processed files are available in ACE format for Monte Carlo transport calculations and in MATXS format for deterministic transport calculations.
(RSICC ID: D00250MNYCP00; NEADB ID: IAEA1420/02).
Not applicable.
a. Documentation available with library
D. Lopez Aldama and A. L. Nichols, “ADS-2.0, A Test Library for Accelerator Driven Systems and New Reactor Design,” International Atomic Energy Agency, Vienna, Austria, INDC(NDS)-0545, December 2008.
D. Lopez Aldama and A. Trkov, “ADS-Lib/V1.0, A test library for Accelerator Driven Systems,” International Atomic Energy Agency, Vienna, Austria, INDC(NDS)-0474, August 2005.
b. Other useful documentation
A. Stanculescu, A. Trkov, “Application Libraries for ADS and Transmutation 15-17 December 2004,” International Atomic Energy Agency, Vienna, Austria, INDC (NDS)-469.
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)
R. E. MacFarlane and D. W. Muir, “NJOY-99.0: Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B data Los Alamos National Laboratory,” RSICC, Oak Ridge National Laboratory, Oak Ridge, Tenn., PSR-480, 2000.
J. F. Briesmeister, MCNP - A General Monte Carlo N-Particle Transport Code, Version 4C Los Alamos National Laboratory, LA-13709-M, 2000.
W. A. Rhoades, et al., “DOORS 3.2, One-, Two-, Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code System,” RSICC, Oak Ridge National Laboratory, CCC-650, 1998.
V. McLane (editor), “ENDF-6 Formats Manuals,” International Atomic Energy Agency, Vienna, Austria, IAEA-NDS-76 Rev. 6, April 2001.
R. E. MacFarlane, TRANSX 2: A Code for Interfacing MATXS Cross Section Libraries to Nuclear Transport Code, Los Alamos National Laboratory, Los Alamos, New Mexico, LA-12312-MS, 1992.
A. Trkov, “Guidelines for Nuclear Data Verification and Validation,” International Atomic Energy Agency, Vienna, INDC(SEC)-0107, August 2005.
A. Trkov, Private communication on ACELST code December 2002.
D. E. Cullen, “PREPRO 2004: 2004 ENDF/B Pre-processing codes (ENDF/B-VII Ready),” International Atomic Energy Agency, Vienna, Austria, IAEA-NDS-39, Rev. 12, November 22, 2004.
The package is transmitted on a CD which contains the reports listed in section 10.a above, html index files, and data files.
October 2011.
Keywords: MONTE CARLO, Sn METHOD, CROSS SECTIONS, DATA LIBRARY, EVALUATED DATA, MULTIGROUP, NEUTRONS