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IAEA1420 ZZ-ADS-LIB. (Abstract last modified 19-JAN-2010)
1.
NAME OR DESIGNATION - ZZ-ADS-LIB/V1.0, ZZ-ADS-LIB/V2.0 2.
COMPUTER FOR WHICH THIS PACKAGE IS DESIGNED -
To request or retrieve programs click on the one of the active versions below.
A password and special authorization is required. Explanation of the status codes.
Machines used:
Package-ID Orig.Computer Test Computer
IAEA1420/01 IBM PC,PC Windows PC Windows
IAEA1420/02 IBM PC,PC Windows
3.
DESCRIPTION - 4.
METHODS - 6.
TYPICAL RUNNING TIME - The execution times depend on the number of the new materials to be processed. 8.
The SIGACE package is included in ZZ-ADS-LIB/V2.0. It is also available separately (IAEA1416/01). 9.
STATUS 10.
REFERENCES - 11.
HARDWARE REQUIREMENTS - 12.
PROGRAMMING LANGUAGE -IAEA1420/01: 13.
SOFTWARE REQUIREMENTS - 14.
OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS - . 15.
NAME AND ESTABLISHMENT OF AUTHORS - 16.
MATERIAL AVAILABLE -IAEA1420/01: 17.
CATEGORIES - Keywords: Monte Carlo method, SN method, accelerator driven systems, cross sections, libraries, neutron
Program-name Package-ID Status
ZZ-ADS-LIB/V1.0 IAEA1420/01 Tested
ZZ-ADS-LIB/V2.0 IAEA1420/02 Arrived
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.
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
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.
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
ZZ-ADS-LIB/V2.0
---------------
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.
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
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.
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
ZZ-ADS-LIB/V1.0
---------------
Processing was carried out using NJOY-99.90 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.
ZZ-ADS-LIB/V2.0
---------------
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.
IAEA1420/01: 13-FEB-2008 Tested at NEADB
IAEA1420/02: 19-JAN-2010 Masterfiled Arrived
[1] STANCULESCU A., TRKOV A.:
Application Libraries for ADS and Transmutation
15-17 December 2004, Vienna, Austria, INDC (NDS)-469.
[2] 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)
[3] MACFARLANE R.E., MUIR D.W.:
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.
[4] BRIESMEISTER J.F.:
MCNP - A General Monte Carlo N-Particle Transport Code, Version 4C
Los Alamos National Laboratory, LA-13709-M, 2000.
[5] RHOADES W.A., et al.:
DOORS 3.2, One-, Two-, Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code System
RSICC, Oak Ridge National Laboratory, CCC-650, 1998.
[6] MCLANE V. (editor):
ENDF-6 Formats Manuals
IAEA-NDS-76 Rev. 6, April 2001.
[7] MACFARLANE R.E.:
TRANSX 2: A Code for Interfacing MATXS Cross Section Libraries to Nuclear Transport Codes
Los Alamos National Laboratory, LA-12312-MS, 1992.
[8] TRKOV A.:
Guidelines for Nuclear Data Verification and Validation
International Atomic Energy Agency, Vienna, INDC(SEC)-0107, August 2005.
[9] TRKOV A.:
Private communication on ACELST code
December 2002.
[10] CULLEN D.E.:
PREPRO 2004: 2004 ENDF/B Pre-processing codes (ENDF/B-VII Ready)
IAEA-NDS-39, Rev. 12, November 22, 2004.
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IAEA1420/01:
- D. Lopez Aldama and A. Trkov:
ADS-Lib/V1.0, A test library for Accelerator Driven Systems
IAEA, INDC(NDS)-0474, August 2005
IAEA1420/02:
- D. Lopez Aldama and A.L. Nichols:
ADS-2.0, A Test Library for Accelerator Driven Systems and New Reactor Designs
IAEA, INDC(NDS)-0545, December 2008
- D. Lopez Aldama and A. Trkov:
ADS-Lib/V1.0, A test library for Accelerator Driven Systems
IAEA, INDC(NDS)-0474, August 2005
IAEA1420/01:
ZZ-ADS-LIB/V1.0 was tested at the NEA Databank on a PC with 3GHz INTEL Pentium 4.
IAEA1420/02:
IAEA1420/01:
ZZ-ADS-LIB/V1.0 was tested at the NEA Databank under WINDOWS XP Professional with the following compilers:
- g95 (g95);
- Compaq Visual Fortran Professional Edition 6.6 a (df);
- Lahey/Fujitsu Fortran 95 Compiler Release 5.50d (lf95).
IAEA1420/01:
In ZZ-ADS-LIB/V1.0, some small modifications have been introduced in the DOS .bat procedures to increase the portability: some less important procedures have been eliminated since they use proprietary software.
ZZ-ADS-LIB/V1.0
---------------
D. Lopez Aldama and A. Trkov
Nuclear Data Section
International Atomic Energy Agency
Vienna, Austria
ZZ-ADS-LIB/V2.0
---------------
D. Lopez Aldama and A. L. Nichols
Nuclear Data Section
International Atomic Energy Agency
Vienna, Austria
ENDF/ evaluated nuclear data files on which the library is based (JEFF3.1)
ACE/ processed ACE formatted files
MATXS/ MATXS and GENDF formatted files
Inputs/ Input files ADSNJI.INP, ADSNT.DAT, ADSSL.DAT
OUT/ output files from NJOY run
PEND/ PENDF files from NJOY run
Programs/ auxiliary programs and batch procedures
Work/ Working directory
Documents/ documentation
IAEA1420/02:
ENDF/ selected evaluated nuclear data files in ENDF-6 format
GENDF/ multigroup cross-section data in GENDF format
ACE/ pointwise continuous-energy cross-section data in ACE format for MCNP
calculations at different temperatures
MATXS/ multigroup cross-section data in MATXS format
Inputs/ NJOY inputs are given by processed material
Programs/ auxiliary programs and batch procedures
acedop/ SIGACE program
Documents/ documentation
- Z. Data.