3. DESCRIPTION
ZZ-ADS-LIB/V1.0
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This test library can be used for a number of code systems in the analysis of Accelerator Driven Systems (ADS).
The library is restricted to those materials needed for benchmarking efforts linked to short and mid-term ADS experimental results and design concepts. The 30 materials selected and the upper energy limit of the evaluation of each of them is given in parentheses.
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FORMAT: ENDF-6
NUMBER OF GROUPS: continuous energy for ACE library
421 neutron groups for MATXS library
NUCLIDES: H-1 (150), O-16 (150), Al-27 (150), Ti-46 (20), Ti-47 (20), Ti-48 (20), Ti-49 (20), Ti-50 (20), Cr-50 (20), Cr-52 (20), Cr-53 (20), Cr-54 (20), Mn-55 (20), Fe-54 (200), Fe-56 (200), Fe-57 (200), Fe-58 (200), Ni-58 (20), Ni-60 (20), Ni-61 (150), Ni-62 (150), Ni-64 (150), Pb-204 (200), Pb-206 (200), Pb-207 (200), Pb-208 (200), Th-232 (20) , U-234 (20), U-235 (20), U-238 (30)
THERMAL SCATTERING: Thermal scattering Data for 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
TEMPERATURES:
for H-1: [293.6,323.6,373.6,423.6,473.6,523.6,573.6,623.6K]
for Actinides and O-16: [293.6, 400, 500, 600, 700, 800, 900, 1200K]
and for the rest of materials: [293.6, 400, 500, 600, 700, 800, 900K]
ORIGIN: JEFF3.1
NEUTRON WEIGHTING SPECTRUM:
standard PWR spectrum included in the GROUPR module of NJOY, 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: sigma-0, between 5 and 10, depending on the nuclide in the range 1-10E10.
LEGENDRE ORDER: P-6 for transport correction to P-5.
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ZZ-ADS-LIB/V2.0
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This test library can be used for a number of code systems in the analysis of Accelerator Driven Systems (ADS) and new reactor designs.
The number of materials was extended from 30 to 156 in 2008 on the basis of the same processing procedures.
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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, 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.
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